ML20035A281
| ML20035A281 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 03/16/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9303250085 | |
| Download: ML20035A281 (28) | |
Text
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r GENuclear Energy r
%ma'i rc Ca pa w
> E r vt:a e Asrwc San et CA M.3 l
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March 16,1993 Docket No. STN 52-001 i
t k
f Chet Posiusny, Senior Project Manager i
Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal j
Office of the Nuclear Reactor Regulation i
Subject:
Submittal Supporting Accelerated ABWR Review Schedule - Open Item i
14,1.3.8-1 1
Dear Chet:
Enclosed are the proposed changes to SSAR Sections 1.8,3.8 and 3.9 which adress Open i-Item 14.1.3.8-1 pertaining to welding. These changes were reviewed with D. Terao during the ITAAC review meeting in San Jose, CA from January 11,1993 through January 20,1993.
Please provide a copy of this transmittal to Dave Terao.
Sincerely, i
J k Fox l
Advanced Reactor Programs i
cc: Norman Fletcher (DOE) j Roy Louison (GE) i f
e 3
1 i
1 JI B 58
-9303250085 930316 PDR ADOCK 05200001 A
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.ABR 2wamac
' Standard Plapt an c TABLE 1.S-21 (Continued)
INDUSTRIAL CODES AND STANDARDS APPLICABLETO ABWR Code or Standard Number Year Title SSPC PA-1 1972 Shop, Field and Maintenance Painting PA-2 1973 Measurements of Paint Film Thickness with Magnetic Gages SP-1 1982 Solvent Cleaning SP-5 1985 White Metal Blast Cleaning SP-6 1986 commercial Blast Cleaning SP-10 1985 Near-White Blast Cleaning OTiiERS TEMA C 1978 Standards of Tubular Exchanger Manufactures Association UL-44 1983 Rubber-Insulated Wires and Cables Crane Manufactures Association c,f America, Specification No. 70 Aluminum Construction Manual by Aluminum Association NCIG-01 Rev.2 Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants i
l W6 Amendment i
ABWR mumn
. Stand'ard Plant urv A SECTION 3.8 CONTENTS (Continued)
Pace Section Title 3.8.1.4.1.1.2 Axisymmetrical Loads 3.8-6 3.8.1.4.1.13 Major Pcnetrations 3.8-7 33.1.4.1.1.4 Variation of Physical Material Properties 3&7 3.8.1.4.1.2 Design Methods 3.8-7 33.1.4.13 Concrete Cracking Considerations 33-7 3.8.1.4.1.4 Corrosion Prevention 3.8-8 3.8.1.4.2 Ultimate Capacity of the Containment 3.8-9 33.1.5 Structural Acceptance Criteria 3&9 3.8.1.6 Material, Quality Control, and Special Construction Techniques 3.8-9 33.1.6.1 Concrete 3.8-9 3.8.1.6.2 Reinforcing Steel 3.8-10 3.8.1.63 Splices of Reinforcing Steel 3&l0 33.1.6.4 Liner Plate and Appurtenances 3&l0 33.1.6.5 Ouality Control 3.8-11 33.1.6.6 Welding Methods and Acceptance Criteria for Containment Vessel Liner and Appurtances 3.8-11 3.8.1.7 Testing and Insenice Inspection Requirements 3 & 11 3.8.1.7.1 StructuralIntegrity Pressure Test 3.8-11 3.8.1.7.2 Preoperational and Insenice Integrated Leak Rate Test 3 & 11 3.8.2 Steel Comtmnents of the Reinforced Concrete Containment 3.8-11 3.8.2.1 Description of the Containment 3.8-11 3.8.2.1.1 Description of Penetrations 3 & 11 3.8-iii r
Amendment
ABWR mems
- Standard Plant nrw a
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SECTION 3.8 CONTENTS (Continued)
Section Title Page 3.8.2.7.1 Welding Methods and Acceptance Criteria 3 S-15 3.83 Concrete and Steel Internal Structures of the Concrete Containment 3&l6 3.83.1 Description of the Internal Structures 3&l6 3.83.1.1 Diaphragm Floor 3S-16 3.83.1.2 Reactor Pedestal 3 3-16 3S3.13 Reactor Shield Wall 3.8-17 3.83.1.4 Drywell Equipment and Pipe Support Structurc 3.8-17 3.83.1.5 Other Internal Structures 33-17 3.83.1.5.1 Miscellaneous Platforms 3&l7 3.83.1.5.2 Lower Drywell Equipment Tunnel 3.8-17 3.83.1.53 lower Drywell Personnel Tunnel 3.8-17 3.83.2 Applicab!c Codes, Standards, and SpecEications 3.8-17 3.833 Loads and Load Combinations 3&l8 I
3.8-v i
I Ameridment
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ABWR mome
' Standard Plant nix A SECTION 3.8 CONTENTS (Continued)
