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Line 74: |
Line 74: |
| 4.4 Cateaor 0 Welds 4.4.1 Oversize Fillet Welds 4.4.1.1 The weld shall meet or exceed the specified size or both fillet weld legs | | 4.4 Cateaor 0 Welds 4.4.1 Oversize Fillet Welds 4.4.1.1 The weld shall meet or exceed the specified size or both fillet weld legs |
| ~requirements. | | ~requirements. |
| exceed ~gn Either size. %elds may be longer than specified. Continuous welds may be | | exceed ~gn Either size. %elds may be longer than specified. Continuous welds may be accepted in place of intermittent welds. Un-equal leg fillets are acceptable, provided the smaller leg meets or exceeds minimum require-ments. |
| -
| |
| accepted in place of intermittent welds. Un-equal leg fillets are acceptable, provided the smaller leg meets or exceeds minimum require-ments. | |
| 4.4.2 Undersize Welds 4.4.2.1 The fillet leg dimension shall not under run the nominal fillet size by more than 1/16 inch. | | 4.4.2 Undersize Welds 4.4.2.1 The fillet leg dimension shall not under run the nominal fillet size by more than 1/16 inch. |
| 4.4.2.2 Groove welds may be undersize by 5 percent or 1/16 inch, whichever is greater. | | 4.4.2.2 Groove welds may be undersize by 5 percent or 1/16 inch, whichever is greater. |
Line 97: |
Line 95: |
| 1d Oversize Fillet Welds 4.5.1.l The weld meets or exceeds specified size re-quirements. Either or both fillet weld legs may exceed design size. Welds may be longer than specified. Continuous welds | | 1d Oversize Fillet Welds 4.5.1.l The weld meets or exceeds specified size re-quirements. Either or both fillet weld legs may exceed design size. Welds may be longer than specified. Continuous welds |
| 'lace of intermittent- welds. | | 'lace of intermittent- welds. |
| may be Unequal leg fil-in accepted | | may be Unequal leg fil-in accepted lets are acceptable, provided the smaller leg meets or exceeds minimun requirements. |
| .
| |
| lets are acceptable, provided the smaller leg meets or exceeds minimun requirements. | |
| 4.3.2 Undersize Welds 4.3.2al 'The fillet leg dimension may not under run the nominal fillet size by more than 1/16 inch. | | 4.3.2 Undersize Welds 4.3.2al 'The fillet leg dimension may not under run the nominal fillet size by more than 1/16 inch. |
| Fillet weld size need not be greater than the thickness of the thinner member. | | Fillet weld size need not be greater than the thickness of the thinner member. |
Line 124: |
Line 120: |
| Page 19 of 19 | | Page 19 of 19 |
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Rev 0 to, Visual Exam Acceptance Criteria for Reverification Insp of Welded Structures.ML17277A436 |
Person / Time |
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Site: |
Columbia |
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Issue date: |
05/12/1982 |
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From: |
Cygelman A BURNS & ROE CO. |
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To: |
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Shared Package |
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ML17277A434 |
List: |
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References |
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QVI-09, QVI-09-R00, QVI-9, QVI-9-R, NUDOCS 8302090404 |
