ML23291A405
| ML23291A405 | |
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| Site: | Susquehanna  |
| Issue date: | 10/12/2023 |
| From: | Susquehanna |
| To: | Office of Nuclear Reactor Regulation |
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Text
SSES-FSAR Text Rev. 56
3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS
Certain structures, components, and systems of the nuclear plant are considered important to safety because they perform safety actions required to avoid or mitigate the consequences of abnormal operational transients or accidents. The purpose of this section is to classify structures, components, and systems, according to the importance of the safety function they perform. In addition, design requirements are placed upon such equipment to assure the proper performance of safety actions, when required.
3.2.1 Seismic Classification
General Design Criterion 2 of Appendix A to 10CFR50 and Appendix A to 10CFR100 require that nuclear power plant structures, systems, and components important to safety be designed to withstand the effects of earthquakes without loss of capability to perform their safety function. NRC Regulatory Guide 1.29 (Rev. 2, 2/76) provides additional guidance and defines Seismic Category I structures, components, and systems as those necessary to assure:
(1) The integrity of the reactor coolant pressure boundary
(2) The capability to shut down the reactor and maintain it in a safe condition, or
(3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10CFR 50.67.
Plant structures, systems, and components, including their foundations and supports, designed to remain functional in the event of a Safe Shutdown Earthquake are designated as Seismic Category I, as indicated in Table 3.2-1. Class 1E electric equipment is Seismic Category I equipment.
Seismic classification of systems instrumentation is discussed in Chapter 7.
All Seismic Category I structures, systems, and components are analyzed under the loading conditions of the SSE and OBE. Since the two earthquakes vary in intensity, the design of Seismic Category I structures, components, equipment, and systems to resist each earthquake and other loads will be based on levels of material stress or load factors, whichever is applicable, and will yield margins of safety appropriate for each earthquake. The margin of safety provided for Safety Class structures, components, equipment, and systems for the SSE will be sufficiently large to assure that their design functions are not jeopardized.
Seismic Category I structures are sufficiently isolated or protected from other structures to ensure that their integrity is maintained at all times.
Components (and their supporting structures) which are not Seismic Category I and whose collapse could result in loss of required function through impact with or flooding of Seismic Category I structures, equipment, or systems required after a safe shutdown earthquake, are analytically checked to confirm their integrity against collapse when subjected to seismic loading resulting from the safe shutdown earthquake.
FSAR Rev. 68 3.2-1 SSES-FSAR Text Rev. 56
The Operating Basis Earthquake as defined in 10 CFR 100, Appendix A, is not incorporated as a part of the seismic classification scheme.
The seismic classification indicated in Table 3.2-1 meets the requirements of NRC Regulatory Guide 1.29 except as otherwise noted in the table. Where only portions of systems are identified as Seismic Category I on this table, the boundaries of the Seismic Category I portions of the system are shown on the piping and instrument diagrams in appropriate sections of this report.
3.2.2 System Quality Group Classifications
System quality group classifications as defined in NRC Regulatory Guide 1.26 have been determined for each water, steam or radioactive waste containing component of those applicable fluid systems relied upon to:
(1) prevent or mitigate the consequences of accidents and malfunctions originating within the reactor coolant pressure boundary,
(2) permit shutdown of the reactor and maintain it in the safe shutdown conditions, and
(3) contain radioactive material.
A tabulation of quality group classification for each component so defined is shown in Table 3.2-1 under the heading, "Quality Group Classification." Figure 3.2-1 is a diagram which depicts the relative locations of these components along with their quality group classification. Interfaces between components of different classifications are indicated on the system piping and instrumentation diagrams which are found in the pertinent section of the FSAR.
System Quality Group Classifications and design and fabrication requirements as indicated in Tables 3.2-1, 3.2-2, 3.2-3, and 3.2-4 meet the requirements of Regulatory Guide 1.26 (Rev. 3, 2/76) except as noted.