Section Titic E;!gg 3.833.1 Load Definitions 3.8-18 3.833.2 Load Combinations 3.8-18 3.83.4 Design and Analysis Procedures 3.8-18 3.83.4.1 Diaphragm Floor 3.8-18 3.83.4.2 Reactor Pedestal 3.8-18 3.83.43 Reactor Shield Wall 3&l9 3.83.4.4 Drywell Equipment and Pipe Support Structure 3&l9 3.83.43 Other Internal Structures 3.8-19 3.83.5 Structural Acceptance Criteria 3&l9 3.83.5.1 Diaphragm Floor 3.8-19 3.83.5.2 Reactor Pedestal 3.8-19 3.83.53 Other Internal Structures 3.8-19 3.83.6 Materials, Quality Control, and Special Construction Techniques 3.8-19 i
3.83.6.1 Diaphragm Floor 3&l9 j
3.83.6.2 Reactor Pedestal 3.8-19 3.83.63 Reactor Shield Wall 3&l9 3.83.6.4 Drywc!! Equipment and Pipe Support Structure 3.8-19 i
3.83.6.5 Other Internal Structures 3.8-20 3.83.7 Testing and laservice Inspection Requirements 3 & 20 3.83.8 Welding Methods and Acceptance Criteria for f
Structural and Building Steel 3 & 20 3.8.4 Other Seismic Cateeory I Structures 3.8 20 j
l 3.8-vi I
Amcndment i
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A l
ABWR meiooxe Standard Plant nim A SECTION 3.8 CONTENTS (Continued)
Section Title Page 3.8.4.1 Description of the Structures 3.8-20.1 3.8.4.1.1 Reactor Building Structure 3.8-20.1 3.8.4.1.2 Control Building 3 & 21 3.8.4.1.4 Seismic Category I Cable Tray and Conduit Supports 3 & 21 3.8.4.2 Applicable Codes, Standards, and Specifications 3 & 21 3.8.4.2.1 Reactor Building 3.8-21 3.8.4.2.2 Control Building 3 & 22 3.8.4.23 Seismic Category I Cable Tray and Conduit Supports 3.8-23 3.8.4.2.4 Welding Methods and Acceptance Criteria 3&23 3.8.4.2.5 Welding Methods and Acceptance Criteria 3.8-23 3.8.4.2.5.1 Welding of Electrical Cable Tray and Conduit Supports 3 & 23 3.8.4.2.5.2 Welding of Heating Ventilation and Air Conditioning Supports 3.8 23 3.8.4.2.53 Welding of Refuel Cavity and Spent Fuel Pool Liner 3.8-23 3.S.43 leads and Load Combinations 3.8-23 3.8.43.1 Reactor Building 3 & 23 3.8.43.1.1 Loads and Notations 3.8-23 1
3.8.43.1.2 Load Combinations for Concrete Members 3 & 24 3.8.43.13 lead Combinations for Steel Members 3.8-25 3.8.43.2 Control Building 3.8-25 3.8.43.4 Seismic Category I Cable Tray and Conduit Supports 3 & 26 3.8.4.4 Reactor Building Design and Analysis Procedures 3.8-26 3.8.4.4.1 Reactor Building 3 & 26 3.8-vii Amendment
ABWR mame
' Standard Plant RI V A SECTION 3.8 TABLES Table Title Page 3.8 1 Load Combinations, Load Factors, and Acceptance Criteria for the Reinforced Concrete Containment 3.8-29 3.8-2 Major Allowable Stresses in Concrete and Reinforcing Stcel 3.8-30 3.8-3 Stress Intensity Limits 3.8-31 3.8-4 Codes, Standards, Specifi ations, and Regulations Used in the Design and Construction of Seismic Category I Internal Structures of the Containment 3.8-32 3.8-5 Load Combinations, Load Factors, and Acceptance Criteria for the Reinforced Concrete Structures Inside the Containment 3.8-34 3.8-6 load Combinations, Load Factors, and Acceptance Criteria for Steel Structures Inside the Containment 3 & 35 3.8-7 1.oad Combinations for Foundation Design 3.8-36 i
3.8-8 Welding Activities and Weld Examination Requirements for Containment Vessel 3.8-36.1 ILLUSTRATIONS Figure Title Page 3.8 1 RB - Moor Plan El. (-) 13200 3 & 37 3.8-2 RB - Floor Plan El. (-) 6700 3.8-38 3.8-3 RB - Floor Plan El. (-) 0200 3.8-39
' S-4 RB - Ground Floor Plan El. 7300 3.8-40 3.8-5 RB - Floor Plan El.13100 3.8-41 3.8-6 RB - Floor Plan El.18500 3.8-42 3.8-7 RB - Floor Plan El. 26700 3.8-43 3.8-8 RB - Roof Plan El. 33200 3.8-44 3.8-ix Amendment
O ABWR mm Standard Plant nry n 3.8.1.6.5 Quality Control Subsubarticle CC-6230 of the ASME Code,Section III, Division 2. See Subsection 3.8.6.3 for COL Ouality control procedures are established in license information.
the Construction Specification and implemented during construction and inspection. The 33.1.7.2 Preoperational and Insersice Const ruction Specification covers t he Integrat'ed trak Rate Test fabrication, furnishing, and installation of each structural item and specifies the inspection and Preoperational and inservice integrated leak documentation requirements to ensure that the rate testing is discussed in Subsection 6.2.1.
requirements of the ASME Code, Section Ill, Dhision 2, and the applicable Regulatory Guides 3.8.2 STEEL COMPONENTS OFTHE REINFORCED CONCRETE are met.