Download: ML17277A436 (14) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292A3921996-06-30030 June 1996 WNP-2 Ten Mile EPZ Evacuation Time Estimate Study. ML17291B2931995-12-31031 December 1995 Adjustable-Speed Drive Retrofit for Ormond Beach Fd Fans. ML17291B1401995-07-0606 July 1995 Technical Evaluation Rept,Wppss Plant No 2,Pump & Valve Ist,Rev 0,Second Ten-Yr Interval. ML17291A9421995-06-30030 June 1995 Rev 0 to IPE of External Events WNP2. ML17291A5691994-12-0707 December 1994 Simulator Facility Certification. ML17291A4481994-10-13013 October 1994 WNP-2 Response to Request for Addl Info on Emergency Classification. ML17290A9181993-12-27027 December 1993 Justification for Revised Tornado Design Criteria,Rev 1. ML17290A6901993-10-0808 October 1993 Revised Significant Hazards Consideration Assessment for WNP-2 Power Uprate W/Elll. ML17290A6861993-09-27027 September 1993 Rev 1 to Evaluation of Sources of Radioactive Matl Found in Cooling Tower Sediments at Washington Nuclear Plant 2. ML17290A3831993-05-18018 May 1993 Rept R-R8-111 Re Flaw in Reactor Recirculation Piping ML17289B0751992-11-23023 November 1992 Rev 0 to Technical Memorandum Tm 2025, Secondary Containment/Standby Gas Treatment Design Basis. ML17289A9881992-10-0707 October 1992 Containment Atmosphere Control Sys (CAC) Summary Issues. ML17289A7251992-06-30030 June 1992 Institutional Custody Fiduciary Svcs. ML17289A7231992-06-30030 June 1992 Institutional Custody Fiduciary Svcs. ML17289A9281992-06-24024 June 1992 WNP-2 Simulator Certification NRC Form 474 Supporting Documentation. ML17289A5351992-05-11011 May 1992 App B, 8X8 Extended Burnup, of EMF-92-040, WNP-2 Cycle 8 Reload Analysis. ML17286B0211991-08-20020 August 1991 Root Cause Analysis Summary, Unsatisfactory Licensed Operator Requalification Program, Reflecting Causes of Operators Continued Inability to Respond to Severe Accident Conditions ML17286A9151991-06-30030 June 1991 Asset Summary 910630. ML17286A9141991-06-30030 June 1991 Summary of Transactions for 900630-910630. ML17285A9631989-12-27027 December 1989 Feedwater Nozzle Insp Rept for Refueling Outage RF89A Spring 1989. ML17285A8871989-08-14014 August 1989 Rev 0 to Commercial Grade Dedication Project for Wppss Contract C-30298. ML17285A6411989-07-31031 July 1989 Instrument Air Sys Review Response to Generic Ltr 88-14. W/Six Oversize Figures ML17285A1971988-12-14014 December 1988 Feedwater Nozzle Insp Rept for Refueling Outage RF88A, Spring,1988. ML20237D3121987-11-30030 November 1987 Final Feedwater Temp Reduction Summary Rept ML17279A6251987-04-30030 April 1987 Rev 2A to Wnp 1,2 10-Mile EPZ Evacuation Time Assessment Study. ML17279A1911987-04-0707 April 1987 Comparision of Electrical Design of Wye Pattern Globe Valve Actuator W/Ball Valve,Hanford 2 & River Bend Design. Five Oversize Drawings Encl ML17279A2341987-03-31031 March 1987 Washington Nuclear Plant 2 Performance Indicator Rept. ML20207N2661986-12-31031 December 1986 Assessment of Fire Protection Program Responsibilities & Administration ML20215B7271986-11-25025 November 1986 Feedwater Nozzle Insp Rept for Refueling Outage RF86A, Spring 1986 ML17278B0001986-08-22022 August 1986 Results of Insp of WPPSS-2 Cycle 1 Discharge Fuel. ML17279A6481986-05-0101 May 1986 Draft Lead Test Assembly Program,Wpps 2. ML17278A8051986-03-31031 March 1986 Safety Review of Wppss Nuclear Project 2 at Core Flow Conditions Above Rated Flow Throughout Cycle 1 & Final Feedwater Temp Reduction. ML17278A4721985-09-30030 September 1985 Crdr & Emergency Procedure Functional Task Analysis Summary Rept. ML17278A4281985-07-31031 July 1985 Washington Nuclear Plant Unit 2 Spray Pond Drift Loss Rept. ML17277B6191985-01-31031 January 1985 Rev 2 to Description of Early Warning Sys for Wppss Nuclear Plants 1 & 2. ML17277B5241984-10-0808 October 1984 Feedwater Piping Thermal Deflection Events, Final Design Engineering Rept ML17277B2451983-12-30030 December 1983 RHR Addendum to Design Verification Program. ML17277B2201983-12-11011 December 1983 Qualification of Purge & Vent Valves at WPPSS-2, Vols 1 & 2 ML20080N1941983-12-0707 December 1983 Excerpt from Qvp Overview Rept,Vol I,Book 1 of 1.Related Info Encl ML17277B2961983-11-30030 November 1983 Rept to Governor J Spellman of State of Wa & Governor V Atiyeh of State of Or. ML17277B2231983-11-0808 November 1983 Qualification of Purge & Vent Valves at WPPSS-2, Vol 4: Rev 4 to Equipment Seismic & Hydrodynamic Requalification