ML23291A405
| ML23291A405 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/12/2023 |
| From: | Susquehanna |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML23291A105 | List:
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| References | |
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| Download: ML23291A405 (59) | |
Text
SSES-FSAR Text Rev. 56 FSAR Rev. 68 3.2-1 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.
SSES-FSAR Text Rev. 56 FSAR Rev. 68 3.2-2 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.
SSES-FSAR Text Rev. 56 FSAR Rev. 68 3.2-3 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.
SSES-FSAR Text Rev. 56 FSAR Rev. 68 3.2-4 (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)
(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
SSES-FSAR Text Rev. 56 FSAR Rev. 68 3.2-5
- 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.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 1 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Reactor System Reactor vessel Reactor vessel support skirt Reactor vessel appurtenances, pressure retaining portions CRD housing supports Reactor internal structures, engineered safety features Reactor internal structures, other Control rods Control rod drives Core support structure Power range detector hardware - pressure retaining portions Fuel assemblies 4.5 GE GE GE GE GE GE GE GE GE GE AREVA C
C C
C C
C C
C C
C C
C A
NA A
NA NA N/A N/A N/A N/A A
N/A 1
1 1
2 2
Other 2
2 2
1 2
III-A III-A III-A X
X X
X III-2 III-1 III-1 X
I I
I I
I N/A I
I I
I I
Y Y
Y Y
Y N
Y Y
Y Y
Y Nuclear Boiler System Vessels, level instrumentation condensing chambers Vessels, air accumulators Air supply check valves, piping downstream of air supply check valve Piping, relief valve discharge Piping, main steam, within outermost Isolation valve Pipe supports, main steam Pipe restraints, main steam Piping, other within outermost isolation valves Piping, instrumentation beyond outermost isolation valves Safety/relief valves Valves, main steam isolation valves Quenchers and quencher supports Valves, other, isolation valves within primary containment Feedwater piping inside isolation valves Valves, instrumentation beyond outermost isolation valves Mechanical modules, instrumentation with safety function Electrical modules with safety function Cable, with safety function 4.5 GE P
P P
GE P
P P
P GE GE P
P P
P GE GE P
C C
C C
C C
C C
R,T C
C,R C
C C
C,R,T C
C C
A C
C C
A NA NA A
B A
A C
A A
B NA NA NA 1
3 3
3 1
1 1
1 2
1 1
3 1
1 2
2 2
2 III-1 III-3 III-3 III-3 III-1 III-1 X
III-1 III-2 III-1 III-1 III-3 III-1 III-1 111-2 X
IEEE-279/323 IEEE-279/323/383 I
I I
I I
I I
I Note 20 I
I I
I I
I I
I NA Y
Y Y
Y Y
Y Y
Y N
Y Y
Y Y
Y Y
Y Y
Y 10 10 10 5
15
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 2 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Recirculation System Piping Piping suspension, recirculation line Pipe restraints, recirculation line Pumps Valves Pump Motors Electrical modules, with safety function Cable with safety function Piping 5
P C
C C
C C
C C
C,R T
A NA NA A
A NA NA NA D
1 1
2 1
1 2
2 2
Other III-1 III-1 X
III-1 III-1 NEMA/NEC IEEE-279/323 IEEE-279/323/383 B31.1.0 I
I NA I
I I
I NA NA Y
Y Y
Y Y
N Y
Y N
10 61 10 15 CRD Hydraulic System Valves, scram discharge volume lines Valves, insert and withdraw lines Valves, other Piping, scram discharge volume lines Piping, insert and withdraw lines Piping, other Hydraulic control unit Electrical modules, with safety function Cable, with safety function 4
P/GE P/GE P
P P
P GE GE P
R R
R R,C C,R R
R R
C,R B
B D
B B
D NA NA NA 2
2 Other 2
2 Other 2
2 2
III-2 III-2 B31.1.0 III-2 III-2 B31.1.0 NA IEEE-279/323 IEEE-279/323/383 I
I NA I
I NA I
I NA Y
Y N
Y Y
N Y
Y Y
10 35 50 12 15 ENGINEERED SAFETY FEATURES Standby Liquid Control System Standby liquid control tank Pump Pump motor Valves, explosive Valves, isolation and within Valves, beyond isolation valves Piping, within isolation valves Piping, beyond isolation valves Electrical modules, with safety function Cable, with safety function 9.3.5 GE GE GE GE P
P P
P GE P
R R
R R
C,R R
C R
R R
B B
NA B
A B
A B
NA NA 2
2 2
2 1
2 1
2 2
2 API 650 NP&V-II X
NP&V-II III-1 III-2 III-1 III-2 IEEE-279/323 IEEE-279/323/383 I
I I
I I
I I
I I
NA Y
Y Y
Y Y
Y Y
Y Y
Y 66 10 10 10 10 15
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 3 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments RHR System Heat exchangers, primary side Heat exchangers, secondary side Piping, within outermost containment isolation valves Piping, beyond outermost containment isolation valves Containment spray line piping within isolation valve Containment spray line piping beyond isolation valve Pumps Pump motors Reactor vessel head spray line piping inside second isolation valve Reactor vessel head spray line piping beyond second isolation valve Valves, isolation LPCI line Valves, isolation, other Valves, beyond isolation valves Mechanical modules Electrical modules, with safety function Cable, with safety function 5.4.7 GE GE P
P P
P GE GE P
P P
P P
GE GE P
R R
C R
C,R R
R R
C R
C,R C,R R
R R
C,R B
C A
B B
B B
NA A
B A
B B
NA NA NA 2
3 1
2 2
2 2
2 1
2 1
2 2
2 2
2 III-2 III-3 III-1 III-2 III-2 III-2 NP&V-II NEMA/NEC III-1 III-2 III-1 III-2 III-2 IEEE-279/323 IEEE-279/323/383 I
I I
I I
I I
I I
I I
I I
I I
NA Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y 10 10 10 10 15 Core Spray Piping, within outermost isolation valves Piping, beyond outermost isolation valves Pumps Pump motors Valves, containment isolation and within containment Valves, beyond outermost containment isolation valves Electrical modules with safety function Cable, with safety function 6.3 P