CONTAINMENT 3.8.1.6.6 Welding Methods and Acceptance Criteria for Containment Vessel Liner and 3.8.2.I Description of the Containment Appurtances The ABWR has a reinforced concrete Welding methods and acceptance criteria for containment vessel (RCCV) as described in the containment vessel liner and appurtance are Subsection 3.8.1. This section will describe the same as those for the steel components of the the following steel components of the concrete concrete containment vessel (i.e., personnel air containment vessel:
locks, equipment hatches, penetrations, and drywell head) gisen in Subsection 3.8.2.7.1.
(1) Personnel Air locks 3.8.1.7 Testing and Inservice Inspection (2) Equipment Hatches, Requirements (3) Penetrations 33.1.7.1 Structural Integrity Pressure Test (4) DrywcIl Head A st ructural integrity test of the containment structure will be performed by the 3.8.2.1.1. Description of Penetrations i
f COL applicant in accordance with Article CC.6000 of the ASME Code, Section 111, Division 2 and The penetrations through the RCCV include the
[
Regulatory Guide 1.136, after completion of the following.
containment construction. The test is conducted at 115% of the design pressure condition of 45 3.8.2.1.1.1 Personnel Airlacks psig in both the drywell and suppression chamber, simultaneously. A pressure test for the design Two personnel air locks with an inside differential pressure condition of 25 psig diameter sufficient to provide 6 ft., 8 in.,
j between the drywell and the suppression chamber high by 3 ft., 6 in., wide minimum clearance is also performed where the drywell pressure is above the floor at the door way are provided.
greater than the suppression chamber pressure.
One of these air locks provides access to the I
upper dry well and the other provides access to During these tests the suppression chamber and the lower drywell via the access tunnel.
spent fuel pool are filled with water to the normal operational water level. Deflection and Lock and swing of the doors is by manual and concrete crack measurements are made to determine automatic means. The locks extend radically that the actual structural response is within the outward from the RCCV into the reactor building limits predicted by the design analysis.
and are supported by the RCCV only. The minimum clear horiiontal distance not impaired by the In addition to the deflection and crack door swing is 6 ft.
measurements, the first prototype containment structure is instrumented for the measurement of Each personnel air lock has two pressure-l strains in accordance with the provisions of 6eated doors interlocked to prevent simultaneous i
3&1l Amendment
ABWR ms3 Standard Plant nrv n T
opening of both doors and to ensure that one door is completely closed before the opposite door can be opened. The design is such that the interlocking is not defeated by postulated malfunctiont of the electrical systern. Signals and controls that indicate the operational status of the doors are provided. Provision is I
1 1
Amendment 3.8-11.1
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ABM 23463oasu Standard Plant atx n (7) bar and machine steel (A576, carbon content not less than 0.3%); and (S) clad (SA-240 type 304L).
The structural steel materials located beyond -
the containment vessel boundaries are as follows:
(1) carbon steel (A36 or SA-36) and (2) stainless steel extruded shapes (SA-479).
The materials meet requirements as specified in Subarticle NE-2000 of ASME Code Section 111.
D The lowest service metal temperature is 30 F.
3.8.2.7 Testing and insenice Inspection Requirements Leakage of the containment vessel, including the steel components is described in Subsection 3.8.1.7.
3.8.2.7.1 Welding Methods and Acceptance Criteria Welding activities shall be performed in accordance with requirements of Section ill of the ASME Code. The required nondestructive examination and acceptance criteria are provided in Table 3.8-8.
3.8.2.7.2 Shop Testing Requirements The shop tests of the personnel air locks in-clude operational testing and an overpressure t e st. After completion of the personnel air locks tests (including all latching mechanisms and interlocks) each lock is given an operational test consisting of repeated operating of each door and mechanism to determine whether all parts are operating smoothly without binding or other defects. All defects encountered are corrected and retested.
The process of testing, correcting defects, and i
retesting are continued until no defects are detectable.
3&l5 Amendment i
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.ABM 234simie Standard Plant arv.n liigh strength structural ASTM A572 or A441 3.83.8 Welding Methods and Acceptance Criteria steel plates for Structural and Building Steel Bolts, studs, and nuts ASTM A325 cr A490 Welding activities shall be accomplished in (dia. >f. 3/4 ")
accordance with written procedures and shall meet the requirements of the American Institute Bolts, studs, and nuts ASTM A307 of Steel Construction (AISC) Manual of Steel i
(dia. 5 3/4 *)
Construction. The visual acceptance criteria shall be as defined in American Welding Society 3.83.6.5 Other Internal Structures (AWS) Structural Welding Code DI.1 and Nuclear Construction Issue Group (NCIG) Standard, The m,terials conform to all ayplicable Visual Weld Acceptance Criteria for Structural l requirements of ANSI /AISC N690 and comply with Welding at Nuclear Plants, NClG-01.
the following:
3.8.4 OTHER SEISMIC CATEGORY I Item Snecification STRUCTURES Miscellaneous platforms Samc as Section Other Seismic Category I structures which 3.83.6.4 constitute the.ABWR Standard Plant are the reactor building, control building and radwaste Lower drywell equipment ASTM A516 Grade 70 building substructure. Figure 1.2-1 shows the tunnel SA-240 Type 304 L spatial relationship of these buildings. The only other structure in close proximity to these Lower drywell personnel ASTM A516 Grade 70 structures is the turbine building. They are tunnel SA-240 Type 3Gt L structurally separated from the other ABWR Standard Plant buildings.
i Reactor shield wall stabilizer The Seismic Category I structure within the
--tube sections ASTM A501 ABWR Standard Plant, other than the containment structures, that contains high-energy pipes is
--plates ASTM AV3 the reactor building. The steam tunnel walls protect the reactor building from potential Lower drywell floor fill A material other impact by rupture of the high-energy pipes.
material than limestone This building is designed to accommodate the concrete guard pipe support forces.