3.2.2.1 Quality Group D (Augmented)
Certain portions of the radwaste system meet the additional requirements of Quality Group D (Augmented) as defined in the NRC Branch Technical Position ETSB 11-1 (Rev. 1), parts B.IV and B.VI. Portions of the radwaste system meeting the requirements of Quality Group D (Augmented) may be determined from notes on the appropriate figures in Chapter 11.
3.2.3 System Safety Classifications
Structures, systems, and components are classified as Safety Class l, Safety Class 2, Safety Class 3, or Other in accordance with the importance to nuclear safety. Equipment is assigned a specific safety class, recognizing that components within a system may be of differing safety importance. A single system may thus have components in more than one safety class.
FSAR Rev. 68 3.2-2 SSES-FSAR Text Rev. 56
The safety classes are defined in this section and examples of their broad application are given.
Because of specific design considerations, these general definitions are subject to interpretation and exceptions. Table 3.2-1 provides a summary of the safety classes for the principal structures, systems, and components of the plant.
Design requirements for components of safety classes are also delineated in this section. Where possible, reference is made to accepted industry codes and standards which define design requirements commensurate with the safety function(s) to be performed. In cases where industry codes and standards have no specific design requirements, the locations of the appropriate subsections that summarize the requirements to be implemented in the design are indicated.
3.2.3.1 Safety Class 1
3.2.3.1.1 Definition of Safety Class 1
Safety Class 1, SC-1, applies to components of the reactor coolant pressure boundary or core support structure whose failure could cause a loss of reactor coolant at a rate in excess of the normal makeup system.
3.2.3.2 Safety Class 2
3.2.3.2.1 Definition of Safety Class 2
Safety Class 2, SC-2, applies to those structures, systems, and components, other than service water systems, that are not Safety Class 1 but are necessary to accomplish the safety functions of:
(1) inserting negative reactivity to shut down the reactor,
(2) preventing rapid insertion of positive reactivity,
(3) maintaining core geometry appropriate to all plant process conditions,
(4) providing emergency core cooling,
(5) providing and maintaining containment,
(6) removing residual heat from the reactor and reactor core, and
(7) storing spent fuel.
Safety Class 2 includes the following:
(1) Reactor protection system and Alternate Rod Injection system.
(2) Those components of the control rod system which are necessary to render the reactor subcritical.
(3) Systems or components which restrict the rate of insertion of positive reactivity.
FSAR Rev. 68 3.2-3 SSES-FSAR Text Rev. 56
(4) The assembly of components of the reactor core which maintain core geometry including the fuel assemblies, core support structure, and core grid plate, as examples.
(5) Other components within the reactor vessel such as jet pumps, core shroud, and core spray components which are necessary to accomplish the safety function of emergency core cooling.
(6) Emergency core cooling systems.
(7) Primary containment.
(8) Reactor building (secondary containment)
(9) Post-accident containment heat removal systems.
(10) Initiating systems required to accomplish safety functions, including emergency core cooling initiating system and containment isolation initiating system.
(11) At least one of the systems which recirculates reactor coolant to remove decay heat when the reactor is pressurized and the system to remove decay heat when the reactor is not pressurized.
(12) Spent fuel storage racks and spent fuel pool.
(13) Electrical and instrument auxiliaries necessary to operation of the above.
Structures, systems, and components in Safety Class 2 are listed in Table 3.2-1.
3.2.3.3 Safety Class 3
3.2.3.3.1 Definition of Safety Class 3
Safety Class 3, SC-3, applies to those structures, systems, and components that are not Safety Class 1 or Safety Class 2, but
(1) Whose function is to process radioactive wastes and whose failure would result in release to the environment of gas, liquid, or solids resulting in a single-event whole body dose to a person at the site boundary greater than 500 mrem.