P GE GE P
P GE P
C R,C R
R C
R R
R A
B B
NA A
B NA NA 1
2 2
2 1
2 2
2 III-1 III-2 NP&V-II NEMA/NEC III-1 III-2 IEEE-279/323 IEEE-279/323/383 I
I I
I I
I I
NA Y
Y Y
Y Y
Y Y
Y 10 10 10 10 15
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 4 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments High Pressure Coolant Injection Piping, and valves within outermost containment isolation valve (turbine inlet steam line and instrument lines only)
Piping and valves within outermost containment isolation valves (other than above)
Piping, return test line to condensate storage tank beyond second isolation valve Piping, beyond outermost containment isolation valve, other Pumps HPCI turbine Valves, beyond isolation valves, motor operated Valves, other Electrical modules, with safety function Cable with safety function 6.3 P
P P
P GE GE P
P GE P
C C
R,O R
R R
R R
R R
A B
D B
B NA B
B NA NA 1
2 Other 2
2 2
2 2
2 2
III-1 III-2 B31.1.0 III-2 NP&V-II X
III-2 III-2 IEEE-279/323 IEEE-279/323/383 I
I NA I
I I
I I
I NA Y
Y N
Y Y
Y Y
Y Y
Y 10,28 10,28 10 11,38 10 10 15 RCIC System Piping, and valves within outermost containment isolation valves (turbine inlet steam line and instrument lines only)
Piping and valves within outermost containment isolation valves (other than above)
Piping, and valves beyond outermost containment isolation valves (except for other shown below)
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 RCIC barometric condenser RCIC condensate pump and condenser vacuum pump Pumps RCIC turbine Electrical modules, with safety function Cable, with safety function 5.4.6 P
P P
C,R C,R R
O,R R
R R
R R
R,C A
B B
D D
D B
NA NA NA 1
2 2
Other Other Other 2
2 2
2 III-1 III-2 III-2 B31.1.0 B31.1.0 X
NP&V-II X
IEEE-279/323 IEEE-279/323/383 I
I I
NA NA NA I
I I
NA Y
Y Y
N N
N Y
Y Y
Y 10,28 10,28 10 11,38 15
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 5 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments FUEL STORAGE AND HANDLING 9.1 Storage Equipment New fuel storage racks Spent fuel storage racks (includes storage of control rods, control rod guide tubes, defective fuel storage containers, out-of core sipping containers and channels)
Control Rod Storage Hangers (includes control rod blades)
Channel storage racks In vessel racks Defective fuel storage containers 9.1.1, 9.1.2, 9.1.4 GE P
R R
R R
R NA NA NA NA NA NA 2
2 2
Other Other 3
AWS D1.1 AISI/AA AISC AWS DI.I AWS DI.I AWS DI.I I
I I
NA I
NA Y
Y Y
N Y
Y Independent Spent Fuel Storage Facility (ISFSI)
Horizontal Storage Modules Dry Shielded Canisters HI-STORM FW Overpacks Multi-Purpose Canisters TNW TNW HI HI ISFSI ISFSI ISFSI ISFSI NA NA NA NA Other Other Other Other ACI 349 ACI 318 ASME NA NA I
I I
I Y
Y Y
Y 62 62,63 62 62 Fuel Servicing Equipment Fuel preparation machine New fuel inspection stand General purpose grapple Irradiated fuel shipping cask Jib cranes Railway bay unloading crane 9.1.4 GE GE GE NA P
P R
R R
R R
R NA NA NA NA NA NA 3
Other 2
Other Other Other X
X X
49CFR 173.393, 49CFR 173.396 CMAA 70/B30.10 CMAA 70/B30.10 I
NA I
I NA NA Y
N Y
Y N
N 45
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 6 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Reactor Vessel Servicing Equipment Main Steam Line Plugs (REM*Light Model)
Dryer & separator sling [Supplied with Nuclear System]
RPV head strongback/carousel Service platform Control rod grapple Reactor building crane Main Steam Line Plugs (Spring Disk Model) [Wetlift]
MSL Plugs Restraint Ring [Wetlift]
Watertight Hook Box [Wetlift]
Rigid Pole Handling System [Wetlift]
Refuel Floor Auxiliary Platform (RFAP)
Jet Pump Plugs 360 Degree Refuel Work Platform 9.1.4 GEH GE GE GE GE P
R R
R R
R R
R R
R R
R R
NA NA NA NA NA NA NA NA NA NA NA NA NA Other Other Other Other Other Other Other Other Other Other Other Other Other AA X
X X
X CMAA 70/B30.20 X
X X
X CMAA-74 X
AISC I
NA NA NA NA I
I I
NA NA NA L
NA Y
Y Y
N Y
Y Y
Y Y
Y Y
Y Y
48, 58 53 73 23 57,58 57 59 60 23 69 23 Refueling Equipment Refueling platforms Fuel grapples 9.1.4 GE GE R
R NA NA 2
Other X
X I
NA Y
N 23 Under Reactor Vessel Service Equipment Equipment handling platform CRD handling equipment 9.1.4 GE NES C
C NA NA Other Other X
X NA NA N
N
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 7 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Fuel Pool Cooling & Cleanup System Heat Exchangers Pumps Skimmer surge tanks Filter demineralizer vessels Resin and precoat tanks Cooling loop piping and valves downstream of Valve 1-53-001, 2-53-001 RHR intertie piping and valves Emergency service water makeup piping and valves Other piping and valves Cooling loop piping upstream of Valve 1-53-001, 2-53-001 from skimmer surge tank 9.1.3 P
P P
P P
P P
P P
P R
R R
R R
R R
R R
R C
C C
D D
C C
C D
C Other Other 3
Other Other Other 3
3 Other 3
III-3, TEMA C III-3 III-3 VIII-1 API-650 III-3 III-3 III-3 B31.1.0 III-3 NA NA I
NA NA NA I
I NA I
N N
Y N
N N
Y Y
N Y
19,31 46,55 19,31,56 RADIOACTIVE WASTE MANAGEMENT 11 Liquid Waste Management Systems Centrifugal pumps Atmospheric tanks Filter vessel Demineralizer vessel Evaporator, complete system Laundry drain filter Liquid and chemical waste piping and valves Laundry drain waste and auxiliary piping and valves 11.2 P
P P
P P
P P
P R/RW/T RW/T RW RW RW RW R/RW/T RW D
D D
D D
D D
D Other Other Other Other Other Other Other Other III-3**
VIII-1/III-3 VIII-1 III-3**
III-3**/MA B VIII-1 B31.1 B31.1 NA NA NA NA NA NA NA NA N
N N
N N
N N
N 31,22 31,22 31,22 31,22 31,22 31,22
