ML20059B967

IC HX Equipment Requirements Specification

ML20059B967
Person / Time
Site:	05200004
Issue date:	10/16/1991
From:	Caviglione M GENERAL ELECTRIC CO.
To:
Shared Package
ML20059B690	List: ML20059B687 ML20059B717 ML20059B739 ML20059B788 ML20059B823 ML20059B834 ML20059B946 ML20059B967 ML20059B981 ML20059B993
References
NUDOCS 9310290174
Download: ML20059B967 (69)

Text

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SBWR SBW 5280 TNIX N014 000 !I 2 TABLE OF CONTENTS Sheet Number

1. SCOPE 4- ,

2. APPLICABLE DOCUMENTS, CODES AND STANDARDS 5

3. REFERENCE DOCUMENTS 7

4. EQUIPMENT FUNCTION 8

5. DESIGN REQUIREMENTS 9 5.1. General Design Requirements 9 5.2. Classification of Components 10 5.3. Thermal hydraulic Design Requirements 10 5.4. Draining Requirements 12 5.5. Safety Requirements 12 5.6. Secondary Side Requirements 13 5.7. Primary Side Venting Requirements '13

• 5.8. Lay-out Requirements 13-

6. OPERATING CONDITIONS 15 6.1. Normal Steady State Conditions 15 6.2. Transient Operating Conditions and Test Conditions 15

7. MECHANICAL DESIGN REQUIREMENTS 18 7.1. Code Design Requirements 18 ,

7.2. Thermal Stress and fatigue Analysis 18 7.3. Design Conditions 18 7.4. Support Reactions 18 -

7.5. Fracture Mechanics Analysis 18 7.6. Flow Induced Loads 18 7.7. Nozzle Loads 19 7.8. Dynamic Analysis Criteria 19 ,

7.9. Blowdown Analysis 19 7.10. Loading Conditions 21

8. MAINTENANCE REQUIREMENTS 22 r 23

9. SERVICE REQUIREMENTS Water Chemistry 23 9.1. 23 9.2. Instrumentation S

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SBWR SBW 5280-TNIX N014 000 !Ii 3.

TABLE OF CONTENTS Sheet Number

10. CONTROLS, TESTS INSPECTIONS AND INSERVICE INSPECTION 24 REQUIRENENTS 10.1. General 24 10.2. Procurement Controls 24 10.3. Welds Control 27 10.4. Assembling Controls 27 10.5. Hydrotest 27 10.6. Leak Testing 2B .

10.7. Visual and Dimensional Examination 28 i~-

10.8. Inservice In*pection Requirements 28

11. MATERIAL REQUIREMENTS 29 11.1. Acceptable Materials 29 11.2. Unacceptable Materials 32  ;

11.3. Gaskets 32

12. FABRICATION REQUIREMENTS 33 12.1. General 33 i 12.2. Fabrication 33 TABLES:

TABLE I WATER QUALITY 36 TABLE II LOAD COMBINATION CRITERIA 37 TABLE III IC CLASSIFICATION 38 TABLE IV PRELIMINARY N0ZZLE LOADS FOR IC DESIGN 39 FIGURES:

Fig. 1 CONTAINMENT BUILDING LAYOUT 40 Fig. 2 CONTAINMENT BUILDING LAYOUT 41 Fig. 3 CONTAINMENT BUILDING LAYOUT 42 Fig. 4 SERVICE LEVEL B (UPSET) DYNAMIC LOAD RESPONSE SPECTRA-HORIZONTAL- 43 Fig. S SERVICE LEVEL B (UPSET) DYNAMIC LOAD RESPONSE SPECTRA-VERTICAL- 44 Fig. 6 SERVICE LEVEL D (FAULTED) OYNAMIC LOADING-HORIZONTAL- 45 Fig. 7 SERVICE LEVEL D (FAULTED) DYNAMIC LOADING-VERTICAL- 46 APPENDIX 3 : SBWR MATERIALS REQUIREMENTS FOR ISOLATION CONDENSER 47 APPENDIX 10: PREHEAT AND INTERPASS TEMPERATURE CONTROLS 56 APPENDIX 20: FATIGUE CRACK INITIATION DESIGN RULES FOR CARBON STEEL 59 l

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1. SCOPE This specification defines the general functional, '

engineering and construction requirements for the Isolation Condenser Units.

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2. APPLICABLE DOCUMENTS, CODES AND STANDARDS The design of this equipment shall be in accordance with specific codes and regulations as follows:

a) American Society of Mechanical Enaineers (ASME) Boiler I and Pressure Vessel Code, July 1989

- Section II, Material Specifications a Part A - Ferrous Materials - '

b Part B - Nonferrous Materials c Part C - Welding Rods. Electrodes and Filler Metals ,

- Section III, Division 1 and Division 2 -Subsection .

NCA Nuclear Power Plant Components; General Requirements

- Section III, Division 1 - Subsection NB - Class 1 Components

- Section III, Division 1 - Subsection NC - Class 2 S

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Components i

- Section III, Division 1 - Subsection NF -Component Supports

- Section III, Division 1 - Subsection NG - Core Support Structures

- Section III, Division 1 - AppendicesSection V. Nondestructive Examination

- Section IX, Welding and Brazing Qualifications

- Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components - Division 1 b) TEMA - Mechanical Standards Class "R" Heat Exchangers c) 10CFR50 Appendix A ' General Design Criteria for Nuclear Power Plants' d) ANSI /ASME NQA-1-1983 and its Addenda (NQA-la) Edition.

(Quality Assurance Program Requirements for Nuclear h-Facility) 8 E

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6 1 ~l SBWR SBW 5280 TNIX N014 000 e) ANSI /ASME NQA-2-1983 Edition. (Quality Assurance -h

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Requirements for Nuclear Facility Applications) f) USNRC Standard Review Plan 3.6.2 MEB 3-1 Rev. 2, June--

1987 Regulatory Guide 1.29 - Seismic Design g) USNRC Classification (Rev. 3) - September 1978 ,

h) ANSI Standard B.16.25 " Butt-welding Ends" 1979 i) ANSI Standard N.18.2 " Nuclear Safety Criteria for the- ,gl Design of Stationary Pressurized Water Reactor Plants" .j ,

1973 j) ANSI Standard N.18.2a " Revision and Addendum ' to ANSI

n. 18.2 - 1973" 1975 k) ASTM Standard A 262 " Standard Practices for Detecting Susceptibility to Intergranular Attack in Austenitic <

Stainless Steel" i t

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3. REFERENCE DOCUMENTS a) GEMD-66 "Infomation. Package for Companies Developing 1 an IC Heat Exchanger Design" b) GEAN-103 "HPCI Testing at SIET" c) ANGE-0104 "HPCI Testing at SIET" d) ANGE-0093 "Relazione Tecnica: High Pressure Isolation Condenser Modular Solution Design Report" -l e) ANGE-0129 "HPCI & PCC Basic Design Requirements" f) Isolation Condenser P & ID n' 107E5154 rev. A g) Composite Design Specification A11-5299 n' 23A6723 l rev. A Condenser System Design Specification h) Isolation  ;

B32-4010 25A5013 rev. A i) FEC/9690 PCCS Design Guidelines i

j) Pressure Integrity of Nuclear Components Standard Plant A62-4030 k) GEAN 212 - IC and PCC Arrangement - Nov. 18, 1991 ,

1) Containment Configuration Data Book T10-1030 ',

n. 25A5044 m) BAR49 - March 1992 - Containment Building Layout i

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4. EQUIPMENT FUNCTION The function of the Isolation Condenser System (IC). is to limit reactor pressure to less than the lowest- set point ,

of the SRVs for moderately frequent events resulting . in reactor isolation.

Furthermore, the ICs, together with the water stored in the RPV, shall conserve sufficient reactor water to avoid automatic depressurization from low reactor water level.

The IC system is not an Engineered Safety Feature (ESF),

although it is used to limit the effects of plant transients.

The IC's shall be sized to remove post-reactor isolation decay heat with two out of three IC's operating and to -

reduce reactor pressure and temperature to safe shutdown conditions with occasional venting of radiolitically generated noncondensable gases to the suppression pool.

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5. DESIGN REQUIREMENTS 5.1. General Desian Reouirements 5.1.1. Each Isolation Condenser Unit shall be designed for 30 MWt capacity and is made of two identical modules.

The IC Unit is located in the pool above the containment roof slab.

The main steam supply line is vertical and feeds two-horizontal headers through four 6" pipes.

Steam is condensed inside 2" vertical tubes and is collected in two lower headers.

Two 4" pipes take the condensate to the 6' main - drain line.

5.1.2. The Isolation Condenser shall be designed with the minimum  :

number of system actuations for reliability.

5.1.3. The IC Unit shall be designed to remain in site, inside ,

the IC pool, for 60 years.

However the IC tubes can be plugged off, if leaking, and headers shall be removable during plant shutdown _ for replacement if needed.

5.1.4. The IC pool and venting system shall be designed for IC tube or pipe ruptures, jet reaction and impingement, and steam / condensate flow oscillations.  ;

5.1.5. The IC pool venting and overpressurization protection system shall be sized to prevent pool overpressure.

5.1.6. The IC shall be designed for OBE and SSE conditions. Load combinations for structural design shall consider dead weight, pressure, thennal and mechanical cycling, seismic, dynamic external loads and main made loads. s/e ,,

5.1.7. Construction materials for the IC tubes and components shall be compatible with nonnal operation requirements of the reactor system.

Material to be nuclear grade stainless steel or inconel, or other material which is not susceptible to IGSC (Intergranular Stress Corrosion).

5.2. Classification of Components The classification of the IC component parts with respect to functional requirements and structural integrity is

- given in Table III.

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10 SBWR SBW 5280 TNIX N014 000 f1 l 5.2.1. Safety Classification The l'C is not to be considered' an ESF (Engineered Safety Feature), although it is used to mitigate the effects of the plant transients.