of 24-Inch Cylinder Operated Butterfly Valves for CSP-V-3, 4,5,6 & 9 & CEP-V-3A & 4A. ML17277B2221983-11-0404 November 1983 Qualification of Purge & Vent Valves at WPPSS-2, Vol 3: Rev 2 to Equipment Seismic & Hydrodynamic Requalification of 30-Inch Cylinder Operated Butterfly Valves CSP-V-1 & 2 & CEP-V-1A & 2A. ML17277A9431983-10-0707 October 1983 Response to NRC Human Factors Engineering Preliminary Design Assessment Audit Rept of 830826. ML17277A8701983-09-30030 September 1983 Design Reverification Program, Vols 1 & 2,final Assessment Rept ML20078M2661983-09-30030 September 1983 Independent Evaluation of Plant Verification Program at WPPSS-2:Vol I Quality Verification ML20080T2071983-09-22022 September 1983 Engineering Insp & Evaluation of Quality Class Ii/Seismic Category I Pipe Supports ML17277A8541983-09-21021 September 1983 Quality Verification Program,Vol 1:Overview Rept,Jul-Sept 1983. ML17292A8091983-09-20020 September 1983 Sheet 1 to Reactor Protection Sys. ML17277A9961983-09-0909 September 1983 Hanford 2 Power Generation Control Complex (Pgcc) Floor Plate Design. 1998-03-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML17292B5571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML17292B4791998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17292B5741998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 990225 Ltr ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7831998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With 981007 Ltr ML17284A7491998-09-10010 September 1998 WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998. ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7681998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With 980915 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2.W/980810 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6751998-06-30030 June 1998 Ro:On 980617,flooding of RB Northeast Stairwell with Consequential Flooding of Two ECCS Pump Rooms.Caused by Inadequate Fire Protection Sys Design.Pumped Out Water from Affected Areas to Point Below Berm Areas of Pump Rooms ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17284A6491998-05-31031 May 1998 Rev 0 to COLR 98-14, WNP-2,Cycle 14 Colr. ML17292B4031998-05-31031 May 1998 Monthly Operating Rept for May 1998 for WNP-2.W/980608 Ltr ML17292B3921998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for WNP-2.W/980513 Ltr ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3371998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for WNP-2.W/980409 Ltr ML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B2911998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for WNP-2.W/980313 Ltr ML17284A7971998-02-17017 February 1998 Rev 28 to Operational QA Program Description, WPPSS-QA-004.With Proposed Rev 29 ML17292B3591998-02-12012 February 1998 WNP-2 Cycle 14 Reload Design Rept. 1999-09-30
[Table view] |
Text
QVI-09 Rev. 0 WP-2 PROJECT VISUAL EXAMINATION ACCEPTANCE CRITERIA FOR REVERIFICATION INSPECTION
. WELDEO STRUCTURES Approved Burns h R nc.
A. I. Cygelman Attachment 2 (Page 1 of 9) 8302090404 830ii7 Page 11 of 19 PDR ADOCK 05000397 6,>> '
PDR
QVI-09 Rev. 0 1.0 SCOPE This document-provides, visual examination acceptance criteria -for reveri-
.fication inspection of'tructural steel and miscellaneous metal, welding, performed in accordance with AWS 01.1, the Structural Welding Code.
These criteria reflect requirements consistent with the engineering approval specified in AWS Ol.l for evaluation of structural welding.
This document."also includes acceptance standards for light gauge HVAC ductwork, and other systems which are not specifically covered by AWS Ol.l.
1.1'hese criteria shall be used by Construction Quality Control for performing reverification inspection by including it on the QCIR as an applicable inspection reference criteria document to evaluate deviations to AWS Dl.l.