- 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.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 8 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Offgas System Heat exchangers Recombiner Condenser-Unit 2 & Common Recombiner Condenser-Unit 1 Recombiner Preheater Motive Steam Jet Condenser Condensate Cooler Charcoal Treatment Inlet Precooler Chiller Piping Valves, flow control Valves, other Motors HEPA filters Pressure vessels Recombiner Vessel-Unit 1, 2 &
Common Motive Steam Jet Ejector Charcoal Guard Bed Charcoal Adsorber Vessels 11.3 P
P P
P P
P P
T T
T T
T RW T
T RW RW D
D D
D NA D
D D
Other Other Other Other Other Other Other VIII-1 III/VIII-1 III-3 III-3 VIII-1 VIII-1 VIII-1 B31.1.0 B31.1.0 B31.1.0 NEMA-MG1 VIII-1 VIII-3 VIII-1 VIII-1 VIII-1 NA NA NA NA NA NA NA N
N N
N N
N N
22,31 50 10,22,31 22,31 10,22,31 22 22,31 22,31
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 9 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Solid Waste Management System Centrifugal pumps Regeneration waste transfer pumps Solidification system pumps Filter demineralizer backwash tanks Phase separators Regen. Waste surge tanks Waste mixing tanks Waste containers, HSA Waste containers, LSA Solid radwaste collecting piping and valves Solidification system piping and valves Aux. piping and valves Backwash tank drain lines 11.4 P
P P
P P
P P
PL PL P
P P
P RW T
RW R
RW T
RW RW RW R/T/RW RW R/T/RW R/T/RW D
D D
D D
D D
NA NA D
D D
D Other Other Other Other Other Other Other Other Other Other Other Other Other III-3 Manuf. Standard Manuf. Standard III-3 VIII-1 VIII-1 VIII-1 D1.1,D1.1 D1.1 B31.1 B31.1 B31.1 B31.1 NA NA NA NA NA NA NA NA NA NA NA NA NA N
N N
N N
N N
N N
N N
N N
19,31,22 22 22 22 31,22 22 22 31,22 22 22 Reactor Water Cleanup System Filter demineralizer vessels Regenerative and nonregenerative heat exchangers Piping and valves within reactor coolant pressure boundary (RCPB)
RWCU Recirc Pumps Piping and valves beyond outermost containment isolation valve up to valves F104, F042, F034, F035 Piping and valves beyond valves F104 and F042 to feedwater system Piping and valves beyond F034 and F035 Mechanical modules 5.4.8 GE GE P
GE P
P P
GE R
R R,C R
R R
R R
C C
A C
C B
D NA Other Other 1
Other Other 2
Other Other III-3 III-3 III-1 III-3 III-3 III-2 B31.1.0 X
NA NA I
NA NA I
NA NA N
N Y
N N
Y N
N 26 10
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 10 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments WATER SYSTEMS RHR Service Water and Spray Pond System Cross connect piping to RHR system, within second automatic isolation valve Piping and valves, chemical treatment makeup water, blowdown Piping, other RHR SW Pumps Pump motors Valves, isolation Valves, other Electrical modules, with safety function Cable, with safety function Heat exchangers Piping drain pumps 9.2.6 P
P P
P P
P P
P P
P P
R O
O,R,SW SW SW C,R O,R,SW O,R,SW O,R,SW R
O B
D C
C NA B
C NA NA C
NA 2
Other 3
3 3
2 3
3 3
3 Other III-2 B31.1.0 III-3 III-3 IEEE-323/344 III-2 III-3 IEEE-279/323 IEEE-279/323/383 III-3/TEMA C NA I
NA I
I I
I I
I NA I
NA Y
N Y
Y Y
Y Y
Y Y
Y N
15 Emergency Service Water System Piping up to RHR SW system 9.2.5 P,GH O,G,R, T,CS, EG,SW C
3 III-3 1
Y Piping supports in Diesel Generator E building Pumps Pump Motors Valves Electrical modules with safety function Cable, with safety function Heat exchangers GH P
P P,GH P
P P,GH EG SW SW O,G,R, T,CS, SW,EG O,G,R,T, CS,SW O,G,R, SW,T,CS R,T,G, CS,EG C
C NA C
NA NA C
3 3
3 3
3 3
3 III-3 III-3 IEEE-323/344 III-3 IEE-279/323 IEEE-279/323/383 III-3 I
I I
I I
NA I
Y Y
Y Y
Y Y
Y 15 52
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 11 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Reactor Building Closed Cooling Water System Piping and valves forming part of containment boundary Piping and valves, other Tanks Heat exchangers Pumps 9.2.2 P
P P
P P
R,C R,C,T R
R R
B D
D D
D 2
Other Other Other Other III-2 B31.1.0 VIII-1 VIII-1/TEMA C Hyd.I I
NA NA NA NA Y
N N
N N
24 Plant Service Water System Piping and valves forming part of the SW/ESW Interface Piping and valves, other Heat Exchangers Pumps 9.2.1 P
P P
P R,C R,C,T CT CW C
D D
D 3
Other Other Other III-3 B31.1.0 VIII-1/TEMA C Hyd.I I
NA NA NA Y
N N
N 24 Turbine Building Closed Cooling Water System Piping and valves Heat exchangers Tanks Pumps 9.2.3 P
P P
P T
T T
T D
D D
D Other Other Other Other B31.1.0 VIII-1/TEMA C VIII-1 Hyd.I NA NA NA NA N
N N
N 24 Circulating Water System Piping Condenser Pumps Valves Cooling tower Piping, Non-pipe Class Valves, Non-pipe Class 9.2 P
P P
P P
P P
O,T,CW T
CW T,CW O
O,T,CW T,CW D
D NA D
NA NA NA Other Other Other Other Other Other Other AWWA-C201 HEI VIII-1/Hyd.I AWWA-C201 & C504 NONE AWWA AWWA NA NA NA NA NA NA NA N
N N
N N
N N
24
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 12 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments 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
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 13 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Diesel Generator E Systems Diesel Generator Diesel Engine intercoolers Engine mounted piping and valves for lube oil, jacket water, fuel oil, intake/exhaust, starting air systems required to perform a safety function Intake/Exhaust piping and expansion joints Auxiliary skid mounted piping, valves, filters and strainers Jacket water, lube oil, fuel oil motor driven pumps Jacket water and lube oil pump motor Fuel oil pump motor Jacket water Stand Pipe Jacket water, lube oil, fuel oil, heat exchangers Jacket water and lube oil heaters Fuel oil transfer system piping and valves (except vent line and portion of fill line)
Fuel oil transfer pump Fuel oil transfer pump motor Fuel oil day tank Fuel oil storage tank Fuel oil transfer system strainer Electrical modules with safety function Cable, with safety functions Air receiver skid piping and valves Air receivers Air Compressors Engine mounted equipment required to perform a safety function Engine mounted equipment and valves not required to perform safety function 9.5.4,-5,-