The planned design basis is for to follow the design guidelines of Safety Class 1, parts through the containment boundary and of Safety Class 2, for part outside the containment.

5.2.2. Seismic Category All Isolation Condenser parts are to be considered .of Seismic Category I.

5.2.3. Quality Assurance The Isolation Condenser must be in accordance with ref.

doc. 2.d and 2.e.

Quality Assurance: 'l

- Group A, inside the primary containment up to the steam distributor included.

- Group B, outside the containment, in the IC pool.

5.3. L 1 J -. ' andic nasian Reauirements -f 5.3.1. Performanc Each isolation condenser shall be designed for 30 MWt heat removal capacity.

To minimize the heat transfer surface and potential heat exchanger overcapacity, the tube drainage shall be sufficient to assure condensing heat transfer rates 4 throughout the tube lengths.

5.3.2. Fouling Th ,. design shall accougt for a fouling factor of ma *C/W (0.0006 hr. ft *F/ BTU) on the p@l side and zon:msistance on the primary tgT5F. ,, . 4; . , _

5.3.3. Tube Plugging The calculation of the E4Fireimfer su'rface area 'shall take into account a margin,ftr tube plugging of.5%. !

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SBWR S% 5280. TNIX N014 000 f1 0 '11-8 5.3.4. Primary Side Pressure Losse's The primary side pressure loss of the IC shall be limitedt y to 20.68 kPa (3 psi) from the steam line penetration :to the main' drain line penetration (top of drywell top slab)L at maximum expected steayd state ' IC~ condensing capacity (140% of nominal capacityr.- -

5.3.5. Heat Transfer Condensation Coefficient 1 The heat '. transfer condensat"f on coefficient 19 side 'the tubes has been evaluated with a conservative approch j (Dukler analysis, Colli -  ;

tube' length is 8500 W/mV,er)f. C the average value along 5.3.6. Heat Transfer Surface Area The IC required heat-transfer area has to be evaluated in_

the following conditions:

- primary side: saturated ' steam at 7.240 MPa(g) (1050 psig)'

- secondary side: pool water. temperature at 100*C (212'F)g ,

5.3.7. Themal Insulation - ,

t The acceptable rate of heat loss from an IC heat exchanger l'

and its connected (see paragraph piping),is, 6.1. below during stand-by c6nditions 0.06 Mtf 5.4. Drainino Recuirements The r uired draining time is less than or equal to seconds after the drain valve opening set point is reached. The draining time after complete opening of the valve is required to be Wseconds or less.

5.5. Safety Reauirements 5.5.1. Double isolation capabilities shall be provided for the IC coolant boundary and. containment boundary. i 5.5.2. The IC system shall be isolatable following IC system component failures or impact damage of parts outside the primary containment system. The design shall be compatible with a Leak Detection and Isolation System (LD&IS) that 8

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SBWR ' SBW 5280 TNIX N014 000 l'l  ! 12-must be capable of detecting and . isolating IC leaks- and ruptures.

5.5.3. The isolation condenser system shall include a redundant unit. The units- shall be separated such that impact or other damage to one IC unit will not functionally disable ,

to other units.

5.5.4. The ICS loops and PCCS (Passive Containment Cooling System) loops shall be completely independent systems. The pools for the independent loops shall be interconnected and isolatable.

5.5.5. Failure of pressurized IC components whose rupture can release steam into the safety-related pool .which contains the PCCS heat exchangers shall be limited at a critical flow through an area equivalent to two 3" pipes plus one 4" pipe or by providing guard pipes (or an enclosure around the components), or by observing the special stress and fatigue usage limits of NRC SRP3.6.2 MEB3-1, or by proof testing using experimental stress analysis cyclic test limits' of ASME III, Subarticle 11-1500, using the thermal, pressure, vibration and seismic load cycling defined in the paragraph 6.

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SBWR SBW 5280 TNIX N014 000 11 l 13 5.6. Secondary Side Reouirements

! 5.6.1. IC Tubes Location The location of the IC tubes in the IC pool should be such a as to guarantee the required performance within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (p minimum from the initiating events.

5.6.2. Pool Inventory Loss I

The moisture content of the steam leaving the vent pipe' shall not exceed 2% of mass flow of the steam generated in the IC/PCCS pool.

5.7. Primary Side Ventina Reouirements Free hydrogen and oxygen gas mixture is generated in the reactor by radiolytic decomposition of water. This can become an explosive mixture if the partial pressure of these gases in a steam-gas mixture increases beyond 36% of ,

the total pressure. Approximately 20 lbs. of gas per l million lbs. of steam is generated by the reactor.

Therefore, at locations in the IC system where steam is condensed by heat losses, there is out-gassing of the hydrogen-oxygen mixture. ,

An explosive mixture shall be prevented in the system by l I

either continuously venting off the gases, or ~ by catalytically recombining them (applies for locations with a low condensing rate), or by maintaining the temperature of the stean-gas mixture above the saturation temperature of steam at 4% of the total system pressure (by conduction or vent flow).

5.8. Lav-out Reouirements 5.8.1. General Arrangement The isolation condenser shall be located above the drywell outside the primary containment.

The vertical 12" sain steam supply line feeds two b' Y

horizontal headers through an upper distributor and four 6 l

inches pipes.

Steam is condensed inside 2" vertical tubes and is collected in two lower headers from which two 4" line take the condensate to the 6" main drain line and hence to the RPV.

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SBWR SBW 5280 TNIX N014 000 l1 [ 14 5.8.2. Arrangement Constraints The location of the isolation condenser units with their associated piping in the IC pool shall be compatible with the present Containmert Building lay-out limitations of Figures 1,2 and 3 and structural requirements for the drywell top slab, i.e.:

1. a maximum pool depth of 4.4 meters; \

2. the steam supply, vent and drain pipes connecting to the isolation condenser shall be routed through the containment roof slab.

In particular:

a) in the dedicated pool compartments, the position of ,

the IC center with respect to the reactor center line shall be:

x =

• 9438 m y =

• 9350 m b) geometrical boundaries: /

- pool bottom elevation = 25300 m Q

- bottom elevation of the slab above pool = 31100 m

- compartment rectangular base of 6175 m by 5475 m c) the IC primary containment penetrations:

- 20" main steam line guard pipe

- 12" main drain line guard pipe and

- 10" vent lines guard pipe shall be located as shown in figure 2.

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6. OPERATING CONDITIONS 3

6.1. Nomal Steady State Conditions The normal steady state conditions for the IC is the standby condition, during which:

- the condensate return valves on the main drain line are closed; i a) the IC is filled with condensate reactor water up to the elevation of overflow into the steam line.

Condensate temperature.is about 10 *C (50*F);

b) the steam pipe and the upper distributor above the condensate are filled with main steam at 289'C_(552'F) and 7.240 MPa(g) (1050 psig);

c) the pool water is at the same temperature of the condensate inside the tubes (10*C).

6.2. Transient Operatina Conditions The expected transient conditions during the component life which shall be analyzed for their effect upon the IC, are listed in the following subsections:

6.2.1. Nomal Operating Transients (Plant Condition 1)

The normal transients to take into account are the steam heatup cycles and cool down cycles.

Occurrences a) Heatup 525 Steam heatup cycles starting from cold condition of 10'C, O Pa(g) to 289'C, 7.240 MPa(g) (50*F, 0 psig to 552*F, 1050 psig) at 55.5 *C/hr (100*F/hr.) maximum.

Occurrences b) Cool down 390 Cool down cycles starting from steam l saturation temperature of 289'C, 7.240 MPa(g) to 10*C, O Pa(g) (552 'F, 1050 psig to 50*F, 0 psig) at 55.5'C/hr.

(100*F/hr.) maximum.

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Occurrences .,

135 i a) MSIVC (Main Steam Isolation Valves Closure).

The reference transient to be considered i is derived from M51V transient and the Load Rejection Without By-pass.

Starting from the stand-by conditions, drain valves are opened and 10*C (50*F) condensate is replaced by 302*C (575'F)-

steam: thermal equilibrium is reached with 8.619 MPa(g) (1250 psig),302*C (575'F) steam inside tubes and 10*C (50*F) water rising to 100*C (212*F) outside.

Reactor pressure decreases afterward, but for mechanical design purposes steam pres-sure and temperature are assumed.to remain constant.

For 134 events the operator closes the drain valves after two hours of operation. 1

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For one event, drain valves are supposed to be closed after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of operation.

After closure, temperature decreases to i

10*C (50*F) at 55.5'C/hr (100*F/hr) .

b) OBE (Operating Basic Earthquake) 10 Dynamic analysis including OBE shall be based on the floor response spectra of Figures 4 and 5. ,

Ten response cycles are to be taken into account for each occurency.

6.2.3. Emergency Conditions (Plant Condition 3)

The events to take into account are:

a) SRV unwanted opening.

< 10~2/yr(*)

Starting from the stand-by conditions, one minute rise to 302*C (575'F), 8.619 MPa(g) (1250 psig) with condensate remaining at 10*C (50*F). 3.3 minute depressurization to 1.103 MPa(g) (160 psig), l i

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then exponentially to 0.1 MPa(g) (15 psig).

10 minutes total time.

Oce rrences b) ATWS (Anticipated Transient Without Scram) <10-g/yr(*)

Reactor isolation with delayed scram:

starting from the stand-by conditions, 0.5 minute steatr pressure increase to 10.342 MPa(g) (1500 psig).

Thermal equilibrium is reached at constant pressure with steam at 314.5'C (598'F) and condensate still at 10*C (50*F). Then, temperature decreases to 10*C (50*F) at 55.5'C/hr. (100*F/hr).