2.0 CODES ANO STANDARDS The criteria in thds document provide the basis for visual examination of AWS Dl.l wel'ding. The required engineering approval, as specified in Paragraphs 3.7.4 and 3.7.5 of A'WS.D1.1 has been provided by the Architect
. Engineer Auhhorization for this is given in Paragraph lU of AWS Dl.l.
3.0 BASIS FOR EVALUATION The applicable weld categories will be entered on the QCIR as a part of the inspection reference criteria based upon the definitions described below.
3.1- Cate or A Welds Must be in accordance with the visual acceptance criteria of the specified section of AWS Dl.l..This category applies to elements of
. fms, crangs, rotating equipment, and other machinery subject to frequent stress reversals.
3.2 Cate or B Welds Have an acceptance level modified to meet the required sezvice con-ditions. This category applies to members of the building frame that carry principal design loads, radial beams, sacrificial shield wall, pipe whip restzaints, pipe supports, and similar principal load bearing structures.
Attachment 2 (Page 2 of 9)
Page 12 of 19
I IVI-09
~hid Rev. 0
. j
- 3. ~tl Are connections between Category B Steel and Miscellaneous Metal.
Are not part of the main building frame, but rather provide support or framing for electrical, instrumentation, and HVAC systems, com-ponents and equipment. Also included in the 0 Category are welds joining miscellaneous metal including, but not limited to, stair-ways, embedments, fan housings, doors, windows, hatches, frames, ledger angles, gratings and their supports.
Is an acceptance level established for relatively thin materials such as HVAC ductwork, cable trays, and unistrut supports.
- 4. 0 ACCEPTANCE CRITERIA Acceptance shall be based on the weld joint meeting each criteria listed for the applicable category. Skewed joints will be evaluated in accordance with Correct Specifications and Project Engineering Directives.
.! ~t 4.l.l Category A ~ must comply with the visual exaninatQ)n requirements of the specified section of AWS Dl.l.
4.2.1 Oversize Fillet Welds The weld shall meet or exceed the specified size require-ments. Either or both fillet weld legs may exceed design size. Welds may be longer than specified. Continuous welds may be accepted in place of intermittent welds.
Unequal leg fillet welds are acceptable, provided the smaller leg meets or exceeds minimum requirements.
4.2.2 Undersize Welds 4.2.2.1 The fillet leg dimension shall not under run the momiral fQ.let size by more than 1/16 inch. For flange to web jolts the undersize condition may not be within two flange thicknesses of the weld end.
Attachment 2 (Page 3 of 9)
Page 13 of 19
e~ 0 QVI-09 Rev. 0 4.2.2.2 Groove welds may be underfilled by 5 percent. or 1/32-inch, whichever is greater.
s 4.2.3 Porosit and Sla 4.2.3.1 The weld may contain a maximum of 5 percent by surface area of unaligned porosity and/or slag.
45 4.2. 4 Pre l'ile li 4.2".4.1 Convexity height, roll over, and butt weld rein-
.forcement are acceptable.
W 4
i~i 4.2.5 Craters 4.2.5.1 The weld may have an underfilled crater, pro-vided the underfill depth does not exceed 1/16 inch, and the crater has a smooth contour blend-ing gradually with the adjacent weld and base metal without acute notches.
4 2.6 Undercut e 4.2.6.1 Continuous undercut shall not be greater than:
1/32 inch for material 3/8 inch and less; 1/16
'inch for material over 3/8 inch thick.
Intermittant undercut may be twice the value for continuous undercut War a maximum 'ccumulated length of lOX of weld lenath. Localized under-cut less than 3/8 inch in length may'e accepted provided the depth does not exceed 3/32 inch for thickness 3/4 inch and less or 1/8 inch for ness. ovar 3/4 ~es.
4.2.7 Cracks 4.2.7.1 Cracks are unacceptable.
4.2.8 Fusicn 4.2.8.1 Incomplete fusion between weld metal and base metal is unacceptable.
Attachment 2 (Page 4 of 9)
Page 14 of 19
e QVI-09 Rev. 0 4.2.9 Weld S atter 4.2.9.1 Weld spatter shall be acceptable.