3.83.7 Testing and Inservice Inspection The reactor building, stcam tunnel, residual Requirrments heat removal (R11R) system, reactor water cleanup (RWCU) system, and reactor core isolation cool-A formal program of testing and inservice in-ing (RCIC) system rooms are designed to handle spection is not planned for the internal struc-the consequences of high energy pipe breaks.
tures except the diaphragm floor, reactor pedes-The RiiR, RCIC, and RWCU rooms are designed for tal, and lower drywell access tunnels. The other differential compartment pressures, with the internal structures are not directly related to associated temperature rise and jet force.
the functioning of the containment system; Steam generated in the RIIR compartment from the therefore, no testing or inspection is performed.
postulated pipe break exits to the steam tunnel through blowout panels. The steam tunnel is Testing and inservice inspection of the dia-vented to the turbine building through the phragm floor, reactor pedestal and lower drywell seismic interface restraint structure (SIRS).
access tunnels are discussed in Subsection The steam tunnel, which contains several pipe-3.8.1.7.
lines (e.g., main steam, feedwater, RiiR), is al-so designed for a compartment differential pres-sure with the associated temperature changes and jet force.
Amendment 3&20
.ABWR 234cioaan Standard Plant nrv n Scismic Category I masonry walls are not used in the design. The ABWR Standard Plant does not contain seismic Category I pipelines buried in soil.
3.8.4.1 Description of the Structures 3.8.4.1.1 Reactor Bullding Structure The reactor building (RB) is constructed of reinforced concrete with a steel frame roof. The RB has four stories above the ground level and three stories below. Its shape is a rectangle of 59 meters in the E W direction,56 meters in the N.S direction, and a height of about 57.9 meters from the top of the basemat.
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Amendment 3 & 20.1 j
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.ABM nasicain Standard Plant RFV n 314.23 Radwaste Building Substructure penetrant and vacuum box examined after fabrication to ensure that the liner does not The radwaste building substructure shall be leak. The acceptance criteria for these designed using the same codes and standards as examinations shall meet the acceptance criteria the reactor building. Refer to Subsection stated in, subsection NE-5200 of Section 111 of i
3.8.4.2.1 for a complete list.
the ASME Code.
In addition, the non-Scismic Category I 3143 Loads and Load Combinations reinforced concrete portion of the superstructure is designed according to the 3143.1 Reactor Building seismic provisions of Section 2314 of the uniform building code.
The temperature and pressure loads caused by a LOCA do not occur on the reactor building.
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314.2.4 Seismic Category 1 Cable Tray and The reactor building ventilation system is Conduit Supports designed to keep the building within operating design conditions.
(1) All codes, standards, and specifications applicable to Ihe building structures shall 3143.1.1 Imads and Notations also apply to cable tray and conduit supports.
Loads and notations are as follows-(2) AISI SG-673, Specification for the Design of D=
dead load of structure plus Cold. formed Steel Structural Members.
any other permanent load (3) NEMA, Fittings and Supports for Conduit and L = conventional floor or roof live Cable Assemblies.
loads, movable equipment loads, and other variable loads such as 314.2.5 Welding and Weld Acceptance Criteria eonstruetion Ioads. The following live loads are used:
314.2.5.1 Welding of Electrical Cable Tray and Condait Suppods Concrete floors and slabs (including roofs) - 200 psf.
Welding activities shall be accomplished in Stairs, stair platforms, grating accordance with the AWS Structural Welding Code, floors, and platforms - 100 D1.1. The weld visual acceptance criteria shall psf. Concrete roofs, live or be as dcfined in AWS Structural Welding Code D1.1 snow load (not concurrent) - 50 and NClG-01.
psf. Construction live load on floor framing in addition to 314.5.2 Welding of lleating Ventilation and Air dead weight of floor - 50 Conditioning Supports psf *.
Welding activities shall be accomplished in R,
= pipe reactions during normal accordance with the AWS Structural Welding Code, operating or shutdown conditions D1.1. The weld visual acceptance criteria shall based on the most critical be as defined in AWS Structural Welding Code D1.1 transien1 or steady-st atc and NCIG-01, condition.
314.53 Welding of Refuel Cavhy and Spent R
= pipe reactions under Ihermal Fuel Pool Liners conditions generated by the postulated break and including Welding activities shall be accomplished in R
accordance with the AWS Structural Welding Code, D1.1. The welded seams of the liner plates shall Y
= equivalent static load on a be spot radiographed where accessible, liquid structure generated by the Amendment 3 &23
ABWR mmme Standard Plant an n reaction on the broken high-energy pipe during the postulated break and including a calculated dynamic factor to account fro the dynamic nature of the load.
Y.
= jet impingement equivalent I
static load on a structure generated by the postulated break and including a calculated dynamic factor to account for the dynamic nature of the load.
Y
= missile impact equivalent static load on a structure generated by or during the i
postulated break, like pipe whipping, and including a
calculated dynamic factor to account for the dynamic nature of the load.