(2) Which provide or support any safety system function. Safety Class 3 includes the following:
- a. Service water systems required for the purpose of:
- 1. Removal of decay heat from the reactor
- 2. Emergency core cooling
- 3. Post-accident heat removal from the suppression pool
FSAR Rev. 68 3.2-4 SSES-FSAR Text Rev. 56
- 4. Providing cooling water needed for the functioning of emergency systems.
- b. Fuel supply for the onsite emergency electrical system.
- c. Emergency equipment area cooling.
- d. Compressed gas or hydraulic systems required to support control or operation of safety systems.
- e. Electrical and instrumentation auxiliaries necessary for operation of the above.
3.2.3.4 Other Structures, Systems, and Components
3.2.3.4.1 Definition of Other Structures, Systems, and Components
A boiling water reactor has a number of structures, systems, and components in the power conversion or other portions of the facility which have no direct safety function but which may be connected to or influenced by the equipment within the Safety Classes defined above. Such structures, systems, and components are designated as "other."
3.2.3.4.2 Design Requirements for Other Structures, Systems, and Components
The design requirements for equipment classified as "other" are specified by the designer with appropriate consideration of the intended service of the equipment and expected plant and environmental conditions under which it will operate. Where possible, design requirements are based on applicable industry codes and standards. Where these are not available, the designer utilizes accepted industry or engineering practice.
3.2.4 Quality Assurance
Structures, systems, and components whose safety functions require conformance to the quality assurance requirement of 10CFR50, Appendix B, are summarized in Table 3.2-1 under the heading, "Quality Assurance Requirements." The Operational Quality Assurance Program is described in Chapter 17.
3.2.5 Correlation of Safety Classes with Industry Codes
The design of plant equipment will be commensurate with the safety importance of the equipment.
Hence, the various safety classes have a gradation of design requirements. The correlation of safety classes with other design requirements are summarized in Table 3.2-5.
FSAR Rev. 68 3.2-5
SSES-FSAR TABLE l.2-2
SUMMARY
Of CODES AND STANDARDS FOR COMPONENTS Of WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE (ORDERED PRIOR TO JULY 1, 1971 WITH THE EXCEPTfONS OF THOSE COMPONENTS LOCATED INSIDE THE RCPB, ANO THE REACTOR PRESSURE VESSEL)
CODE ClASSIFICA TIONS
COMPONENT CROUP A CROUP B CROUPC GROUP 0
Pressure Vessels ASME Soifer and Pressure Vessel ASME Boiler and Pressure Ve5sel ASME Boiler and Pressure Vessel ASME Boiler and Pressure Vessel Code, Section 111, Class A.. Code, s<<tion 111, Class C. Code,Section VIII, Division 1 Code,Section VIII, Division 1 or See Footnote (2) See Footnote (2) Equivalent
0-15 Psig - APl-620 with NOT Examination A.Pl-620 with NOT Examination APl-620 or Equivalent Storage Tanks Atmospheric - Applicable Storage Tank Codes Applicable Storage Tank Codes APl-650, AWWA.0100 or ANSI B Storage Tan ks such a, APl-650, A.WWA.D100 or such as APl-650 AWWAD100 or 96.1 or Equivalent ANSI B 96.1 with NOT ANSI B 96.1 with NOT Examination Examination
Piping ANSI B.31.7, Class 1. ANSI 8 31.7, Clins II. ANSI 8 31.7, Class Ill. ANSI 8 31. 1.0 or Equivale-nt See Footnote (3) See Footnote (3) See footnote (3)
Pumps and Draft A.SME Code for Pumps and Ofaft ASME Code for Pumps and Draft ASME Code for Pumps and Valve! - ANSI S 3 t.1.0 or Equivalent Valves Valves Class I. Valves Class II. Valves Class tu. Pump -Draft ASME Code for Pumps See Footnote (1) & (4) See Footnote (1) & (4) See Footnote 14) Valves Class Ill or Equivalent
(1 l All Pf@SSUre-t"etaining cast parts afe radiographed (or ultr.MOnically ~ted to equivalent standards). Where size or configuration does not permit eff PCtive volumetric examination, magnetic particle or liquid penetrant examination may be substituted. Examination procedures and acceptance sl.lndards are al IE'ast equivalent to those specified in the applicabfe class In the code.