6.2.4. Faulted Conditions (Plant Condition 4) a) Large LOCA < 10-4/yr'(*)

Transient enveloped by the SRV unwanted opening.

b) SSE (Sefe Shutdown Earthquake) < 10-4/yr (*)

Dynamic analysis including SSE shall be based on the floor response spectra of Figures 6 and 7.  ;

(*) Assume one occurrence defining maximum loads (not to be -

included for fatigue usage evaluations).

6.2.5. Test Conditions The following test condition transients shall be considered in the stress and fatigue analysis of the IC:

Occurrences a) Primary Side Hydrostatic Test Test pressure = 1.25 design pressure 10 (*)

Test temperature =,,RTNDT+60'F(ASME III App.G) b) Tube Leakage Test (test requirements to be defined) (later) ,

c) Others (later)

(*) Heavy requirement that it is possible to reduce according to ASME XI IWA-5000.

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! 18' SBWR .SBW 5280 TNIX N014 000 {1

7. MECHANICAL DESIGN REQUIREMENTS 7.1. Code desian reauirements

- Parts of the HPIC through the containment boundary:

ASME Section 111 Class 1.

- Component parts beyond the isolation valves:

ASME Section 111 Class 2.

7.2. Themal Stress and Faticue Evaluation A themal stress and fatigue evaluation shall be perfomed in accordance with ASME Code Section 111 rules using the special design stress and fatigue usage limits defined for-the applicable materials (see appendicies 3,10 and 20).

7.3. Desian Conditions Design Pressure 8.619 MPa(g) (1250 psig)

Design temperature 302'C (575'F) 7.4. Suoport Reactions The support foot reactions are 'those forces, at the point of attachment of the external support, that each support foot shall sustain without exceeding the stress intensity limits of ASME !!I, Class II.-

ihe umbrella reactions for each foot shall be evaluated and are to be used in the IC design.  ;

7.5. Fracture Mechanics Analysis A fracture mechanics analysis of the IC component ferritic steel parts (steam pipe, steam distributor) shall be performed in accordance with Appendix G of. ASME Section 111.

7.6. Flow Induced Loads The IC shall be designed to minimize the effect of flow induced loads. The potential for flow induced vibration damage shall be assessed at the exchange tube bundle and at weld attachment locations between tubes and headers.

Potentiality for' vibrations arise from:

- The primary steam and condensate flow inside tubes.

- The secondary flow outside the exchange tubes, due to natural circulation of the IC pool water.

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7.7. Nozzle loads Nozzle loads are those forces, at the point of attachment of piping to the IC headers, resulting from differential thennal growth, seismic and LOCA conditions.

The preliminary nozzle loads at the IC interfaces with the' piping lines inside the primary containment are assumed to be as defined in table IV.

Additionally the thennal' stresses caused by pipe-material differences or size discontinuity shall be included.

7.8. Dynamic Analysis Criteria The Floor Response Spectrum method shall be used. The response spectra shown in Figures 4 and 5 apply for dynamic loads resulting from combination of OBE and DPV/SRV loads (upset conditin).

for The response dynamic spectra shown loads resulting in Figuresof6 SSE, from combination and 7DPV apply /SRV and LOCA loads (faulted condition).

A three directional dynamic excitation shall be considered.

The total three directional response is to be calculated using the square root at the sum of the squares of the modal contributions.

7.9. Blowdown Analysis 7.9.1. Pipe Rupture Criteria The IC and its component . parts shall be designed to withstand the loads induced by a LOCA event.

A hydraulic and structural analysis are to be performed to evaluate the pressure loads, condensation loads and other dynamic loads which may derive from a postulated pipe rupture.

Postulated rupture to take into account are, in accordance with the applicable document (paragraph 2.).

a) Sudden complete circumferential pipe failure with flow from both ends. Pressurized IC components larger than 2 inch diameter, such as pipes, tube sheets, heads and plenums whose rupture can release steam into the IC pool, may be used in the IC pool if:

1. guard pipes are provided around the pressurized IC component (the guard pipes may be vented into the E

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SBWR SBW.5280 TNIX N014 000 1- 20 g IC pool water through quencher-type orifices which j assure steam condensation) '

or:

11. the stresses and fatigue usage of the pressurized l exceed special limits '!

IC component do not established by- the US NRC SRP. 3.6.2.,~ Branch. '

Technical Position MEB 3-1; or:

111. the pressurized IC components has been proof-tested using experimental stress analysis cyclic tests in accordance with ASME Code Section III, I Article 11-1000, Subarticle 11-1600. The number of operational cycles upon which this experimental cyclic testing shall be baseo 's ' defined in the above item.

b) Sudden failure of guard pipe pipes and ' transition )

pieces that extend the containment boundary only if -

guard pipe design does not meet the special limits-established by US NRC SRP 3.6.2., Branch Technical -

Position MEB 3-1. .;

c) The multiple failure of a group of closely spaced heat exchanger tubes - (cascading tube failure). The number of failed tubes and the break flow area is to be determined using the following principles:

i. There is the sudden circumferential failure of one tube. ,

i ii. The tubes surrounding the broken tube can be used to limit consequential damage if the . tubes are j l

held together by tube stays. l iii. The consequential damage caused by the first tube I failure (Item i.) is limited to longitudinal l splitting of surrounding tubes without shear-off l if tube stays are provided (see Item 11.). Also, i the tube materials and welded joints used must be l for the environmental conditions,  !

qualified without IGSC (Intergranular Stress Corrosion), and  !

without high fatigue usage, and must not be i

susceptible to brittle fracture type failure. The resultant consequential break flow area is equivalent to flow from both ends of a split tube multiplied by the number of surrounding tubes that can be impacted by the first broken tube.

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Progetto loontitcativo Rev. :Pegma propect document no rev .[page SBWR SBW 5280 TNIX N014 000 1 l .21 f

7.9.2. Fatigue Analysis Criteria Fatigue evaluation shall take into account:

a) Mechanical and thennal cycling occuring during normal and upset transients.

b) Flow and condensation induced vibration that occurs i during- ,

- two hours of operation with 302*C (575'F) steam inside tubes and 50*F water on the outside during 134 envelope upset transients;

- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of operation at the same conditions for one upset transient; c) 10 response acceleration cycles for. each of the : 10 dynamic load excitation cycles taking into account OBE and DPY/SRV events.

d) All the test condition transients.

7.9.3. IC Compartment Design Compartments that contain the IC units and supply pipe shall be designed to withstand the pressure caused by an assumed pipe rupture within the compartment: the vent area limits the pool pressure to 34.5 KPa(g) (5 psig).

The maximum assumed rupture have an area equivalent to two 4 3" pipes plus one 4" pipe.

7.10. Loadino Conditions The IC and its component parts shall .be designed to with stand the loads resulting from the combinations defined in table II.

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Progetto loontifu:ativo - -

proyect Rev. Pegma Occomem no. e, . . jpop SBWR SBW 5280 TNIX N014 000 l1 l 22- ,

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8. MIKTEMNCE REQUIREMENTS

- The IC heat' exchangers shall be readily inspectable, repairable and replaceable in the IC pool.

- Removal for routine inspection should not be necessary ,

but difficulties of removal shall be however minimized (i.e. cutting / reweld shall be also minimized).

- The water in the IC pool compartment shall be-removable without emptying the entire IC pool.

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I Progetto 'identitcativo Rev- . Pagina N cocument no rev. ' peg, . 6 i

SBWR SBW 5280 TNIX N014 000 l1 23

9. SERVICE REQUIREMENTS 9.1. Water Chemistry The IC shall be designed to operate satisfactorily with the water chemistry indicated in Table I. >

9.2. Instrumentation Process instrumentation and controls shall be provided to monitor the IC during all nonnal and off-nonnal operating conditions.

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, gge SBWR SBW 5280 TNIX N014 000 ]1' [ 24 L 10. CONTROLS, TESTS INSPECTIONS AND INSERVICE INSPECTION REQUIREMENTS 10.1 General Applicable Non Destructive examination methods are:

Ultrasonic (UT), Radiographic (RT), Magnetic Particle.

(MT), Liquid Penetrant (PT), Eddy Current (ET), Visual Examination (VT), Leak Testing.

Before NDE begins, the Supplier shall prepare NDE procedures and drawings or sketches detailing the essential variables of the applicable method. The procedures shall be consistent with applicable Codes and Standard and shall be submitted to the Customer for approval .

In addition for the requirements of ASME Code Section III .

NC, the following requirements apply. l 10.2 Procurement Controls Controls shall be performed consistent with procurement specification requirements. The following specific requirements apply.

/p 10.2.1 Headers and Headers Covers Forgings shall be examined according to ASME Code, Sec. V Art. 23, SA-745 " Standard practice for ultrasonic examination of austenitic steel forgings" with the following additional requirements.

10.2.1.1 Preparation for forgings j The headers hollow forgings shall be UT examined after 4 heat treatment and after' rough-machining to provide , I cylindrical surfaces for radial examination; the ends of i forgings shall be machined perpendicular to the axis of '

the forgings for the axial examination. l The headers covers forgings shall be UT examined after i heat treatment and after rough-machining to provide faces I flat and parallel to one another.

The surface roughness of exterior finish shall not exceed 250 micro in. (6.3 micron). - l l The UT shall be perfonned prior to drilling holes, tapers,  !

grooves or machining sections to contour extruded nozzles.

10.2.1.2 UT Procedure The headers hollow forgings shpil be radially and axially scanned using straight beam techique.

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Mogetto identifcativo Rev , Pegina protect Cocument no ' re, !page SBWR SBW 5280 TNIX N014 000 l1  ! 25' In addition the hollow forgings shall be examined by angle b from the outside diameter in two beam technique perpendicular directions. I The headers covers forgings shall be UT examined using a-  :

straight beam from at least one flat face and radially l from the circumference.

If radial penetration is not possible due to attenuation ,

or to curved shape of the cover, angle beam examination  ;'

directed radially may be subsistuted in place of radial  !

straight beam.

l-10.2.1.3 Quality Level The applicable quality level for straight beam examination shall be SA-745 par. 12.1.1.1 (a) QL-1, for angle beam examination shall be SA-745 Par.12.1.2.1 QA-1.