W
= wind force (Subsection 33.1)
If the actual construction live load is greater than this value a design check of the stmctures willbe made.
r 3 & 23.1 Amendment 1
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'ABWR mems
. Standard Plant REV.C
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q Table 3.8-8 i
WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR
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CONTAINMENT VESSEL (1)(2)(3)
I i
Component Weld Type NDE' Requirements I
Containment Category A, butt welds (long'l)
RT-j Containment Category B, butt welds (Circ.)
RT l
't Containmerit Category C, butt welds RT i
Containmem Category C, nonbutt welds UT or MT or PT Containment Category D, butt welds RT
~:
f Containment Category D,nonbutt welds UT or MT or Fr Containment Structural attachment welds a) Butt welds RT b) Nonbutt welds UT or MT or Ff SpecialWelds Weld metalcladding PT
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NOTES:
(1). The required confirmation that facility welding activities are in compliance with the requirements will include the following third-party verifications:
i (a) Facility welding specifications and procedures meet the applicable AShE Code requirements:-
-l (b) Facility welding activities are performed in accordance with the applicable AShE Code requirements; -
(c) Welding activities related records are prepared, evaluated and maintained in accordance with the ASME
' i Code requirements; (d) Welding processes used to weld dissimilar base metal and welding filler metal combinations are l
compatible for the intended applications;
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(e) The facility has established procedures for qualifications of welders and welding operators in accordance with the applicable ASME Code requirements; (f) Approved procedures are available and used for preheating and post heating of welds, and those procedures ~
l meet the applicable requirements of the AShE Code;
^
~(g) Completed welds are examined in accordance with the applicable examination method required by the -
ASME Code.
i i
-l 3.5-36.1 l l
Amendment 1
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ABWR utaiome Standard Plant REV.C j
Table 3.8 8 WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR j
CONTAINMENT VESSEL (I)(2)(3) (Continued) i (2) Radiographic film will be reviewed and accepted by the licensee's nordestnetive examination (NDE),12 vel Ill i
examiner pnor to final acceptance.
(3) The NDE requirements for containment vessels will be as stated in subarticle NE-5300 of Section III of the
}
ASME Code.
LEGEND.-
i RT-Radiographic Eumination MT - Magnetic Particle Examination Irr-Liquid Penetrant Examination l
LEGEND (Continued):
i C
N 9
A i
w A
P y
f
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O s' 3 g"
6 A
D Categories A, B, C, and D Welded joint Typical Locations
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Amendmerg 36-362 I
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ABWR n46mit Standard Plant nrv n SECTION 3.9 CONTENTS (Continued)
Section Title Pace 3.9.1.4.9 ASME Class 2 and 3 Vessels 3.9-3 3 S.1.4.10 ASME Class 2 and 3 Pumps 3S-3 3 9.1.4.11 ASME Class 2 $nd 3 Vahes 3.9-3 3 S.1.4.12 ASME Class 1,2 and 3 Piping 3.9-3 39.1.5 Inclastic Analysis Mcthods 3.9-3 3.9.1.6 Welding Methods and Acceptance Criteria for ASME Code Welding and Welding of non-ASME Pressure Boundary Retaining Piping 3.9-3.1 3.9.1.6.1 ASME Code Welding 3S-3.1 3.9.1.6.2 Welding of non-ASME Pressure Retaining Piping 3S-3.1 3.9.2 DvnamicTestine and Analvsis 3.9-3.1 3S.2.1 Piping Vibration, Thermal Expansion, and Dpamic Effects 3.9-3.1 3.9.2.1.1 Piping Vibration Thermal Expansion 3.9-4 and Dynamic Effects 3.9.2.1.1.1 Measurement Techniques 3.9-4 3.9.2.1.1.2 Monitoring Requirement 3.9-4 39.2.1.13 Test Evaluation and Acceptance 3.9-5 Criteria for Main Steam Piping 33.2.1.1.4 Reconciliation and Corrective Actions 3.9-5 3.9.2.1.2 Thermal Expansion Testing 3.9-6 3.9.2.1.2.1 Measurement Techniques 3.9-6 3.9.2.1.2.2 Monitoring Requirements 39-6 3.9.2.1.2.3 Test Evaluation and Acceptance Criteria 3S-6 39.2.1.2.4 Reconciliation and Corrective Actions 3.9-7 3.9.iii t
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Amendment
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ABWil mome.
' Standard Plant nrv n SECTION 3.9 CONTENTS (Continued)
Section Title Page 3.9.2.2 Scianic Qualification of Safety-Related Mechanical Equipment (Including Other RBV Induced Loads 3.9-9 f
l 3.9-iii.1 Amendment
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.ABWR macase Standard Plant nry a SECTION 3.9 TABLES (Continued)
Table Title Pape 3.9-9 Reactor Coolant System Pressure Isolation Valves 3.9-5832 3.9-10 Welding Activities and Weld Examination Requirements for ASME Code,Section III Welds 3.9-5833 ILLUSTRATIONS Figure Title Page 3.9-1 Transient Pressure Differential Following a Steam Line Break 3.9-59 3.9-2 Reactor Internal Flow Paths and Minimum Floodable Volume 3.9-60 3.9-3 ABWR Recirculation Flow Path 3.9-61 3.9-4 Fuel Support Pieces 3.9-62 3.9-5 Pressure Nodes for Depressurization Analysis 3 S-63 39-6 Stress-Strain Curve for Blowout Restraints 3.9-64 3.9 xii Amendment
.ABWR meme Standard Plant nrv n The loading combinations and design criteria 3.9.I.6.1 ASME Code Welding for pipe whip restraints utilized to mitigate the effects of postulated piping f ailures are Welding activities for pressure boundary and provided in Subsection 3.6.2.3.3.