(2! 1968 Edition including Addenda through Summer 1970.
(31 1969 Edition and Addenda.
(4! NOYffl1ber 1968 Edition and March 1970 Addenda.
Rev. 46, 06/93 SSES-FSAR Table Rev. 52
TABLE 3.2-3
SUMMARY
OF CODES AND STANDARDS FOR COMPONENTS OF WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE ORDERED AFTER JULY 1, 1971
CODE CLASSIFICATIONS
COMPONENT GROUP A(1) GROUP B(2) GROUP C(3) GROUP D(4)
Pressure Vessels ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure Vessel Code,Section III, Vessel Code,Section III, Vessel Code,Section III, Vessel Code,Section VIII, Nuclear Power Plant Nuclear Power Plant Nuclear Power Plant Division 1 Components - CLASS 1 Components - CLASS 2 Components - CLASS 3
Piping As above(5)(12)(14)(15)(17)(20) As above(6)(11)(14)(18)(20) As above (7)(14)(19)(20) ANSI B31.1 Power Piping(20)
Pipe Supports As above As above(11)(13) As above(11)(13) ANSI B31.1
Pumps As above As above As above Manufacturers Standards
Valves As above As above As above ANSI B31.1
0-15 psig --- As above(8) As above(8) AP-620 or ASME Boiler and Storage Tanks Pressure Vessel Code Section VIII, Division 1
Atmospheric --- As above(8) As above(8)(9)(10) API-650, AWWA D 100, Storage Tanks ANSI B 96.1, or ASME Boiler and Pressure Vessel Code Section VIII, Division 1
(1)(2)(3)Components ordered after July 1, 1971 comply with the Codes and Standards in effect at the date of award of the order, except t hat Group A, B and C components ordered between July 1, 1971 and July 1, 1972 also comply with the following paragraphs of the ASME Boiler and Pressure Vessel Code,Section III, Winter, 1971 Addenda as applicable: (1) NB-2510, NB-2541, NB-2553, NB-2561, (2) NC-2510, NC-2571, (3) ND-2510, ND-2571.
(4) Certain portions of the radwaste systems meet the additional requirements of Quality Group D (Augmented) as defined in NRC Branch Technical Position ETSB 11-1, Parts B.IV and B.VI.
I
(5)(6)(7) For installation of ASME items, ASME Section III, 1971 Edition with Addenda through the Winter of 1972 shall apply. ASME mater ial shall meet the requirements of ASME Section II, 1971 Edition th rough the Winter 1972 Addenda or any later Edition or Addenda. Any additional ASME Section III material require ments of Subsection 2000, 1971 Edition through the Winter 1972 Addenda, shall apply. For postweld heat treatment, Paragraphs NB-4600, NC-4600 and ND-4600 of ASME Section III, 1974 Edition, Summer 1976 Addenda are used.
For the installation of attachments to piping systems after te sting, paragraphs NB-4436, NC-4436, and ND-4436 of ASME Section III, 1974 Edition, Summer 1976 Addenda are used.
For attachments to piping systems, Paragraphs NB-4433, NC-4433 and ND-4433 of ASME Section III, 1977 Edition, Summer 1979 Addenda are used.
For Code Nameplates, Stamping, and Data Reports, paragraphs NCA-8210, NCA-8220, NCA-8230, NCA-8300, NCA-8414, NCA-8415, NCA-8416, NCA-8417, NCA-8418, and NCA-8420 of ASME Section III, 1977 Edition, Winter 1977 Addenda are used.
FSAR Rev. 65 Page 1 of 2 SSES-FSAR Table Rev. 52
TABLE 3.2-3 (Continued)
SUMMARY
OF CODES AND STANDARDS FOR COMPONENTS OF WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE ORDERED AFTER JULY 1, 1971
(8) Orders for Nuclear Storage Tanks were placed after December 31, 1971.