.6,-.7,-.8 GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH GH EG EG EG EG EG EG EG EG EG EG EG EG,O EG EG EG O
EG EG EG,O EG EG EG EG EG N/A C
N/A C
C C
N/A N/A C
C N/A C
C N/A C
C C
N/A N/A C
C D
N/A N/A 2
3 Other 3
3 3
Other 3
3 3
Other 3
3 3
3 3
3 3
3 3
3 Other 3
Other DEMA III-3 X
III-3 III-3 III-3 IEEE-323,-344 IEEE-323,-344 III-3 III-3 IEEE-323,-344 III-3 III-3 IEEE-323,-344 III-3 III-3 III-3 IEEE-323,-344 IEEE-383 III-3 III-3 NA DEMA DEMA I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I I
NA I
N/A Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y Y
N Y
N
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 14 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments 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 (or ASME AG-1-1997)71 MIL-F-51079A (or ASME AG-1-1997)71 UL-586 I
Y 16 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 Instrumentation Fans Prefilters HEPA filters Adsorber units Dampers, isolation Dampers, flow distribution Ductwork Coils, cooling Electric heating coils P
P P
P P
P P
P P
P P
CS CS CS CS CS CS CS CS CS CS CS NA NA NA NA NA NA NA NA NA C
3 3
3 3
3 3
3 3
3 3
NEMA MG1 IEEE-344/323 IEEE-279/323 AMCA UL Class I MIL-F-51068C (or ASME AG-1-1997)71 MIL-F-51079 (or ASME AG-1-1997)71 AACC CS-8 ANSI N509-80 Table 5-1 AMCA AMCA AISI, AWS ARI NEC,NEMA I
I I
I I
I I
I I
I I
Y Y
Y Y
Y Y
Y Y
Y Y
Y
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 15 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Relay Room, Cable Spreading, Battery Room HVAC, and HVAC Equipment Room Motors Fans Prefilters Coils, heating, electric Coils, cooling Dampers Ductwork Piping & valves Instrumentation 9.4.1 P
P P
P P
P P
P P
CS CS CS CS CS CS CS CS CS NA NA NA NA NA NA NA C
NA 3
3 3
3 3
3 3
3 Other NEMA MG1 IEEE-344/323 AMCA UL Class 1 NEC, NEMA ARI AMCA AISI B31.1 IEEE-279/323 I
I I
I I
I I
I I
Y Y
Y Y
Y Y
Y Y
Y SGTS Equipment Room H&V Motors Fans Heaters, electric Dampers Ductwork Instrumentation 9.4.1.1.5 P
P P
P P
P CS CS CS CS CS CS NA NA NA NA NA NA 3
3 3
3 3
3 NEMA MG1 IEEE-344/323 AMCA NEC 424 NFPA 90A & 90B AMCA AISI,AWS IEEE-279/323 I
I I
I I
Y Y
Y Y
Y
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 16 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments REACTOR BUILDING Reactor Building HVAC (Zone I and Zone II)
Includes Steam Tunnel Cooling, U2 Elec. Eq. Room H&V and U1 Remote Shutdown Room Ventilation 9.4 Motors P
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 RDT M-16-1T NA N
Coils, Coiling - Chilled & Service Water P
R NA Other ARI NA N
Coils, Heating P
Dampers, Isolation, & Ductwork Connected to RB Recirculation System P
R NA 3
AMCA, SMACNA, AISI, AWS I
Y Dampers, Other P
R NA Other AMCA NA N
Ductwork - Other P
R NA Other SMACNA, AISI, AWS NA N
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 Motors Fans Filters Coils, cooling Piping and valves 9.4.2 P
P P
P P
R R
R R
R NA NA NA NA C
3 3
3 3
3 IEEE-323/344 AMCA NA ARI III-3 I
I I
I I
Y Y
Y Y
Y
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 17 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Emergency SWGR and Load Center Rooms Motors Fans Prefilters Coils, cooling U1-CSCW, U2-DX & condenser Coils Cooling - RBCW, Both Units Dampers Ductwork Piping & Valves, Unit 1-CSCW, Unit 2-Refrigeration Instrumentation 9.4 P
P P
P P
P P
P P
R R
R R
R R
R R
R NA NA NA C
NA NA NA C
NA 3
3 3
3 3
3 3
3 Other NEMA MG1 IEEE-344/323 AMCA UL Class 1 III-3 ARI AMCA AISI,AWS III-3 IEEE-279/323 I
I I
I I
I I
I I
Y Y
Y Y
Y Y
Y Y
Y Also See Plant Chilled Water System Refueling Floor HVAC (Zone III)-Both Units Motors Fans Prefilters HEPA filters Adsorber units Coils, Cooling (RBCW) & Heating Damper-Isolation and Ductwork Connected to RB Recirculation System Ductwork - Other Dampers - Other Piping & Valves Also See Plant Chilled Water System 9.4.6 P
P P
P P
P R
P P
P R
R R
R R
R R
R R
R NA NA NA NA NA NA NA NA NA NA Other Other Other Other Other Other 3
Other Other Other NEMA MG1 AMCA UL Class 1 MIL-F-51079 (or ASME AG-1-1997)71 MIL-F-51068C (or ASME AG-1-1997)71 RDT M-16-1T AACC CS-8 ARI AMCR,SMACNA AISI,AWS SMACNA/AISI AMCA B31.1 NA NA NA NA NA NA I
NA NA NA N
N N
N N
N Y
N N
N
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 18 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Drywell Atmosphere Recirculation and Cooling System Motors Fans Coils, cooling Ductwork Dampers Piping and valves 9.4.5 P
P P
P P
P C
C C
C C
C NA NA NA NA NA NA Other Other Other Other 3
Other IEEE-334/
NEMA MG1 AMCA 210 ARI AISI,AWS AMCA B31.1 I
I I
I I
NA Y
Y Y
Y Y
N 65 65 65 65 65 Combustible Gas Control System Primary Containment Atmosphere monitoring system (PCAMS)
Piping valves forming Containment Penetration Boundary P
P C,R C,R B,D B
2 2
IEEE-344 III-2 IEEE-344 III-2 I
I Y
Y 10, 41 69 Standby Gas Treatment & RB Recirculation System Motors Fans Prefilters Demisters HEPA filters Adsorber units Ductwork Dampers Piping Valves Electric heaters Control panels P
P P
P P
P P
P P
P P
P CS CS CS CS CS CS CS CS CS CS CS CS NA NA NA NA NA NA NA NA C
C NA NA 3
3 3
3 3
3 3
3 3
3 3
3 IEEE-323/344 AMCA UL Class 1 MSAR 71-45 MIL-F-51079 (or ASME AG-1-1997)71 MIL-F-51068C (or ASME AG-1-1997)71 AACC CS-8 ANSI N509-80 Table 5-1 AISI,AWS AMCA NFPC B31.1 NEMA & NEC NEMA, IEEE 323 I
I I
I I
I I
I I
I I
I Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y 16 16 16 16 16 16 16 16 16 16
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 19 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Radwaste Building HVAC Motors Fans Prefilters HEPA filters Coils, cooling & heating Adsorber units Ductwork Dampers Electric heating coil 9.4.3 P