10.2.1.4 Acceptance Criteria  ;

Acceptance criteria for straight beam examination shall be in accordance with SA-745 Par.12.1.1.1, for angle beam examination shall be in accordance with SA-745 Par.

12,1.2. .

10.2.2 Steam Distributor and Distributor Cover ,.

Forging shall be examined according to ASME Code, Sec. V Art. 23, SA-388 " Recommended Practice for Ultrasonic Testing and Inspection of Heavy Steel- Forgings" with the following additional requirements.

I 10.2.2.1 Preparation of forging The forging for distributor shall be UT examined after heat treatment and after rough-machining to provide ,

cylindrical surfaces for radial examination; the ends of .

the forging shall be machined perpendicular to the axis of .'

the forgings for the axial examination. i The surface roughness of exterior finish shall not exceed  !

250 micro in. (6.3 micron).

• The UT shall be perfonned prior to drilling holes, tapers, '

i grooves and machining the final external contour.

10.2.2.2 UT Procedure The forging for distributor shall be radially and axially scanned usign straight beam technique.  :

In addition the forging shall be examined by angle beam technique two perpendicular directions. l 9

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• SBWR SBW 5280 TNIX N014 000 l1  ! 26 I

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l 10.2.2.3 Reference Standards Reference Standards for Straight Beam examination shall be flat bottom holes with diameter of 0.4 m for each 6 m of section thickness or fraction thereof to a max. of 3 m.

Reference Standards for Angle Beam examination shall be notch 3% of section thickness (or 6 m whichever is larger) in depth, 60 degrees V-shaped and 25 or less long.

The section thickness is the thickness after. final ,

machining.

10.2.2.4 Acceptance Criteria Acceptance criteria shall be in accordance with ASME Code Sec. III, Div. 1 - NB-2542.2 10.2.3 Pipes Pipes for main steam line, feed lines and drain lines  !

shall be Ultrasonic examined after final heat treatment and before bending according to ASME Code Sec. 111, Div. 1 NC-2550 with the following additional requirements. l$

V i

10.2.3.1 The surface roughness of exterior finish shall not exceed l 250 micro in. (6.3 micron).

10.2.3.2 Pipes shall be examined in two circumferential directions, as defined in NC-2552.1, and in two axial directions.

10.2.3.3 The reference specimen shall be in accordance with NC2552.3 (a) and (b) with the following additional requirements.

- The reference specimen shall contain two axial standards defects (notches), on the outside and inside i surfaces, and two circumferential standard defects (notches), on the outside and inside surfaces.

Notches shall be 5% of nominal wall thickness (or 0.10 m whichever is larger) in depth, 60 degrees V-shaped and 25 m or less long.

10.2.3.4 Repair of defects by welding is not pemitted.

10.2.4 Tubes ,

Tubes shall be UT examined before bending according to ASME Code Sect. III Div. 1 NB-2551.

After bending, tubes shall be PT examined according to ASME Code Sect. III Div. 1 NB-2556.

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ANSALDO Progetto 60entificativo Rev. > Pagma .

protect occument no ,rev {page SBWR .SBW 5280 TNIX'N014 000 !1 -l 27 10.3 Welds Control Welds control shall be perfomed in accordance with the prescriptions of ASME Code Sect. III, Div. 1 NB-5000 and consistent with approved procedures.

Additionally:

a) circumferential butt welded joint in piping shall be examined by the . radiographic and the liquid penetrant method; b) tube-to-headers welds shall be surface examined by the liquid penetrant method and volumetric examined. by radiographic method; c) headers to supports full penetration corner welds shall be surface examined by ' the liquid penetrant-method and volumetric examined by ultrasonic method, d) each layer of the buttering of distributor nozzles for field welds to Inconel 600 piping shall be surface p examined by the liquid penetrant method. Volumetric 4 ',

examination by Radiographic method -shall be made at site after piping welding.

10.4 Assemblina Controls Controls shall be performed during the overall assembling in order to verify that:

- tubes are properly positioned in the corresponding J i

header holes;

- dimensions and tolerances are consistent with approved  ;

manufacturing drawings, 1 1

- all parts which will become inaccessible, are properly positionedandfixedand/orweldedandinspected;

- inner surfaces are properly cleaned.

Before packaging, a final cleanliness control shall be perfomed at Customer's Personnel presence.

All control Reports shall be part of the final Manufactu-ring Report.

l 10.5 Hydrotest

• Hydrostatic tests shall be performed on the IC module and subassemblies in accordance with ASME Code Sect. III.

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Pugetto identr'cativo Rev. ;Pagina wo,.ci occum.nino. ,.,  !

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SBWR SBW 5280 THIX N014 000 ,1 28

.6 Final hydrostatic test of ' the overall unit shall be '

perfomed at site.

10.6 Leak Testina Leak test shall be performed on the IC module in accorda-nce with ASME Code Sect. V Art.10 APPENDIX V. " Helium mass spectrometer test - tracer probe and hood techniques".

The ccaponent is acceptable .when no leakage _is detgeted that exceeds the allowable rate of 1 x 10E-04 std cm /sec - '$$ '

(1 x 10E-04 millibar liter /sec).

10.7 Visual and Dimensional Examination The IC and its parts shall be subjected to visual .and dimensional examination to verify confomance with the drawing and all of the requirements of this specification which do not involve tests. 4 10.8 Inservice Insoection Recuirements

- ISI amount shall be minimized during the design phase, by reducing eg. the number of welds. i

- The IC is an extension of the reactor coolant pressure boundary which is not isolated from the pressure boundary.

Therefore, ASME Code Sections III, Class II, and Section XI requirements for design and accessibility '

of welds for in-service inspection apply.

- The IC tubes, the Secders and IC pool shall be arra-nged so IC tubes can be inspected with ultrasonic '

probes (if needed according to above requirements) or plugged off. This requires that the tubes should be ,

accessible from outside the IC pool or a means prov-ided to isolate one IC pool from another.

- Exchange tubes shall be iaspected by the Eddy current method.

I

- Routine ISI of tube header welds is required (ultr-asonicinspection).  ;

- Non-destructive examination for welded part, forged j part, and out surface shall be done according to the applicable laws and codes. t 8 ,

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. Progetto identdcetivo pro,ect Rev. ,pggma occument no re, }pege SBWR SBW 5280 TNIX N014 000 l1 } 29 I

11. MATERIAL REQUIREMENTS  :

Materials listed in Paragraph 11.1 below are acceptables for the application when used in proper relationship with ,

other materials. Chemical analysis of material shall be perfomed according to ASTM E 38. .

11.1 Accentable Materials All materials shall be subjected to the requirements of  ;

ASME Code (ref. 2.a), Appendix 3 of this document, and the following paragraphs.

11.1.1 Ni-base Alloy Ni-base Alloy material shall be subjected to the following -

requirements:

11.1.1.1 Pickling of wetted surfaces is prohibited.

11.1.2 Austenitic Stainless Steel Austenitic stainless steel material shall be subject to

(#b the following requirements:

11.1.2.1 In the final fabrication condition, wrought austenitic' I stainless steel shall be in the solution heat treated I condition. Heat treatment shall be done at 1040/1150 *C metal temperature, followed by an approved cooling process.

Localized heat treatment is not pemitted unless qualified for a specific application.

11.1.2.2 Grain size and unifomity shall be controlled in' the material to provide adequate UT inspectability, where ,

required. , i 11.1.2.3 Material shall be tested to verify freedom from sensiti- ,

zation according to ASME A 262 Practice A. (ref. 2.k). , ,

i 11.1.2.4 Hardness of cold worked raw materials shall not exceed 92 l '

HRB Hardness shall be controlled during fabrication by process control of bending, cold faming, straightening or other similar operations.

11.1.3 Carbon and Low Alloy Steel Materials  !

Carbon and Low Alloy Steel Materials shall be subject to the following requirements:

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s e., o.

SBWR SBW 5280 TNIX N014 000 ;1 30 11.1.3.1 Forgings shall be SA-508 Cl. 3. Sulfur content shall - be limited to 0.015 %.

11.1.4 Pressure boundary materials a) Pipes for steam suppl /y line and guar' pipe -

Pipes material shall be SA-333 Gr. 6 seamless. ,

b) Forging for distributor and distributor cover Forgings material shall be SA-508 C1. 3.

c) Boltings for distributor covers Bolting material shall be SA-540.

d) Pipes for feed lines Pipes material shall be SB-167 Nickel-Chromium-Iron ,

Alloy UNS N06600 (Alloy 600). I e) Forging for headers and headers covers Forging material shall be 58-564 Nickel-Chromium-Iron Alloy UNS N06600 (Alloy 600). fp f) Bolting for headers covers Bolting material shall be SB-637 UNS N07718 (Gr. 718).

g) Tubes Tubing material shall be SB-163 Nickel-Chromium-Iron  ;

Alloy UNS N06600 (Alloy 600).

I h) Pipes for Drain Lines i See previous Par. d).

"T" forging and drain "T" forging cover

1) Drain Forgings material shall be SA-182 F304AL with Carbon content not exceeding 0.020%.

Material shall be melted by vacuum furnace followed by electroslag-consumable remelting and furnished in ,

heat-treated conditions according to SA-182 Par. 5.3.

Heat treatment of forging may be perfomed before machining. Drain "T" forging shall not be machined directly from bar stock.

1) Boltings for 'T" forging covers Boltings for 'T" forging cover shall be SA-193 B8.

m) Pipes for main drain line Pipes material shall be SA-312 TP304L with the Carbon content not exceeding 0.020%.

The tubes shall be seamless, hot finished and in

• solution heat-treated conditions according SA-312.