(9) Atmospheric Storage Tanks fabricated to Group C requirements may be used in a Group D or Group D (Augmented) system.
(10) The Diesel E Fuel Oil Storage Tank Complies with ASME B&PV Code Section III, 1971 Edition, Winter 1972 Addenda. The A-D Die sel Generator Fuel Oil Storage Tanks comply with the ASME Boiler and Pressure Vessel Code,Section III, 1974 Edition, Winter 1975 A ddenda as applicable.
(11) Control Rod Drive Hydraulic System (CRD) piping and supports are constructed in accordance with ASME Section III, 1974 Edition with Addenda through Winter 1975 except as permitted by NA-1140(f) of ASME III as follows. Materials conform with ASME Section III, 1974 Edition, with Addenda through Winter 1975, or any later Edition of Addenda. ASME Section III, 1977 Edition, with Addenda through Winter 1977,
Subsection NF, Paragraph NF-2610, shall apply to piping system support.
(12) 1 and smaller Nuclear Class 1 Piping is designed in accordance with the rules for Nuclear Class 2 piping per ASME Section III, 1974 Edition, Summer 1975 Addenda, Paragraph NB3630.
(13) Allowable stresses for pipe supports for Nuclear Class 1, 2 and 3 piping shall be in accordance with ANSI Power Piping Code B3 1.1, 1973.
(14) For the design of ASME flanges, ASME Section III, 1977 Edition with addenda through summer 1979 is used.
(15) For the design of Nuclear Class 1, 1 branch connections, ASME Section III, 1977 Edit ion with Addenda through Summer 1979 is used.
(16) Code case N316, approved for use at Susquehanna SES by the NRC on 2/17/82, is used in the Bechtel design of small pipe and CRD small pipe.
(17) For the evaluation of Nuclear Class 1 piping components for s nubber elimination or other piping modifications, ASME Section II I, 1977 edition with addenda through summer of 1979 may be applied.
(18) For the evaluation of Nuclear Class 2 piping components for s nubber elimination or other piping modifications, ASME Section II I, 1980 edition with addenda through winter of 1981 may be applied.
(19) For the evaluation of Nuclear Class 3 piping components for s nubber elimination or other piping modifications, ASME Section II I, 1983 edition with addenda through summer of 1984 may be applied.
(20) For the evaluation of ASME piping components or ANSI piping components which are analyzed for Seismic Category I requirements, Code Case N-411 may be applied for Snubber Elimination or other piping modifications/evaluations.
FSAR Rev. 65 Page 2 of 2 SSES-FSAR
TABLE 3.2-4 CODE GROUP DESIGNATIONS FOR MECHANICAL COMPONENTS SUPPLIED BY THE NSSS VENDOR -INDUSTRY CODES AND STANDARDS
{SEE NOTE a)
A A 1 ASME III, 1 ASHE Ill, 1 NA & NB Subsections TEHA C NA & NB Subsection TEHA C note (d) e 8*,C 2,MC* ASHE 1H, 8,. C ASHE III, 2 & HC*,
ANSI B3U II NA & NC Subsections NP & VC, NA & NE Subsections TEMA C TANKS TEHA C TANKS NA, NC Note(d)
C 3 ASME VIII, Div. l ASME III, 3 ANSI B31.7, NP & VC, IIJ IlI TEMA C NA & ND Subsections TANKS NA, ND TEHA C TANKS Note (d)
D ASME VIII, Div. 1 ASME VIII, Div. 1 ANSI 831.1.0 ANSI 831.1.0 TEMA C TANKS (b) TEHA C TANKS (b)
Note (cl Hate (c)
- Hetal concrete containment vessels under ASME containment vessel (as applicable) Section and extens1ons III, Divisions 2, at which time the requirements of of containment only. Future addenda will include this division shall also be 111et.