P P
P P
P P
P P
RW RW RW RW RW RW RW RW RW NA NA NA NA NA NA NA NA NA Other Other Other Other Other Other Other Other Other NEMA MG1 AMCA UL Class 1 MIL-F-51079A (or ASME AG-1-1997)71 MIL-F-51068C (or ASME AG-1-1997)71 ARI & UL MIL-C-17605 RDT M-16-1T SMACNA AMCA NEC NA NA NA NA NA NA NA NA NA N
N N
N N
N N
N N
Diesel Generator Buildings HVAC Motors Fans Ductwork Dampers 9.4.7 P,GH P,GH P,GH P,GH G,EG G,EG G, EG G,EG NA NA NA NA 3
3 3
3 NEMA MG-1 IEEE344 AMCA AISI,AWS AMCA I
I I
I Y
Y Y
Y Turbine Building HVAC Motors Fans Filters Coils, cooling Ductwork Dampers Electric heating coil 9.4.4 P
P P
P P
P P
T T
T T
T T
T NA NA NA NA NA NA NA Other Other Other Other Other Other Other NEMA MG1 AMCA NA ARI SMACNA AMCA NEC,NEMA NA NA NA NA NA NA NA N
N N
N N
N N
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 20 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Emergency Service Water Pumphouse Ventilation Motors Fans Ductwork Dampers 9.4.8 P
P P
3 3
3 NEMA MG1 IEEE344 AMCA AISI,AWS AMCA I
I I
I Y
Y Y
Y Administration Building HVAC Motors Fans Prefilters Dampers Coils, cooling Coils, heating Ductwork P
P P
P P
P P
O O
O O
O O
O NA NA NA NA NA NA NA Other Other Other Other Other Other Other NEMA MG1 AMCA UL Class 1 AMCA ARI NEC, NEMA SMACNA NA NA NA NA NA NA NA N
N N
N N
N N
Main Steam and Power Conversion System Main Steam System Main steam piping to turbine stop valves and branch line piping up to and including first valve.
Main Steam piping from and including the turbine stop valve to turbine HP casing and branch line piping up to and including first valve.
Steam piping and valves, other 10.3 P
P P
R,T T
T B
D D
2 Other Other III-2 B31.1.0 B31.1.0 NA NA NA N
N N
20 9,18,33 Main Condenser Evacuation System Piping and components Heat exchangers Air ejectors 10.4.2 P
P P
T,RW T
T D
D D
Other Other Other B31.1.0 VIII-1 B31.1.0 NA NA NA N
N N
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 21 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Condensate and Feedwater System Reactor feedwater piping and valves, RPV to outermost isolation valve Reactor feedwater, piping and valves, other Steam piping to feedwater pump turbine Crossover (low pressure) piping Bypass (high pressure) piping, downstream of first isolation valve Condensate piping and valves Heat exchangers Pressure Vessels Pumps, feedwater and condensate 10.4.7 P
P P
P P
P P
P C,R R,T T
T T
T T
T A
D D
D D
D D
NA 1
Other Other Other Other Other Other Other III-1/III-2 B31.1.0 B31.1.0 B31.1.0 B31.1.0 VIII-1/TEMA C VIII-I Hyd.I I
NA NA NA NA NA NA NA Y
N N
N N
N N
N 32 24 Condensate Cleanup System Piping and valves Pressure vessels 10.4.6 P
P T
T D
D Other Other B31.1.0 VIII-1 NA NA N
N Condensate Storage and Transfer System Tanks Piping and valves Pumps 9.2.10 P
P P
O RW,O,T,R T
D D
D Other Other Other D100 B31.1.0 Hyd.I NA NA NA N
N N
24 Turbine Gland Sealing System Steam seal evaporator (SSE)
Steam Packing Exhauster Piping and valves SSE Drain Tank 10.4.3 P
P P
P T
T T
T D
D D
D Other Other Other Other VIII-1 X
B31.1.0/X VIII-1 NA NA NA NA N
N N
N
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 22 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Auxiliary Steam System Auxiliary boilers Piping and valves 10.4.11 P
P T
T D
D Other Other I
B31.1.0 NA NA N
N Main Chlorination System Pumps Motors Piping and valves 9.2.8 P
P P
CA CA CA D
NA D
Other Other Other Hyd.I NEMA MG1 B31.1.0 NA NA NA N
N N
24 Lube Oil System Batch oil tank Reservoirs Pumps Motors Conditioners Heat Exchangers Piping and valves 10.2 P
P P
P P
P P
O T
T T
T T
T D
D D
NA NA D
D Other Other Other Other Other Other Other VIII-1 API-620 VIII/Hyd.I NEMA MG1 NA VIII/TEMA C B31.1.0 NA NA NA NA NA NA NA N
N N
N N
N N
24 Instrumentation and Control Systems Reactor Instrumentation Reactor Protection System All portions that must operate to control and safety shut down the reactor to a hot shutdown condition (Electronic modules)
Cable with safety function Alternate Rod Injection All portions that must operate to control and safely shut down the reactor to a hot shutdown condition (Electronic modules) Cable with safety function 7.2 GE P
P C,R,T C,R,T R
NA NA NA 2
2 2
IEEE-279 IEEE-279/383 10CFR50.62 I
NA NA Y
Y Y
15 47
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 23 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Neutron Monitoring System Guide Tubes, TIP (from Ball/Shear valve assembly through penetration to first connection)
Guide Tubes, TIP (remainder of tube after first connection)
Valves, isolation, TIP subsystem Electrical modules, IRM and APRM Cable, IRM and APRM, with safety function GE GE GE GE P
C,R C,R C,R C,R C,R B
B B
NA NA 2
2 2
2 2
III-2 III-2 III-2 IEEE-279 IEEE-279/383 I
NA I
I NA Y
Y Y
Y Y
15 Non-Nuclear Instrumentation All portions that input to the reactor protection system All portions that input to the engineered safety feature actuation system GE P/GE C,R C,R NA NA 2
2 IEEE-279 IIII-279 I
I Y
Y Engineered Safety Features Actuation System All portions 7.3 GE C,R NA 2
IEEE-279 I
Y Engineered Safety Features Systems (controls and instrumentation required for safety associated with each actuated system)
Emergency core cooling system Containment isolation system Containment purge systems (pressure boundary only)
Emergency diesel generator systems Main steam line break detection system 7.3 GE P
P P,GH C,R C,R C,R G,EG C,R,T NA NA NA NA NA 2
2 2
2 2
IEEE-279 IEEE-279 IEEE-279 IEEE-279 IEEE-279 I
I I
I I
Y Y
Y Y
Y Controls and Instrumentation Associated with Safe Shutdown Systems PCAMS 7.4 P
C,R B,D 2
IEEE-279 I