core support structure shall be performed in accordance with the requirements of Section III In the case of the RIP motor casing failure or Section Vill as applicable, of the ASME crent, there are specific restraints applied to Code. The required nondestructive examination mitigate the effects of the failure. The and acceptance criteria are stated in Table mitigation arrangement consists of lugs on the 3.910. Component supports shall be fabricated RPV bottom head to which are attached two long and examined in accordance with the requirements rods for each RIP. The lower end of each rod of Subsection NF of Section III of the ASME Code engages two lugs on the RIP motor / cover. The use and NCIG-01.
of inciastic analysis methods is limited to the middle slender body of the rod itself. The 3.9.I.6.2 Welding of Non-ASME Pressure attachment lugs, bolts and clevises are shown to Retaining Piping be adequate by clastic analysis. The selection of stainless steel for the rod is based on its Welding activities involving non-ASME high ductility assumed for energy absorption pressure retaining piping shall be accomplished during inelastic deformation.
in accoradnce with written procedures and shall meet the requirements of the ANSI B31.1 Code.
The mitigation for the CRD housing The weld acceptance criteria shall be as defined t
attachment weld failure is by somewhat different for the applicable nondestructive examination means than are those of the RIP in that the method described in ANSI B31.1 Code.
components with regular functions also function to mitigate the weld failure effect. The 3.9.2 Dyrtamic Testing and Analysis r
components are specifically:
3.9.2.1 Piping Vihretion, Thermal Expansion, (1) Core support plate and Dynamic Effects (2) Control rod guide tube The overall test program is divided into two phases; the preoperational test phase and (3) Controt rod drive housing the initial startup test phase. Piping vibra.
tion, thermal expansion and dynamic effects test-(4) Controt rod drive outer tube ing will be performed during both of these phases as described in Chapter 14. Subsections (5) Bayonet fingers 14.2.12.1.51,14.2.12.2.10 and 14.2.12.2.11 re-late the specific role of this testing to the ov-Only the cylindrical bodies of the control crall test program. Discussed below are the gen-rod guide tube, control rod drive housing and cral requirements for this testing. It control rod drive outer tube are analyzed for energy absorption by inelastic deformation.
Inclastic analysis for there latter two events together with the criteria used for evaluation are consistent with the procedures described in Subsection 3.6.2.3.3 for the different components of a pipe whip restraint.
Figure 3.9-6 shows the stress-strain curve used for the blowout restraints.
4.9.1.6 Welding Methods and Acceptance Criteria for ASME Code Welding and Welding of Non4SME Pressure Retai: ring Piping Amendment 3.9-31 j
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- GWR 234 exons Standard Plant REV.B Table 3.9-10 WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR ASME CODE, SECTION III WELDS CLASS 1 COMPONENTS (1) (?) (3)
Component Weld Type NDE Requirements Vessel Category A(Longitudinal)
RT plus MT or PT Vessel, Pipe, Pump, Valve Category B (Circumferential)
RT plus MT or I'T Pipe, Pump, Butt weld RT plus MT or Fr Valve Fillet and socket welds MT or Fr Vessels (6)
Category C and similar welds RT plus MT or PT. RT must be multiple exposure Parual penetration and fillet welds MT or PTon all accessible surfaces Vessels (6)
Category D
& Branched Connections a) Butt welds, all RT plus MT or PT b) Comerweldednozzles RT plus MT or PT c) Comer welded branch and RT plus hff or PT
[
piping connection exceeding 4" nominal diameter d) Comer welds branch and MT or Fr piping 4" and less e) Weld buildup deposits at UT plus a, b, e above if connected to openings nozzle or pipe f) Partial penetration MTor PTprogressive and fmal surfre g) Oblique full pene: ration branch RT or UT plus hfr or Fr. In addition, and piping connections UT of weld, fusion zone, and parent metal beneath attachment surface.
General Fillet, partial penetration, socket MT or FT welds General Structural attrhment welds hfT or PT SpecialWelds
- 1) Specially designed seals hfr or l'T
- 3) Hartismfacing PT l
a) Valves 4" or less None
~
- 5) Brazedjomts NT b
L 3.9-58.33 l Amendment
4 j
'ABWR.
23unmat Standard Plant REV.B j
Table 3.9-10 i
WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR ASME CODE, SECTION III WELDS (CONTINUED)
Cl ASS 2 COMPONENTS (1) (2) (o Component Weld Type -
NDE Requirements Vessel Category A(Longitudinal) a) Eitherof themembersexceeds RT 7
3/16 inch b) Each member 3/16 in. or less MT, PT, or RT l
Pipe, Pump, Valve Longitudinal RT Vessel Category B (Circumferential) a) Eitherof the members exceeds RT l
3/16 in.
b) Each member 3/16 in.or less MT, PT, or RT l
l Pipe, Pump and Valve Circumferential
,i a) Buttwelds RT i
b) Fillet and parnal penetration MT or PT -
l Vessel (6)and Similar Category C l
Joints in Other Components a) Cornerjoints,eitherof the RT members exceeds 3/16 in. of thickness.
b) Each member 3/16 in. or less MT, PT, or RT c) Partial penetration and fillet MT or FT welds
.l Vessel (6) and Similar Category D j
Welds in Other Components a) Full penetration joints when RT i
either members exceed 3/16in.
l of thickness l
b) Fullpenetrationcornerjoints MT or PT i
when either member exceeds
.]