NOTES:
(a) Wtth options and additions as necessary for service conditions and environmental requirements.
(b) Class D tanks shall be designed, constructed, and tested to meet the intent of AP[ Standards 620/650, AWA Standard DlOO, or ANSI 896. 1 Standard for Aluminum Tanks.
(c) For pumps classified Group O and operating above 150 psi or 212"F, ASHE Section VIII, Div. 1 shall be used as a guide in calculating the wall thickness for pressure retaining parts and In siling the cover bolting. For pumps operating below 150 psi and 212°F, manufacturer's standard pump for service Intended may be used.
(d) For pumps classified A, B, or C applicable Subsections NB, NC, or NO respectively In Pressure Vessel Code, Section Ill shall be used as a guide In calculating the thickness of pressure ASHE Boiler and retaining portions of the pump and In sizing cover bolting,
Rev. 48, 12/94 SSES-FSAR
TABLE 3.2-5
SUMMARY
OF SAFETY CLASS DESIGN REQUIREMENTS (MINIMUM)
.. 3 Other 2:.
Quality Group A B C D Cl ass i fi cat i on< 1 >
Quality Assurance B B B N/A Reoui rement<i!>
Seismic Categor_v<3 > I I I N/A
(1) The equipment shall be constructed in accordance with the indicated code group listed in Table 3.2-1 and defined in Tables 3.2-2, 3.2-3, and 3.2-4.
(Z) B - The equipment shall be constructed in accordance with the quality assurance requirements of IOCFR50, Appendix B.
N/A - The equipment shall be constructed in accordance with the quality assurance requirements consistent with accepted practice for steam power plants.
(3) I - The equipment for these safety classes shall be constructed in earthquake as described in Section 3.7. accordance with the seismic requirements for the safe shutdown
N/A - The seismic requirements for the safe shutdown earthquake are not applicable to the equipment of this classification.
Rev. 48, 12/94 Security-Related Information Figure Withheld Under 10 CFR 2.390
SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT
CODE CLASSIFICATION OF PIPING AND VALVES
FIGURE 3.2-1 Restricted Orifice Adapter Process or Excess Flow Pipe Check Valve (Note 1) (See Note 3) Instrument, Instrument
Panel, Instrument Valve Root Valve ASME Section I I I Class 2 Class 1 (See Note 4)
Class 2 Class 3 INSTRUMENTS REQUIRED (See Note 2) TO OPERATE SAFETY SYSTEMS Class 3 Class 3 (See Note 2)
Class Class 2
Class 2 ANSI B31.1 (Except for Note 2)
Class 3 ANSI B31.1 NON-SAFETY INSTRUMENTS REQUIRED TO MAINTAIN A PRESSURE BOUNDARY
ASME I I I CL. 1,2,3 ANSI B31.1 NON-SAFETY
Other Then Section I I I INSTRUMENTS NOT Process Pipe Classes ANSI B31.1 REQUIRED TO MAINTAIN A Excess Flow Check I Instrument PRESSURE BOUNDARY Containment alve(See Note 5) INSTRUMENTS WHICH Penetration--...---... Class 2 Class 2 ARE OPEN TO CONTAINMENT AND FORM Root Valve CONTAINMENT PRESSURE BOUNDARY Piping Instrument or Instrument Panel Notes : 1) Class for instrument lines from pipe to root valve and adaper is same as process pipe class.
- 2) Class 2 shall be required on lines that can contain reactor coolant or are radiation Class V and are outside contaiment.
- 3) A reducing adapter at the root valve serves as a restriction orifice.
- 4) Most GE shutoff instrument valves are B31.1 not Class 2.
- 5) Any automatic valve equivalent to an excess flow check valve may be used as an isolation valve for this type of line.
FSAR REV.65
SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT
MINIMUM INSTRUMENT LINE CLASSFICATIONS
FIGURE 3.2-2, Rev. 48
Auto-Cad Figure Fsar 3_2_2.dwg