Y
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 24 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Instrumentation Associated with Other Systems Required for Safety Spent fuel pooling cooling system Fuel handling area ventilation isolation system Control room panels Local instrument racks associated with safety related equipment 7.6 P
P P
P R
R CS ALL NA NA NA NA 2
2 2
2 IEEE-279 IEEE-279 IEEE-279 IEEE-279 I
I I
I Y
Y Y
Y Instrumentation Associated with Systems Not Required for Safety Seismic Instrumentation Area radiation monitoring 7.7 P
P ALL ALL NA NA Other Other NA NA I
NA Y
N Leak Detection Instrumentation Temperature elements Differential temperature switch Differential flow indicator Pressure switch Differential pressure indicator switch Differential flow summer GE GE GE GE GE GE C,R,T C,R CS C,R CS CS 2
2 2
2 2
2 IEEE-323 IEEE-323 IEEE-323 IEEE-323 IEEE-323 IEEE-323 I
I I
I I
I Y
Y Y
Y Y
Y 39 39 39 39 39 39 Process Radiation Monitors Electrical modules, main steam line and reactor building ventilation monitor Cable, main steam line and reactor building ventilation monitors GE P
R R
NA NA 2
2 IEEE-323 IEEE-279/323/383 I
NA Y
Y 15
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 25 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments ELECTRIC SYSTEMS 8
Engineered Safety Features AC Equipment 4.16 kV switchgear 480 V load centers 480 V motor control centers 8.3 P,GH P,GH P,GH R,G,EG R,EG R,G,EG NA NA NA 2
2 2
IEEE-308/323/344 IEEE-308/323/344 IEEE-308/323/344 I
I I
Y Y
Y Engineered Safety Features DC Equipment 125 V and 250 V station batteries and racks, battery chargers 125 V switchgear and distribution panels 8.3 P,GH P,GH CS,EG CS,EG NA NA 2
2 IEEE-308/323/344 IEEE-308/323/344 I
I Y
Y 120 V Vital AC System Equipment Static inverters 120 V distribution panels 8.3 P
P CS CS,R,EG NA NA 2
2 IEEE-308/323/344 IEEE-308/323/344 NA I
Y Y
Electric Cables for ESF Equipment 5 kV power cables 600 V power cables Control and instrumentation cables 8.3 P
P P
ALL ALL ALL NA NA NA 2
2 2
IEEE-323/383 IEEE-323/383 IEEE-323/383 NA NA NA Y
Y Y
15 15 15 Miscellaneous Electrical Primary containment building electrical penetration assemblies Conduit supports, safety related Tray supports, safety related Emergency lighting systems Emergency communications systems 8
P P
P P
P C
ALL ALL ALL ALL NA NA NA NA NA 2
2 2
2 Other IEEE-317/344/383 IEEE-344 IEEE-344 IEEE-344 NONE I
I I
I NA Y
Y Y
Y N
15 15 74
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 26 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments AUXILIARY SYSTEMS Compressed Air and Instrument Gas Systems Compressors Pressure Vessels, for safety related equipment Pressure vessels, not for safety related equipment Piping and valves forming part of containment boundary Piping and valves, safety related Piping and valves, other Nitrogen storage bottles Piping and supports - Diesel Generator E Building 9.3.1 P,PL P
P,PL P
P P
P GH T,R,I,RW C,R ALL C,R C,R ALL R
EG NA C
D B
C D
NA D
Other 3
Other 2
3 Other Other Other NONE III-3 VIII-1 III-2 III-3 B31.1.0 DOT B31.1 NA I
NA I
I NA I
I N
Y N
Y Y
N N
N 64 49 Sampling Systems Sample coolers Piping and valves on III-1 systems Piping and valves on III-2 systems Piping and valves on III-3 systems Piping and valves, other systems Piping and valves, containment penetration, isolation 9.3.2 P, PL P
P P
P P
R,T,RW C
R R
R,T,RW C
D A
B C
D A
Other 1
2 3
Other 1
VIII-1 TEMA C III-1 III-2 III-3 B31.1.0 III-1 NA I
I NA NA I
N Y
Y Y
N Y
10 10 68 10 10 Fire Protection System Tanks Pumps, piping and water system components Gas system components (CO and Halon 1301)
Fire and smoke detection and alarm system Piping and supports - Diesel Generator E Building 9.5.1 P
P P
P GH O
ALL CS ALL EG D
NA NA NA NA Other Other Other Other Other API-650/D100 NFPA/NEPIA NFPA/NEPIA NFPA/NEPIA NFPA/NEPIA NA NA NA NA I
N N
N N
N 49
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 27 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments General External Hydrogen System Vessels Piping Valves P
P P
T T
T D
D D
Other Other Other VIII-1 B31.1.0 B31.1.0 NA NA NA N
N N
Nitrogen System Vessels Piping Valves P
P P
O R,O,RW O
D D
D Other Other Other VIII-1 B31.1.0 B31.1.0 NA NA NA N
N N
Reactor Building Chilled Water System 9.2.12.2 Chillers Chilled Water Heat Exchangers P
P R
R D
D Other Other X/B9.1 VIII/ TEMA C NA NA N
N Pumps P
R D
Other VIII/ Hyd.I NA N
24 Piping Valves Isolation, Chilled Water to Primary Containment P
P R
R D
B Other 2
B31.1 III-2 NA I
N Y
Remainder P
R D
Other B31.1 NA N
Turbine Building Chilled Water System 9.2.12.3 Chillers Chilled Water Heat Exchangers P
P T
T D
D Other Other X/B9.1 VIII/TEMA C NA NA N
N Pumps P
T D
Other VIII/ Hyd.I NA N
24 Piping Valves P
P T
T D
D Other Other B31.1 B31.1 NA NA N
N
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 28 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Radwaste Building Chilled Water System 9.2.12.4 Chillers Chilled Water Heat Exchangers P
P RW RW D
D Other Other X/B9.1 VIII/TEMA C NA NA N
N Pumps P
RW D
Other VIII/Hyd.I NA N
24 Piping Valves P
P RW RW D
D Other Other B31.1 B31.1 NA NA N
N Control Structure Chilled Water System 9.2.12.1 Centrifugal Water Chillers - (Except Condenser)
Centrifugal Water Chillers - Condenser Heat exchangers Pumps Motors Piping Valves P
P P
P P
P P
C D
D NA D
D 3
3 3
3 3
3 3
VIII III-3 VIII-1/TEMA C VIII-1/L Hyd.I IEEE-323/344 B31.1 B31.1 I
I I
I I
I I
Y Y
Y Y
Y Y
Y Equipment and Floor Drains Piping, radioactive Piping, nonradioactive Piping & valves, containment penetrating isolation Piping and supports in Diesel Generator E Building -
nonradioactive 9.3.3 P
P P
GH ALL ALL R,C EG D