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propoet occument no rev {page SBWR SBW 5280 TNIX N014 000 4 1 - l 31 -

l n) Pipes for vent line Pipes material snall be SA-312 TP304L. .

o) Vent nozzlea '

Material for ' the vent nozzles welded to the headers i shall be SB-564 Nickel-Chromium-Iron Alloy UNS N06600 (Alloy 600). ,

p) Instrumentation nozzles Material for instrumentation nozzles (2" complete with flange and 1/4" NPT) shall be SA-182 F304L with Carbon ,

content not exceeding 0,020%. ,

11.1.5 Non-Pressure boundary materials l i

The material for non-pressure retaining parts -shall be in accordance with the applicable ASME or ASTM Specifica-'- l tions.

a) Flow distributor device Forging material shall be SA-182 F304. . ,

A' b) Venturi inserts Forging material shall be SB-564 Nickel-Chromium-Iron k Alloy UNS N06600 (Alloy 600). ,

c) Flow distributor plug Material for the flow distributor plug (to be welded i to the drain "T" forging cover) shall be SA-312/240.TP'  ;

304. .j d) Supports Material for supports integral attachments. shall be '

SA-240 TP 304.

Material for support beams and plate shall be SA-36, i ,

coated for corrosion protection.

f) Flange for guard pipe ,

Flange material shall be SA-105 protective coated on >

outside surface.

g) Flanges for drain "T" forgings and vent lines -

Flanges material shall be SA-182/240 TP 304-

)

i 11.1.6 Protective coating The outside surfaces of guard pipe,- flange item f), and all the support beams and plates which will be exposed to

• pool water, shall be protective coated to avoid corrosion.

Coating shall be compatible with 100'C water temperature. .;

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Progetto loontificativo Rev. i Pegina proyect opt no row Jpage SBWR SBW 5280 TNIX N014 000 1 l 32 Inorganic Zinc coating shall be used, such. as CARBOLINE '

Carbo Zinc 11 FD or AMERON Dimetcote 6, or approved equal.

11.2 Unaccentable Materials Contamination of the IC with sulphur, lead, low melting point metals, their alloys, and their compounds shall be prohibited during f abrication, testing, shipping or erection. Where a satisfactory substitute material free of such contaminants cannot be found, the use of such  :

substance for processing and fabricating metals at room temperature is pemissible providing all surfaces, crevices, blind holes, etc., are throughly cleaned to a f

remove the containment prior to any operation involving ~

-elevated temperatures.

The Supplier shall submit to the Customer, for approval, a ,

detailed Cleaning Procedure. This procedure shall contain specific informations to assure reliable cleaning ~ process of the materials and components during all stages of manufacturing.  ;

11.3 Gaskets l For distributor cover the gasket shall be of the spiral  !

wound graphite filled type or approved equal.  ;

For headers covars the gaskets shall be metallic 0-rings of te self-energized type provided with retainer clips. i For the drain "T" forgings covers the gaskets shall be j .

metallic 0-rings. i r

The 0-rings shall be manufactured, worked, tested, 1

inspected and certified according to the production standards of a qualified manufacturer. l Material shall be Alloy 718 or Alloy X-750. '

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SBWR SBW 5280 TNIX N014 000 i1  ; 33

12. FABRICATION REQUIREMENTS 12.1. General Manufacturing technology in process of work of the IC unit shall be high level.

The principal manufacturing documents are listed below.  !

The following list is for guidance purpose and is not necessarily comprehensive.

Planning Engineering schedule  !

- Procurement and Fabrication Drawings  !

- Fabrication plan and description of the activity

- Procurement Specifications

- Control Specifications  !

- Manufacturing procedure Specifications Welding Specifications and Welding Procedure Specification i Welding book i

- Final Manufacturing Report to be submitted to the Customer after completion of the IC and before its i shipping to te plant site. i Technical Manual.  ;

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1 12.2 Fabrication the general l\

j Manufacturing procedures shall meet requirements listed in Table 111 and the prescriptions j detailed hereinafter.

12.2.1 Material Procurement

}

Material procurements shall be carried out to meet the .

prescription of Par.11. and according to the relevant  !

specifications, approved, if required, by the Customer.

12.2.2 Thennal cutting 12.2.2.1 Austenitic Stainless Steel and Nickel-Chromium-Iron Alloy Thennal cutting of pressure retaining materials and weld preparation shall be made by plasma cutting process only.

No other type of thermal cutting is admitted.  ;

After cutting, a minimum of 1.0 m of material shall be removed by machining or griding.

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p.9 SBWR SBW 5280 TNIX N014 000 f ..

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! 34 12.2.2.2 Carbon Steel, Carbon Manganese and Low Alloy Steel Preheat temperature for thennal cutting shall not be lower than the one specified for the welding of the same material and thickness.

After thennal cutting operations, including arc-air and oxygen cutting, on all pressure retaing materials and all weld preparations, a minimum of 1.0 mm of material shall be removed by machining or griding.

12.2.3 Welding Welding procedures and weld procedure / operator qualifications shall be consistent with ASME Code Section IX.

Special precautions shall be taken for Inconel 82 buttering of SA-508 C1. 3 distributor nozzles ends, to avoid adverse effects on material properties: welding procedure shall be submitted to Customer for approval.

12.2.4 Heat Treatment 4 Heat treatment shall be in accordance with Appendix 3.

The values of the main parameters of these treatment shall be reported to the Customer.

12.2.5 Repair Welding a) Reoair to welds - They may proceed without prior Customer approval, provided that the repair procedures are consistent with welding specification requirements and that the repair is properly recordede  ;

Weld repairs shall not be done more than twice. j b) Repair to base material - No repair to base material shall proceed without prior Customer approval.

12.2.6 Surface Protection The Surface Protection Procedure shall contain specific informations to assure reliable surface protection of the l materials and components during all stages of manufactu-ring.

4 The surface protection treatment shall be provided for j manufacturing time, according to the prior program to be established by the Supplier.

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Progetto loontihcativo Rev ;Pegina prosect 00cument no . rev. ?page SBWR 'SBW 5280 TNIX N014 000 f-1  ! 35 Exposure of austenitic stainless steel to substances ,

containing chloride or fluoride ions is to be avoided.

Where manufacturing or inspections processes necessitate exposure to chloride or fluoride ions, all . finished '

surfaces that may have been so exposed shall be thoroughly.

cleaned with approved cleaners or solvent to -ensure freedom from contaminants. _

Surface cleanliness should be tested in accordance with Supplier Surface Protection Procedure.

Grit- blasting shall not be performed 1on surfaces in '

contact with water.

The Supplier Surface Protection Procedure. shall contain detailed infomation on surface protective coating of carbon and low-alloy steel in contact with water according -

to the functional requirements of the' component.

~

t 12.2.7 Cleaning Manufacturing and welding procedures shall include precautions against contamination by such items: mercu ry,  !

lead, zinc, cadmium or other low melting point metals.

All surfaces shall be cleaned prior to heat treatment.

Welding procedures shall prevent the contamination of the deposited weld metal by a temperature sensitive crayon.

No cleaning of not formed austenitic stainless steel >

material by acid pickling shall be performed. ,

Water used for cleaning or testing the component shall be

?

grade B in quality according to the applicable procedure.

Cleaning procedures, solvent specifications and packaging procedures shall be submitted to the Customer for  !

approfval.

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REACTOR WATER OUALITY PARAMETER SYSTEM DESIGN Chloride (ppb 20.0 Sulfate (ppb , 20.0 Conductivity at25'C(pS/cm) 0.25 Silica (ppb as SiO2) 100 pH at 25'C min 7.0 max 8.0 (8.6,)

CORROSION PRODUCT METALS (pob)

Fe Insoluble 20.0 Soluble Cu Total 2.0 All Other Metals 8.0 Sum 30.0

• • Does not include an incremental conductivity value of 0.8 pS/cm at 25'C due to carbon dioxide from air in water stored in tanks open to the atmosphere.

• 0perating values change to these values during plant shuntdown.

Otherwise, operating and shutdown design values are the same.

Note 1: The values given are for reactor water quality during reactor operation and shutdown except as noted by asterisk.

Note 2: IC pool water quality is the same as reactor water quality at shutdown design values.

Note 3: Pool water is demineralized and filtered and will contain no I biological material or biocides.

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SBWR SBW 5280 TNIX N014 000 1  ! 37 TABLE II TABLE COMBINATION CRITERIA )

i PLANT CONDITION LOAD COMBINATION SERVICE LEVEL

- Deadweight, Design Pressure Design Design Temperature, OBE 1 Deadweight, Nomal Condition A (nonnal)

Transients 2 Deadweight, Upset Condition B.(upset)

Transient, OBE 3 Deadweight, Emergency Condition C (emergency)

Transients ,

4 Deadweight, SSE, Faulted Condi- D (faulted) tion (1)

- Test Deadweight, Test Pressure Test Note:(1) The response spectrum used for dynamic analysis takes into account building response to SSE and LOCA loads.

Other pipe rupture loads are to be combined by means of the SRSS method.

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Progetto toontifcat'v0 Rev. Pegra progect Occument no rev , .page SBWR SBW 5280 TNIX N014 000 f1 l M TABLE III IC CLASSIFICATION COMPONENT PARTS ANSI SAFETY ASME CODE Q.A. SEISMIC CLASSIFICAT.' CLASSIFICAT. GROUP CATEGORY Through primary CLASS 1 CLASS 1 A 1 containment Outside primary CLASS 2 CLASS 2 B l' containment E

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pg,= =p p SBWR SBW 5280 TNIX N014 1 l. 39 000 TABLE IV PRELIMINARY N0ZZLE LOADS FOR HPIC DESIGN L

LOAD Plant Condition (note 1) 1 and 2 3 -4 Axial.or Shears 0.050 Ap Syp 0.055 Ap Syp 0.070 Ap Syp Transverse (LBS) 0.25 Zp Syp 0.30 Zp Syp 0.35 Zp Syp Bending)

(IN-LBS Moments Torsional Moment 0.25 Zp Syp 0.30 Zp Syp 0.35 Zp Syp (IN-LBS)

NOTE I: The six component of nozzle loads are assumed to be >

applied simultaneously.