3/16 in..
j c) Both members 3/16 in. or less MT or PT
$ Partialpenetration and fillet MT or PT i
weldjoints Branch Con.and Nozzlesin a) Nominal size exceed 4 in.
RT l
Pipe, Valve, Pump b) Nominal size 4 in or smaller MTorPT(externaland accessible j
internalsurfaces) j I
1
)
i 3.9.$8.34 l Amendmera
\\
l ABWR m eionan Standard Plant mB i
Table 3.910 WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR 1
ASME CODE, SECTION III WELDS (CONTINUED)
CI AS9 2 COMPONf?NTS d) (2) 44) (Continued)
Component Weld Type NDE Requirements Vessels Designed to Category A RT NC-3200 Category B RT Category C, Buu weld RT Category C, Full penetration corner UT or RT Category C, Panial penetration MT or PT both sides i
comer and fillet welds Category D, Full penetration (6)
RT Category D, Partial penetration MT or PT both sides Fillet, panial penetration, socket, and MT or PT structural attachment welds SpecialWelds a) Specially designed seals hit or PT b) Weld metal cladding MT or PT c) Hard surfacing PT
$ Hard surfacing for valves with None irdet connection 4" nominal pipe size or less e) Tube-tube sheet welds PT f)
Brazedjoints
\\T i
Storage Tanks a) Side joints RT l
(Atmospheric) b) Roof and roof-to-sidewall NT c) Bottom joints Vacuum box testing of at least 3 psi G Bottom to sidewall Vacuum box plus MT or PT e) Noz2le to tank side MT or PT f)
Nozzle to roof VT g) Joints in nozzles RT h) 06ers Similar weldsin vessels Storage Tanks a) Sidewall RT (0-15 psi) b) Roof RT c) Roof-to-sidewall RT,if not possible, hfT or PT d) Bottom & bottom-to-side Vacuum box method plus hfT or FT e) Nozzle tank MT or FT f) Jointe to nozzles RT f) Others Same as similar vesseljoin:s i
3.9-58 35 l Amendmem
t
[_
-ABWR 23A6100AE REV.B Standard Plant 1
Table 3.9-10 WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR ASME CODE, SECTION III WELDS (CONTINUED)
Cl ASS 3 COMPONFNTS (1) (2) (e).
Component Weld Type NDE Requirements Vessels Category A(Longitudinal) 1.
a) Dickness exceeding the RT limits of Table ND.5211.2-1 b) Weldsbasedonjoint RT l
efficiency permitted by ND3351.1 c) Butt weldsin nozzles RT l
anached to vessels in a or b above 2.
Welds notincluded in 1 above Spot RT each 50 ft of weld. Additional RT to cover each welders work.
3.
Nonferrous vessels exceedmg RT 3/8 inch Pump, Valve, Pipe Pipes greater than 2 in. size RT, MT, or FT l
Pumps & valves greater than 2 in.
According to the product fann Vessel Category B (Circumferential) i 1.
a) nickness exceeds Table RT l
ND.5211.2 for fenous j
metals b) Thickness exceeds 3/8 in.
RT for nonferrous metals c) Jointefficiencyaccordingto RT
[
ND3352.l(a) 4 4 Attachmentstovesselsand RT exceeds nominalpipe size 7
10 in, or thickness 1 1/8 in.
L 2.
Welds not involved in 1 above RT 6 in. long sections plus the intersections of Category A welds j
t Pipe, Pump and Valve Greater than 2 in. nominal pipe size RT, PT, or MT
~
r Vessel Category C 1.
a) RicknessexceedsTable RT l
b) Anachments exceed 10 inch RT NPS or 1 1/8 in, wall thickness 2.
Welds not involved in 1 m 2 Spot RT to cover each welders work
[
above 1
Pipe, Pump, Valves Greater than 2 in nominal pipe size RT, PT, or MT l
i I
f 3.9-5E36 l Amendmcra e
P a
'ABWR mamE Standard Plant REV B I
n f
Table 3.9-10 WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR i
ASME CODE, SECTION III WELDS (CONTINUED) j t
CI A99 3 COMPONENTS (1) (2) (M (Continued) l Component Weld Type NDE Requirements
.l Vesse!
Category D 1.
Full penetration butt welds RT 1
designed forjoint efficiency per ND3352.l(a) 2.
In nozzles or communicating RT-chambers anached to vessels or I
heads requiring fullRT 3.
Welds not covered by I and 2 Spot RT to cover each welders work, above i
Pipe, Pump and Valve Greater than 2 in. nominal pipe size RT, PT, or MT
-l SpecialWelds
. a) Weld metalcladding PT b) Hard surfacing -
PT (i) Hardsurfacingforvalvec None with inlet connection 4" nominal pipe size orless f
c) Tube-tube sheet welds PT d>
Brazedjoints VT f
Storage Tanks a) Sidewalljoints Same as Category A or B vesseljoints (Atmospheric) b) Roof and roof-to-sidewall VT c) Bottom joints Vacuum box testing of at least 3 psi.
j or PT or MT plus VTduring pressure test 4 Bottom to sidewall Same as bottom joints
}
c) Nozzle to tank side MT or Irr f) Nczzle to roof VT g) Joints in nor21es ex. roof MT or FT nor21es h) Others Similar welds in vessels Storage Tanks a) Sidewall Same as Category A or B vesseljoints (0-15 psi) b) Roof Same as Category A vesseljoints.
l h
c) Roof-to-sidewall Same as above,if possible, or MT or l
@ Bottom & bonom-to-side Vacuum box testing at least 3 psi, or.