D B
NA Other Other 2
Other B31.1.0 B31.1.0 III-2 B31.1 NA NA I
I N
N Y
N 49 Demineralized Water Makeup System Tanks Pumps Motors Piping and Valves Piping and supports - Diesel Generator E Building 9.2.9 P
P P
P GH CW CW CW ALL EG D
D NA D
D Other Other Other Other Other VIII-1 B31.1.0/Hyd.I NEMA MG1 B31.1.0 B31.1 NA NA NA NA I
N N
N N
N 24 49
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 29 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Buildings Reactor Building Pressure resistant doors Watertight door R.B. Equipment door Primary Containment Access hatches/locks/doors Liner plate Penetration assemblies Vacuum relief valves Downcomers Downcomer Bracing Diesel Generator A-D Building Control structure Radwaste and offgas building Turbine building Administration Building Circulating water pump house ESSW pumphouse Low Level Radwaste Holding Facility Diesel Generator E Building P
P P
P P
P P
P P
P P
P P
P P
P P
P P
GH R
R R
R C
C C
C C
C C
0 0
0 0
EG B
B B
B B
B B
B B
B B
NA NA NA NA NA NA NA NA NA 2
2 2
2 2
2 2
2 2
2 2
2 2
Other Other Other Other 3
Other 2
ACI/AISC ASTM/AWS AISC ASTM/AWS ASTM/AWS ACI/AISC/III III-MC III-MC III-MC III-2 III-2 AISC ACI/AISC ACI/AISC ACI/AISC ACI/AISC ACI/AISC ACI/AISC ACI/AISC ACI/AISC /UBC ACI/AISC I
NA NA NA I
I I
I I
I I
I I
NA NA NA NA I
NA I
Y Y
Y Y
Y Y
Y Y
Y Y
Y Y
Y N
N N
N Y
N Y
27,30 29 44 22 21
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71
- Refer to the general notes at the end of this table.
Page 30 of 47 Principal Components (34*)
FSAR Section Source Of Supply (1)*
Location (2)*
Quality Group Classification (3)*
Safety Class (4)*
Principal Construction Codes and Standards (5)*
Seismic Category (6)*
Quality Assurance Requirement (7)*
Comments Structures Roof Scuppers and Parapet Openings Spray pond & Emergency Spillway Condensate storage tank Spent fuel pool, Rxwell,Dryer-Sep.Pool&Cask Pit Spent fuel pool liner Refueling water storage tank Pipe Whip Restraints Missile Barriers for safety related equipment Biological shielding within Primary containment, Reactor Building and Control Building Safety related masonry walls New Fuel Storage Vault P
P P
P P
P P
P P
P P
R,CS,G O
O R
R O
R,C C,R,CS, SW,G C,R,CS R,G,CS R
NA NA D
NA NA D
NA NA NA NA NA 2
3 Other 2
2 Other 3
Other Other Other 2
ACI/AISC ACI D100 ACI/AISC ACI/AISC D100 AISC ACI/AISC ACI/AISC ACI/UBC ACI/AISC NA I
NA I
I NA I
I I
I I
Y Y
N Y
Y N
Y Y
Y Y
Y 42 Post Accident Monitoring SRV position indication system Noble gas effluent radiological monitor Continuous samples of plant effluents for radioactive iodine
& particulates Containment hi-range radiation monitor Containment pressure monitor Containment Suppression pool water level instr.
Containment H2/O2 monitor system 7.6 P
PL PL P
P P
P R
T T
R R
R R
NA NA NA NA NA NA NA 2
NA NA 2
2 2
2 344 ANSI N13.1 ANSI N13.1 323/344 323/344 323/344 323/344 I
NA NA I
I I
I Y
N N
Y Y
Y 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
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 31 of 47 General Notes and Comments
- 1)
=
=
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
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 32 of 47 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
- 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
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 33 of 47 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.
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",
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
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 34 of 47 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.
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)
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 35 of 47 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
- 6)
I
- The equipment shall be constructed in accordance with the seismic requirements for the Safe Shutdown Earthquake, as described in Section 3.7.
NA - The seismic requirements for the Safe Shutdown Earthquake are not applicable to the equipment or structure.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 36 of 47
- 7)
Y
- Requires compliance with the requirements of 10CFR50, Appendix B in accordance with the quality assurance program described in Chapter 17.
N
- Not within the scope of 10CFR50, Appendix B.
- 8)
This note has been intentionally left blank.
- 9)
The following qualification shall be met with respect to the certification requirements:
- 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".
- 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.
- 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.
- 2.
See Figure 3.2-2 for instrument line classifications.
- 3.
Other instrument lines:
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.
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.
c)
Those connected to Group D systems and not utilized to actuate safety systems will be of Group D classification.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 37 of 47
- 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.
- 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.
- 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.
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).
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.
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:
- 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.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 38 of 47
- 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.
- 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.
- 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.
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.