Where:

Ap = Cross sectional area of pipe metal, (ina )

Syp = Tensile yield strength of pipe material at design tempera- 5 ture, (lb/in2). When pipe material is not specified, yield shall be taken as 30,000 psi Section modulus of pipe, (in3 ).

Zp =

b

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SBWR SBW S280 TNIX N014 000 f ,1 ' { 47 APPENDIX 3 SBWR MATERIALS REQUIREMENTS FOR ISOLATION CONDENSER April 4,1991 I

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i Progetto ,loentifiestivo Aes Papna Droyect document no tev Dage SBWR SBW 5280 TNIXN 014 000 g 4g 3.2 r ou rht Austenitic Stainless Steels 3.2.1 Requirements of this section shall apply to all vrought austenitic stainless steel (such as Types 304 and 316) components exposed to water or steam environment at temperatures over 100*C. unless specified otherwise 3.2.2 All materials shall be purchased to specifications prepared for SB7R s e rvic e . If the components cannot be solution heat treated after welding or other heat creating operation, unless qualified, the carbon content of the material shall not exceed 0.0201.

3.2.3 Solution Heat Treatment of Austenitie stainless Steels

a. In the final fabrication condition, wrought austenitic stainless steel parts shall be in the solution heat treated condition. The recommended solution heat treatment is heating to the temperature range of 1040' to ll50'C with a hold time designed to achieve full solutionizing while minimizing grain growth. Heat treatment shall immediately be followed by quenching or cooling below 205'C such that sensitization is avoided. For crevice applications Type 316L is preferred to Type 304L and for parts for service even at or below 100*C, solution heat treatment and water quenen.

ing must be done. Alternate method of quenching such as air quench, are allowed provided the process is qualified and controlled with sensitiza-tion tests required in this specification.

b. Localized heat treatment of austenitic stainless steel is not permitted unless qualified for a specific application.

3.2.4 Sensitization 3.2,4.1 Welding of wrought Type 300 series austenitic stainless steel is considered to cause sensitization. Sensitized wrought austenitic stainless steel shall not be used. Austenitic stainless is considered to be sensitized if it has been heated within the temperature range between 430'c and 980*:

regardless of the subsequent cooling rate. When heated above 430'C, the austenitic stainless steel material shall be solution heat treated in accor-dance with Paragraph 3.2.3. Type 316(NG) or Type 316L and Type 304(NC) or Type 304L material with 0.020 percent maximum carbon is exempt from this requirement during welding provided it is in a solution heat treated condition prior to velding, 3.2.5 Austenitic Stainless Steel Pies or Tubina. Wrought austenitic stainless steel pipe or tubing shall be Type 304(NC), Type 304L, Type 316(NC) and Type 316L to an applicable SBVR materials specification. For parts that cannot be solution heat created af ter welding, only Type 304L or Type 304(NC) for non creviced parts, or Type 316(NC) or Type 316L for creviced parts with 0.020 percent maximum carbon material shall be used. Other stainless steels qualified for S5WR service such as Type 347 Modified are also acceptable.

3.2.5.1 Cold bending or forming shall be controlled such that hardness in the e

final fabricated condition shall not exceed Rockwell B 90 for Type 304(NC) and Type 304L and Rockwell 5 92 for Type 316(NC) and Type 316L. Hardness values

ANSALDO Proget!D toontificativo Rev P 3 gr3 Drotect ;oocument no rev Cap SBWR SBW 5280 TNIXN 014 000 1 aq shall be reported on the Materials Test Report. Brinell hardness equivalent to Rockwell B may be used.

3.2.5.2 Induction Bendine of Fire. Induction bending of pipe shall be quali-fled based on the bend radius and the pipe diameter for components to be bent to band radii of 5D and less. Each heat of material shall be qualified by bending a test piece and subjecting it to high sensitivity U.T. examination and destructive examination for microfissures.

3.2.6 Veldine Materials for Austenitic Stainless Stegl. Filler metals for welding austenitic stainless steels shall be selected to be compatible with the base metal (s) to be welded. Tiller metal shall be procured in accordance with applicable ASME Code Requirements. Acceptable filler metal Types are 308L, 309L, 309 Mot, 316L and 316LC.

3.2.6.1 Ferrite Control 3.2.6.1.1 For all stainless steel welding materials including consumable inserts for components which operate above 100'C the ferrite content shall be not less than 51 (or 5 FN) for each individual reading, and the average shall be not less than 81. Maximum ferrite content shall not exceed 20% Ferrite content shall be determined on undiluted weld deposits. Ferrite measurements shall be made in accordance with the magnetic measurement requirements described in ASME Section III. Paragraph NB2433.

3.2.7 Austenitic Stainless Steel Velds 3.2,7.1 Heat Inout Controls. Velding heat input controls are required for all welds including repair welds, overlay / cladding welds, weld bead straignt ening, and joining carbon or low alloy steel to stainless steel. Austenttic stainless steel components solution heat treated after welding are exempt irem these requirements.

a. For manual CTAW and SMAV, heat input shall be limited by weaving and welding technique controls. Non weaving (stringer bead) welding tech-niques shall be used where possible. Veaving and technique shall be controlled to meet the equivalent of host input limits of paragraph 3.2.7.1.b.

b. For automatic (or machine) welding and manual welding with processes other than GTAV or SMAV, welding heat input shall not exceed 44,000 joules /cm-calculated according to the following formula:

Voltare I) (Volts) x Current I (Amon) x 60 Heat Input - Travel Speed (em per Minute)

NOTES:

(1) This heat input is based on the voltage at the arc. Voltage may. however.

be measured at the welding power supply. If the heat input limit is exceeded when voltage is measured at the welding power supply, the voltage U l 8 i E l

ANSALDO -

Progetto toentificativo Aev P a gir's pro,ect coc., ment no ee. page SBWR SEW 5280 TNIXN 014 000 1 50 may be reduced by an amount equal to the voltage drop between the power supply and the arc. This voltage drop shall be determined by direct measurement for each power supply, welding process, and cable combination (2) For pulsing current applications, the weighted average current, according to the formula below shall be used to calculate the heat input.

(High Pulse Current x High Pulse Time) +

Weighted Average Current - flow Pulse Current x Low Pulse Timei High Pulse Time + Low Pulse Time 3 2 7.2 The maximum interpass temperature shall be 180*C for all stainless steel welds. (See Appendix 10.)

3.2.7.3 Socket welds and seal welds shall use the GTAW process (with filler metal added) for at least the root layer (s). Protective gas back purging is not required.

3.2.8 Intergranular Attack (ICA) shall be controlled per the requirements ci CE specification E50YP11 for all wrought austenitic stainless steel which during operation is wetted with water at temperatures above 100*C. ICA control shall be applied to raw material and subsequently after any heat treatment above 815'C and any pickling operations. Where a minimum depth of 0.8 mm of material will be removed from all wetted surfaces after the final heat treatment, no ICA control is required. Results are to be noted in :ne Katerials Test Report.

3.2.9 All solution heat treated wrought material for service above 100*C shall be tested for sensitization per the requirements of CE specification E50YP20. As a minimum, one specimen representing each heat treat lot shall be tested for sensitization. The material tested shall be heat treated with tne lot it represents. The Materials Test Report for the material shall note the results of these tests.

3.3.6 Reoortine Ferrite in Veldine Materials. The ferrite content and the method used for its determination shall be reported in the Material Test Report for austenitic stainless steel weld metal and castings.

3.4 Crindine Controls 3.4.1 These requirements shall apply to final fabricated surfaces to be exposed to reactor water. Abrasive grinding of stainless steel heat affected zones shall be minimized to the extent possible. Care shall be taken to confine grinding to the weld metal only and limit grinding of the adjacent base metal to that required to meet the fabrication and examination require-ments of the ASME Code, this specification, the equipment requirement specifi-cation, or support drawing. Orinding abrasives and wire brushes for stainless steel and nickel chrome iron alloy shall not have been used previously on materials other than stainless steel or nickel chrome-!ron alloy. For wrought austenitic stainless steel surface to be exposed to reactor water, if any

. grinding is done and not followed with solution heat t r e a tme r.t . the surface shall be polished to remove the grinding marks to obtain a final surface finish of 0.8 mm of finer. ,

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SBWR SBV 5280 TNIXN 014 000 1 51 l

i 3.5 Urourht Ni Cr Fe A11ov 600 and Weld Metal Alloys 82 and 192.

3 5.1 This section describes the design and processing requirements for Ni Cr-Fe alloys. The requirements are applicable to wetted components exposec  !

to temperatures over 100*C.

3.5.1.1 High Stress Corrosion Cracking (SCC) resistance is obtained by using improved nickel base alloys as follows:

a. Base material for welded structure:

Alloy 600 with Niobium modified chemistry (1-41)

b. Veld metal; Alloy 82 or 182 with Niobium as follows:

Alloy 82. 2-31 Nb Alloy 182: 2.5 4.5% Nb 3.5.2 Desirn Limitations for Wrourht Allov 600 3.5.2.1 Design limitations for wrought Alloy 600 for both solution annealed and the improved heat treatment (885'C) are listed below. Requirements for Niobium modified Alloy 600 are also included.

3.5.2.2 Unereviced Case. The Stress Rule Index (SRI) as defined in Paragrapr.

3.2.10 shall not exceed 1.0. Sustained stress is defined in Paragraph 1.6.e.2.

3.5.2.3 Creviced Case

a. The SRI value for unstabilized Alloy 600 shall not exceed 0.80. For Alloys of Nb modified chemistry SRI values of 1.0 is permitted (See Table 3),

b. Crevices in regular Alloy 600 components shall be eliminated by redesis seeling, or repairing using a non flux welding process. If a crevice cannot be avoided, Niobium modified Alloy 600 may be used.

c. There shall be no heat treat oxide film on surfaces which form wetted crevices.