PT or MT plus VT during pressure test c) Nozzle to tank MT or PT f) Joints in nozzles M T or Irr
[
g) Others Same as similar vesseljoints j
i l
l i
l Amendmem 3.9-58 37 l-
~
ABWR 1
memt Standard Plant mB j
j
~!
Table 3.910 l
WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR l
ASME CODE, SECTION-III WELDS (CONTINUED)
{
t COMPONENTS St!PPORTS (11' (2) (7)
?
Component Weld Type NDE Requirements l
k Class 1 Suppons Primary member, full penetration RT-bun welds 1
Secondary member welds -
VT I
Class 2 and MC Supports Primary member, full penetration RT
+
buu welds Parnal penetration or fillet welds hfr or PT throat greater than 1 in.
Secorxiary member welds VT Class 3 Supports Primary member, groove or throat MT or PT l
greater than 1 in.
Special Requirements, All Welds transmitting loads in the UT base metal beneath the weld i
Classes through thickness direction in members greater than 1 in.
?
A L
5 I
h
-i l
?
I i
6 I
I Amendmern 3.9-56.36 l l
l
~.
/ABWR.
useioois
.l Standard Plant mB Table 3.910 l
WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR j
ASME CODE, SECTION III WELDS (CONTINUED)
)
CORE SI'PPORT STRitCTifRFR (1) (2) (R)
I Component Weld Type NDE Requirements
(
i Core Support Structures Category A, longitudinal butt welds Examination may be by any technique -
(Provide direct support or Category B, circumferential butt or certain combinations of techniques, restraint of the fuel, etc.
welds from simple VT to MT or PT plus RT under normal operating Category C, flange to shcIl welds or UT. Quality factor n and fatigue conditions.)
Category D, nonle to shell welds factorfare dependent on the
_l Category E, beam end connections to technique (s) selected, in accordance other structures with Table NG-3352-1.
j f
Repair welds under 3/8 in. or 10%
4 i
Repair welds over 3/8 in.or 10%
1 M
i i
Intemal Structures Same as above Same as above l
l (Can be any other structure
}
within the reactor vessel.)
r.nnmanwnry j
j Temporary Attachments All MT or PT (Removed before operation.)
NOTES:
l l
3 (1) The required confirmation that facility welding activities are in compliance with the certified design commitments will include the following third-party verifications-l l
(a) Facility welding specifications and procedures meet the applicable AShE Code requirements;
[
(b) Facility welding activities are performed in accordance with the applicable A ShE Code requirements; I
(c) Welding activities related records are prepared, evaluated and maintained in accordance with the ASME l
Coderequirements; (d) Welding processes used to weld dissimilar base metal and welding filler metal combinations are compatible for the intended applications.
.l (e) The facility has established procedures for qualifications of welders and welding operators in accordance i
with the applicable ASME Code requirements; (f) Approved procedures are available and used for preheating and post feating of welds, and those procedures j
meet the applicable requirements of the AShE Code, (g) Completed welds are examined in accordance with the applicable examination method required by the t
ASME Code.
(2) Radiographic film will be reviewed and accepted by the licensee's nondestructive examination (NDE), level III examiner prior to finalacceptance.
l Amendment 39-5839 l
t
4 l
l MN 23A6100AE REV.B Standard Plant l
Table 3.910 j
WELDING ACTIVITIES AND WELD EXAMINATION REQUIREMENTS FOR i
ASME CODE, SECTION III WELDS (CONTINUED) i
[
Notes (continued):
(3) ne NDE requirements for Class I components will be as stated in subarticle NB-5300 of Section 111 of the l
ASME Code.
(4) ne NDE requirements for Class 2 components will be as stated in subarticle NC-5300 of Section 111 of the
[
AShE Code.
(5) ne NDE requirements for Class 3 components will be as stated in subanicle ND-5300 of Section III of the ASME Code.
i (6) ne NDE requirements for containment vessels will be as stated in subarticle NE-5300 of Section Ill of the ASME Code.
l (7) ne NDE requirements for component supports will be as stated in subarticle NF-5300 of Section III of the ASME Code.
(8) ne NDE requirements for Core Suppon structures will be as stated in subanicle NG-5300 of Section III of the AShE Code.
(9) For corner joints UT may be used instead of RT. For Type 2 full penetration corner weld joints,if RT is used, the fusion zone, and parent metal beneath the attachment surface shall be UT examined after welding.
LEGESR RT-Radiographic Examination UT - Ultrasonic Examination MT-Magnetic Particle Exammatiort FT-Liquid Penetrant Exammation VT - Visual Exammation LEGEND (Continued):
C A
A 4
g s@
A
'i
- $y N
y
\\ \\
0 l
0 8
a O
C Categories A B, C, and D Welded Joint Typical Locations i
3 9 58 40 l Amendmers
.