Group D Classification is generally applicable, supplemented by the QC techniques described above. Thus, the Hydraulic Control Unit shall be classified as "Special Equipment".
- 13)
This Note Has Been Deleted.
- 14)
This Note Has Been Deleted.
- 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).
- 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.
- 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.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 39 of 47
- 18)
This section of steam piping was seismically analyzed to ensure that it will not fail under loadings normally associated with an SSE.
- 19)
All or part of this component is constructed to a more stringent code or standard than indicated.
- 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.
- 21)
The power conversion system structures may be constructed in accordance with applicable codes for steam power plants.
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.
- 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.
- 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.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 40 of 47
- 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.
- 25)
This Note Has Been Deleted.
- 26)
The shell side of the nonregenerative heat exchanger was constructed in accordance with ASME Section VIII, Division I.
The regenerative and nonregenerative heat exchangers were also constructed to TEMA Class R requirements.
- 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.
- 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.
- 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.
- 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.
- 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).
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 41 of 47
- 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.
- 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:
- 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.
- 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.
- 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.
- 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".
A certification has been obtained from the manufacturer of the main steam leads that the quality control so defined has been accomplished.
- 34)
This Note Has Been Deleted.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 42 of 47
- 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.
- 36)
These Notes Have Been Deleted.
- 37)
This Note Has Been Deleted.
- 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:
- a.
All welding shall be qualified in accordance with Section IX, ASME Boiler and Pressure Vessel Code,
- b.
All pressure-containing castings and fabrications shall be hydrotested in 1.5 X design pressure,
- c.
All high-pressure castings shall be radiographed according to:
ASTM E-94 E-142 maximum feasible volume E-71, 186 or 280 Severity level 3
- 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,
- e.
Wheel and shaft forgings shall be ultrasonically tested according to ASTM A-388,
- 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,
- g.
Notification to be made on major repairs, and records maintained thereof, and
- h.
Record system and traceability according to ASME Boiler and Pressure Code Section III, Appendix IX, Paragraph IX 225.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 43 of 47
- 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.
- 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.
- 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.
- 43)
Code Case 1481-1 has been used because the design temperature of the piping involved is greater than 700°F. ASME Sec.
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.
- 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.
- 46)
Portions of embedded fuel pool piping are B31.1.
- 47)
Seismically qualified for operating basis earthquakes.
- 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.
- 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.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 44 of 47
- 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.
- 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 asSection III due to the inability of the shell supplier to re-stamp the entire condenser asSection VIII.
- 52)
The Reactor and Turbine Building Closed Cooling Water System Heat Exchangers are presented separately.
- 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),
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.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 45 of 47
- 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.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 46 of 47
- 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.
SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
SUMMARY
FSAR Rev. 71 Page 47 of 47
- 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.
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 FSAR Rev. 65 Page 1 of 2 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 Vessel Code,Section III, Nuclear Power Plant Components - CLASS 1 ASME Boiler and Pressure Vessel Code,Section III, Nuclear Power Plant Components - CLASS 2 ASME Boiler and Pressure Vessel Code,Section III, Nuclear Power Plant Components - CLASS 3 ASME Boiler and Pressure Vessel Code,Section VIII, Division 1 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 Storage Tanks As above (8)
As above (8)
AP-620 or ASME Boiler and Pressure Vessel Code Section VIII, Division 1 Atmospheric Storage Tanks As above (8)
As above (8)(9)(10)
API-650, AWWA D 100, 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 Technical Position ETSB 11-1, Parts B.IV and B.VI.
(5)(6)(7) 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.
I
SSES-FSAR Table Rev. 52 FSAR Rev. 65 Page 2 of 2 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 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.
A A
e 8*,C C
D SSES-FSAR TABLE 3.2-4 CODE GROUP DESIGNATIONS - INDUSTRY CODES AND STANDARDS FOR MECHANICAL COMPONENTS SUPPLIED BY THE NSSS VENDOR
{SEE NOTE a) 1 2,MC*
3 ASME III, 1 NA & NB Subsections TEHA C ASHE 1H, 8,. C ANSI B3U II NP & VC, TEMA C TANKS ASME VIII, Div. l ANSI B31.7, IlI NP & VC, IIJ TEHA C TANKS ASME VIII, Div. 1 ANSI 831.1.0 TEMA C TANKS (b)
Note (cl ASHE Ill, 1 NA & NB Subsection TEHA C note (d)
ASHE III, 2 & HC*,
NA & NC Subsections NA & NE Subsections TEHA C TANKS NA, NC Note(d)
ASME III, 3 NA & ND Subsections TEMA C TANKS NA, ND Note (d)
ASME VIII, Div. 1 ANSI 831.1.0 TEHA C TANKS (b)
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
SUMMARY
OF SAFETY CLASS DESIGN REQUIREMENTS (MINIMUM) 2:.
3 Other Quality Group Cl ass i fi cat i on< 1 >
A B
C D
Quality Assurance Reoui rement<i!>
B B
B N/A Seismic Categor_v<3>
I I
I N/A (1)
(Z)
(3)
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.
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.
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 FIGURE 3.2-1 CODE CLASSIFICATION OF PIPING AND VALVES SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT
Auto-Cad Figure Fsar 3_2_2.dwg FSAR REV.65 FIGURE 3.2-2, Rev. 48 MINIMUM INSTRUMENT LINE CLASSFICATIONS SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT Process Pipe (Note 1)
Root Valve ASME Section Class 1 Class 2 Class 3 Class Class 2 Class 3 I I I ASME I I I CL. 1,2,3 Other Then Section I I I Process Pipe Classes Containment Penetration--...---...
Excess Flow Check alve(See Note 5)
Class 2 Root Valve Piping Restricted Orifice Adapter or Excess Flow Check Valve (See Note 3)
Class 2 (See Note 4)
Class 3 (See Note 2)
Class 3 (See Note 2)
Class 2 ANSI B31.1 (Except for Note ANSI B31.1 ANSI B31.1 ANSI B31.1 I Instrument Class 2
- 2)
Instrument, Instrument Panel, Instrument Valve INSTRUMENTS REQUIRED TO OPERATE SAFETY SYSTEMS NON-SAFETY INSTRUMENTS REQUIRED TO MAINTAIN A PRESSURE BOUNDARY NON-SAFETY INSTRUMENTS NOT REQUIRED TO MAINTAIN A PRESSURE BOUNDARY INSTRUMENTS WHICH ARE OPEN TO CONTAINMENT AND FORM CONTAINMENT PRESSURE BOUNDARY 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.