3.5.3 Resirn Limitations for Rerions Containine Vrourht A11ov 600 Heat Affected Zone and Weld Filler Metals Vith and Without Niobium Modificaticn 3.5.3.1 Uncreviced Case

a. Tha SRI value shall not exceed 1.0. For all welded components including weld repairs all accessible surfaces in the final repair condition sha'..

be liquid penetrant examined. Where the back side of the joint cannot ce thus examined, the root and the second layer shall be radiographed. The E

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rev page SBVR SBW 5280 TNIXN 014 000 1 52 f

examination techniques and the acceptance criteria the ASME Code shall apply. The penetraneter thickness shall be based on root weld thickness b.

Velds which by design cannot be inspected to demonstrate acceptance by the

" standards of paragraph 3.5.3.la. shall have an SRI vs.lue not to exceed  !

0.80. '

3.5.3.2 creviced case. For alloys without the addition of Nb, components shall not have veld metal or veld heat affected zones in crevice areas. If a '

crevice cannot be avoided by design, Nb modified Ni-base alloys can be used For Nb modified alloys 600, 82 and 182. SRI values shall not exceed 1.0.

t 3.5.3.3 For use of Kb modified Alloy 600, high K82 and high N182 alloys. the design limitations for the creviced case are the same as for the non-creviced case (See Table 3).

TABLE 3. STRESS RULES FOR ALLOYS 600. 82. AND 182 i

Uncreviced Creviced Not Known --

(Cannot Examir.e

• Alloy Vrought Velded Vrought Walded the Back Side)

Alloy 600 for SRI SRI SRI Not SRI s 0.80 i solution s 1.0 s 1.0 s 0.80 Allowed annealed, or solution i annealed {

plus 850*C l

heat treated i Alloy 600 SRI SRI SRI SRI SRI s 1.0 i Nb Modified s 1.0 s 1.0 s 1.0 s 1.0 '

Regular -

SRI -

Not SRI s 0.80 i Alloy 82 s 1.0 Allowed j 3 i

Kb Modified -

SRI -

SR1 SRI $ 1.0 '  ;

Alloy 82 s 1.0 s 1.0  :

i i

Nb Modified -

SRI -

SRI SRI s 1.0 '

Alloy 182 s 1.0 i i'

3.5.4 The SRI calculation shall be performed for the most highly stressed l

component in an assembly. If acceptable (per Table 3), all other joints in the assembly may also be considered acceptable.  !

3.5.5 For any fired furnace haating of nickel chrome iron at temperatures  !

above 650*C the sulfur content of the fuel and atmosphere shall be known.

Where an oil fired furnace is used, each lot of oil, defined as one shipment from one rource of supply shall be analyzed and shall be limited to 0.5 weight 8 l 8 l i

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i ANSALDO Progetto loentificetwo Rev Pagn oro ct coc.com no e. ce;e SBWR SBW S280 TNIXN 014 000 1 53 percent sulfur maximum. '.'here a gas fired furnace is used, the gas shall be analyzed at least once a month The sulfur content of the gas shall be less than 10 grains per standard cubic meter of fuel gas. For gas furnaces where a full muffle furnace is not used, the burners shall be adjusted to yield an oxidizing flame. *'han furnace is used to carburize or when carbon monoxide (CO) is used as a reducing medium, the furnace shall be completely purged of all CO before heat treating nickel-chrome-iron. The above control on sulfur content need not apply if all surfaces have at least 1.6 mm removed after heat treatment. ,

3.5.6 Allowable velding materials are regular Alloy 82 and Nb modified Alloys ,

82 and 182, per the requirements of applicable ASME Code Section. All welding materials shall be Ni-Cr-Fe alloy per SFA-5.14 ERNi-Cr 3. If submerged arc welding process is used, the as-deposited chemistry shall comply with the.

requirement of SFA 5.14 For welding preheat and interpass temperature controls, see Appendix 10.

3.5.7 Processine Recuirements 3.5.7.1 Heat Treatment Controls -

3.5.7.1.1 Meat Treatment. Nb modified Alloy 600 is an acceptable material.

The regular Alloy 600 is acceptable either as solution anneal (S.A.) or as S.A. plus 850*-885'C modified heat treated. The solution annealing is to be ,

cone at 1075* 2 25'C followed with water quench. the 850 885'C heat-treating may be followed with air cool. ,

t 3.5.7.2 Acid Cleanine Controls. After each pickling operation on Alloys  :

600/82/182, the treatment shall be followed by neutralizing and rinsing. or by  !

removal of 0.75 mm minimum from all pickled surfaces by machining. No i pickling is allowed after final machining. Alloy 600, purchased from the x11' . ;

without special surface treatment requirements, is normally acid pickled, and surface removal is required as described above. Nitric acid cleaning

(* Passivation' for free iron removal) is permitted, but no hydrofluoric acid or other reducing acids may be in the ' passivation' bath.

3.5.7.3 Basic (Caustic) Cleanine Controls. Caustic cleaning may be used fer parts with no crevices.

3.5.7.4 Interaranular Attack (ICA) and Pittina Controls 0

3.5.7.4.1 Parts and raw materials shall be examined for intergranular attack unless a minimum of 0.75 mm of metal is removed from all as-received surfaces during fabrication.

3.5.7.4.2 Material subjected to any heat treatment or pickling operation at any time during fabrication shall be examined for ICA per Paragraph 3.5.7. 3 unless a minimum of 0.75 mm of metal is subsequently removed from all surfaces. See Paragraph 3.5.7.2 for further pickling controls.

. 3.5.7.4.3 Metallographic examination at 200 to 400 X magnification shall be f a

performed on unecched cross sections of specimens to measure the depth of ICA i Prior to mounting the metallographic sample shall be prepared so as to 8

9

ANSALDO Progetto i loemttf>Cativo Rev Pages prDett 00tymeet 60 F9g Qggf SBVR SBW 5280 TNIKN 014 000 j sa preserve the edges of the cross section during metallographic polishing. ICA shall be measured on a cross section perpendicular to and from the surface where ICA occurs.

3 5.7.4.6 The depth of pitting shall be measured inward from the original surface, as described above, for ICA.

3.5.7.4.5 Completed parts or components shall not have ICA or pitting in excess of 0.025 mm deep.

3.6 Plain Carbon Steel Materials 3.6.1 Requirements of this section shall apply to all ASME Code Class I & II piping systems and components as well as to the balance of planc equipment 3.6.2 All materials shall be purchased to ASME Code specifications. The materials shall be high quality, consistent with the design requirements.

3.6.3 All forms of materials (piping, plate, forging, casting, fitting) sha;;

be intrinsically tou6h grades. The material must achieve charpy impact energy absorption tested per ASME Code.Section III and Section II SA specification The Section III impact test requirements are specified in paragraph NB2300/NC2300.

3.6.4 To achieve the required quality, toughness, and other mechanical properties, the material must be manufactured to the quality requirements of the ASME Code specifications. Melting practice, chemistry control, impur!:

limits, and the heat treatment requirements of the applicable specification shall be met. Specific requirements in addition to the above are as follows

a. The stock material shall be produced by a fine grain melting practice. and shall be silicon plus aluminum killed,

b. The ferritic and the austenitic grain size shall be 5 or finer on the average, as measured by the applicable JIS or equivalent,

c. In addition to the chemical composition per the applicable specification.

sulfur and phosphorus shall be controlled not to exceed 0.0301 each.

d. The material shall be heat treated to achieve uniform mechanical proper-ties including charpy impact energy requirements of the ASME Code specifications for high toughness grades. All hot forming shall be followed by re heat treatment, Specimens shall be taken and testing parformed in a manner that demonstrates the actual properties of the material after hot forming and final heat treatment.

3.6.5 Fatigue crack initiation design rules are presented in Appendix 20. to be used as a design guide.

3.6.6 C_arbon Steel Velds 3.6.6.1 For preheat and interpass temperature controls, see Appendix 10.

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l Progette ICentif+cativo Rev A4;ma Drosec' docuNat ne few ca;f SBWR SBW 5280 TNIXN 014 000 1 55 3 6.6.2 Veldine Materials. Velding electrodes and bare rod materials shall I be in compliance with the applicable J15 filler metal specifications. Velding  !

materials for shielded metal are welding of the pressure retaining parts shall be limited to the low hydrogen type.

3.6.7 Boltinz. Bolts shall have a protective coating to prevent atmospheric corrosion in accordance with the approved material and procedure.

3,6.8 Seouence of Examination. (Pressure Retaining Ferritic Steel) Accep--

tance radiographic, magnetic particle, liquid penetrant examination shall be performed following the final heat treatment for properties.

3.6.9 Method of Surface Examination. For completed components. the selection of either magnetic particle testing or liq'uid penetrant examination, or a combination of both, to be used to disclose surface defects in pressure retaining carbon and low alloy steel components, shall be established based on the specific application of the selected technique. ,

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SBWR SBW 5280 TNIX N014 000 [1 l 56 APPENDIX 10 PREHEAT AND INTERPASS TEMPERATURE CONTROLS ,

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APPENDIX 10 10.1 PREMEAT AND INTERPASS TEMPEP.ATt'RE CONTROLS 10.1.1 Preheat and interpass temperature for all welding including temporary attachments and plate ed 5e repairs shall be in accordance with Table 10-1.

Preheating techniques shall ensure that the full thickness (T) of the weld joint preparation and adjacent base material is at the specified temperature for the distance of 'T' or 150 mm whichever is least. 'T' is defined as the material thickness of the thickest material being joined. In no case shall the distance 'T' on the adjacent base material be less than 50 mm.

10.1.2 Maintenance of Preheat 10.1.2.1 Preheat shall be maintained until post weld heat treatment for low alloy steel materials except that preheat may be dropped to room temperature for the following cases:

a. Temocrary Attachments and Plate Edre Reoairs. Preheat shall be carefully controlled to ensure that the required size area has been heated. Preneat temperature shall be mainteAned during welding and for one hour after welding has been completed. If the welding procedure has been qualified for drop of preheat, then preheat may be dropped following the one hour hold.

b. Veld overlav. For stainless steel or Ni-Cr-Fe veld overlay on low alloy  ;

steel head and shell courses made to fine grain practice, preheat may be dropped to room temperature after a post w*1d intermediate heat treat of 230*C to 290*C for cight hours if the overlay weld procedure is qualified for drop of preheat.

c. Arc-air Courinn. Prehest shall be maintained during gouging and for one ,

hour af terwards. Preheat for other thermal cutting processes may be i dropped following cutting.

10.1.2.2 Loss of preheat for any welding shall be reported with corrective '

action taken in each instance.

10.1.3 In case of welding to predeposited stainless or nickel chrome-iron weld overlay (weld buildup or cladding) on carbon or low alloy steels requiring preheat, the following restriction shall apply

. Velds to weld overlay thicknesses 3 mm and over may not require preheat or post veld heat treatment if the specific procedure to be used has been l

qualified to show that the heat affected zone does not reach the base material. In those cases, all of the welding parameters affecting heat input shall be recorded in the procedure and no increase in the amount of

' the heat input above qualification values shall be used for production welds. l i

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• SBWR SBW 5280 TNIXN 014 000 1 58 ,

TABLE 10-1 FREHEAT AND INTERFASS TEMPERATURE REQUIREMENTS FOR WELDING AND' THERMAL CUTTINC (P. NUMBERS AS DEFINED IN THE ASME CODE, SECTION IX).

Thickness Minimum Preheat Temeerature Beat Interrass Temeera ure ,

I. CARBON STEEL MATERIALS VELDS TO P1 MATERIALS TO BE LETT IN THE AS VELDED CONDITION .}

19 m and Less 15' 260*C f over 19 m 100'C 260*C  ;

WELDS TO P1 MATERIAL UHICH ARE 1ATER POST VELD HEAT TREATED f 25 m and Less 15'c 260'C '

Over 25 m 100*C 260*C THERMAL CUTTING OF P1 MATERIAL . -

50 mm and Less 15'C 260*C Over 50 m 65*C 260*C >

I II. STAINLESS STEEL AND NICKEL-CHROME-IRON MATERIALS l t

P8 AND P43 PB, Stainless None 180*C P43, Ni-Cr Fe 205'C f

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SBWR SBW 5280 TNIX N014 000 f 1 =j 59  :

I APPENDIX 20 FATIGUE CRACK IMITATIM DESIGN RULES i FOR CARBON STEEL ,

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. rev Da;e SBWR SBW 5280 TNIXN 014 000 1 60 APPENDIX 20 - FATICUE CRACK INITI ATION CESIGN RULES FCR CARECN STEEL l 20.1 Score Fatigue design rule evaluation shall be conducted on all ASME l I

Code carbon steel pipes and safe ends for which fatigue analysis is performed I

The rules specifically apply to circumferential girth butt welds and to p;;;ng and safe ends exposed to reactor coolant at any purity and oxygen content at temperatures of 245*C or higher.

20,2 Arelicability and Exemrtions. The rules are exempted in certain cases A flow chart shown in Figure 20-1 defines applicability rules. Applicability of these rules and the exemptions to their use are described in the following I

20.2.1 Elbows, tees, and valve bodies designed and analyzed per the stress index method of the ASME Code procedure are exempted from fatigue design rules analysis; these components already have large safety margins.

20.2.2 Transients have total cycle times of ten seconds or less and no tensile hold time are exempted from fatigue design rules analysis provided that the oxygen content of the water does not exceed 0.3 ppm.

20.2.3 All transients where the metal temperature does not exceed 175'C are exempted from fatigue design rules application.

20.2.4 All systems containing only air or gases, with the exception of steam / water mixtures, are exempted from f atigue design rules applications 1 20.2.5 The design rules apply where tensile loading occurs and where conditions are not otherwise exempted by the rules of this paragraph. The stress range shall be defined by the maximum principal stress range for the non-exempted condition.

I 20.2.6 In situations where the calculated primary plus secondary stress intensity limits are exceeded, a plastic analysis may be performed. In sa:n cases, the fatigue design rules are applicable only when the simplified j elastic-plastic analysis per ASME Code is used. l l

20.3 Acolication of Fatirue Desien Rules to Carbon Steel Pirire and Safe Eres l l

20.3.1 The design rules consist of four factors that supplement the present Code fatigue design procedures, and are categorized as follows:

a. A new set or fatigue strength reduction factors for butt welds only (Kf) l

b. A notch factor (K ) based on the Neuber analysis to account for the effectsoflocalhielding.

c. A anan stress correction factor (K,).

d. An environsental correction factor (K ).

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i SBWR SBW 5280 TNIXN 014 000 1 61 FATICUE DESIGN RULE APPLICABILIN FOR CARBON STEEL PIPING AND SAFE ENOS t

ARE FATICUE T water DESIGN RULES r 2 245*C? NO APPLICABLE?

YES Fatigue Design Rule g application is not rauired.

T metal @ vater No surface =

2 180*C?

4 g YES YES Are stresses compressive?

g NO ,

l Stress Duration YES 0 YES i

= 2 i

< 10 seconds and < 0.3 pp,7 no tensile hold time?

NO g NO q Fatigue Design rule aplication is required i

FIGURE 20-1 F14W CHART TO DETERMINE WHERE THE TATICUE DESIGN RULES APPLY E

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SBWR SBW 5280 TNIXN 014 000 1 62 With the inclusion of these four factors for piping fatigue analysis, the peak stress amplitude is given by 5, - 1/2K Kg n m en e n Vhere S - range of alternating primary + secondary stresses calculated using conventional ASME Code.

and K - plastic strain correction factor (based on simplified elastic-plastic' analysis) specified in ASME Code.

20.3.2 The specific form of each of the four new factors follows:

A. Fatirue Strenrth Reduction Factor (K )g

1. Eirine Analysis Fatigue evaluation of piping components is typically performed using the stress index values from the applicable code. However, for the fatigue stress rule evaluation, the stress indices specified in Table 3 shall be used. These values are the same as those specified in the ASME Code except that the K7 stress index for girth butt welds is somewhat higher. In computing the other factors for piping, the K, value shall be used as the fatigue strength reduction factor K f.

2. Notches For notches in carbon steel components, the fatigue strength factor is determined as follows:

For Notches:

K -1+ t '

1 + c' a

where:

K g

- theoretical stress concentration factor of tne notch o' - material constant - 0.48 mm. for carbon steel a - notch root radius (mm)

5. Notch Factor (K )

The notch correction factor K depends on the ratio 5 /35 where 5 is the ASME Code allowable design stEess intensity value for" car @on steel

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ANSALDO Progeno Icontificatovo Rev Pagira prDiect 00Cument no een page SBWR SBW 5280 TNIXN 014 000 1 63 For K m, there are cases to consider, as follows:

5 K

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-1 fros psh m .f (Kg (0.67) - 1) (K f (S.A. ) - 1) 3S S K -1+ for < 1 (g , y) g S

K -K for A>1 n f 35, C. Mean Stress Correction Factor (K,)

The mean stress correction factor K, depends on the type of loading being considered, as follows:

For fully reversed load cycling (tension. compression):

K, - 1 For load-controlled cycling at any R ratio:

~

a (1 R) where:

R -

S,g /S,,, W S - minimum not section stress for the stress cycling g

being analyzed, and S - maximum not section stress for the stress cycle being analyzed For deflection controlled cycling from an initial zero deflection to a maximum deflection and return:

S K, - [i for 0 $ p5 a f f

i e

6 s

E

m  ;

a

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SBWR SBW 5280 TNIXN 014 000 1 -64 S, .)

0.32 (2 3S* ) S J

K,- 1.1 + )

for < <2 f

l 5  :!

K,- 1.1 for p 2 2 {

m D. Environmental Correction Factor (K )

The environmental correction factor, K depends on the ratio S'/35 (1-R) as well as two empirical constanIE H and H', as follows:

t S,

K -1 for 0 s 35

[

m (1-R) < 0.35 S S n n K, - 0.35)

- 1 + H (35m (1 R) 'for 0.35 < 3Sm (1 R) # 1 l

S

' K - H' for m 35, 1-R) 2 The constants H and H' have the following values:

Constant Air Water Environment 0.1 to 0.3 ppa oxygen > 0.3 ppa or Unknown H .1.0 2.0 3.5 r

H' 1.0 2.3 3.3 The environmental correction factor, K is applicable only when the water temperature equals or exceeds 2458, C during the entire fatigue cycle, If a cesperature transient occurs from a T less than 245'C to a T 2 greater than 245'C, then the following applies:y I

4 s

E r ,e- -

e v -

, e a <, - ,, -

! ANSALDO -

Progetto (loentificativo Rev Pages o**ct 1ooe m sco- re, p.g.,

SBWR SBW 5280 TNIXN 014 000 1- 65-2 245'c 245'c 1

For thermal transients where the temperature crosses the transient point as shown in the figure above. the following multiplier shall be used on the K '"

i factor only: ,

M - 1/ Ken for T2 < 245'c ,

245'c - T T - 245 1 2 M- *T 2 -T

'# > 245'C i T T K 2 2 1 en 1 This equation assigns the environmental factor only to that part of the stress range which occurs during the time when T > 245'C.

M.3.3 If the fatigue usage factor requirements for a specific component cas.not be schieved using the Iangg of maximws stresses in the fatigue stress rule c-iterion, then reanalysis of the component using only the maximum-principsi tensile stresses (substituted for the maximum range of stresses) can be conc' tcted.

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