4.2.10 Arc Strikes 4.2.10.1 Arc strikes are acceptable provided there are no
.11 ~it 4.2.11.1 cracks.
The fitup of backing bars is not a basis for
- ~L" 4.3.1 id The welds on rejection.,
the main frame member side shall meet the requirements for Category B.
4.3.2 The welds on the miscellaneous metal, side shall meet the xe uirements for Category 0.
4.4 Cateaor 0 Welds 4.4.1 Oversize Fillet Welds 4.4.1.1 The weld shall meet or exceed the specified size or both fillet weld legs
~requirements.
exceed ~gn Either size. %elds may be longer than specified. Continuous welds may be accepted in place of intermittent welds. Un-equal leg fillets are acceptable, provided the smaller leg meets or exceeds minimum require-ments.
4.4.2 Undersize Welds 4.4.2.1 The fillet leg dimension shall not under run the nominal fillet size by more than 1/16 inch.
4.4.2.2 Groove welds may be undersize by 5 percent or 1/16 inch, whichever is greater.
Attachment 2 (Page 5 of 9)
Page 15 of 19
QVI-09 Rev. 0 4.4.3 Porosit and Sla 4.4.3.1 Porosity and slag are not a basis for rejection.
4.4.4 Profile 4.4.4.1 Convexity height, roll over, and butt weld rein-forcement, are acceptable.
4.4. 5 Fusion 4.4.5.1 Incomplete fusion between weld metal and base metal is unacceptable.
4.4.6 Undercut 4.4.6.1 Undercut not exceeding 3/32" for material up to 3/4" thick, and 1/8" for material over 3/4" thick, may be acceptable for the full length of the weld. I~ ~
447 Craters 4.4.7.1 Underfilled groove weld craters shall be accepted provided the depth of underfill is 1/16 inch or less. Underfilled single-pass fillet weld craters shall be accepted provided the crater length is less than 5 percent of the weld length. Qn multi-pass filet welds a crater depth of 1/16 inch or less is acceptable.
4.4.8 Cracks 4.4.8.1 Ml cracks ere unacceptable.
4.4.9 Misali nment 4.4.9.1 Misalignment not in excess of the thinner member thickness is acceptable.
4.4.10 Arc Strikes 4.4.10.1 Arc strikes are acceptable provided there are no cracks.
Attachment 2 (Page 6 of 9)
Page 16 of 19
QVI-09 Rev. 0 4.4.11.1 The fit-up of backing bars is not a basis for rejection.
- 4.4.12 Weld Soatter 4.4.12.1 Weld spatter shall be acceptable.
1d Oversize Fillet Welds 4.5.1.l The weld meets or exceeds specified size re-quirements. Either or both fillet weld legs may exceed design size. Welds may be longer than specified. Continuous welds
'lace of intermittent- welds.
may be Unequal leg fil-in accepted lets are acceptable, provided the smaller leg meets or exceeds minimun requirements.
4.3.2 Undersize Welds 4.3.2al 'The fillet leg dimension may not under run the nominal fillet size by more than 1/16 inch.
Fillet weld size need not be greater than the thickness of the thinner member.
4.3.2.2 Groove fields may be unders'ze by 3 percent by 1/32 inch, whichever is greater.
Porosi t or Sla Inclusions 4.5.5.1 -Porosity or slag inclusions are not e criteria for rejection.
4.5.4 Profile 4.5.4.1 Convexity height, roll over, and weld reinforce-ment are acceptable.
a.5.5 Cracks 4.5.5.1 All cracks are unacceptable.
Attachment 2 (Page 7 of 9)
Page 17 of 19
QVI-09 Rev. 0 4.6.6 Fueicn 4.5.6.1 Incomplete fusion between weld metal and base metal is unacceptable.
4.5.7 Undercut 4.5.7.1 (Same as 4.2.6.1) 4.5.8 11 t 4.5.8.1 Misalignment is not a basis for rejection.
4.5.9 Corner Welds 4.5.9.1 Corner welds used to seal ductwork are design-ated partial penetration welds. Such welds do not require full fusion. Weld reinforcement greater than the material thickness. shall verify the adequacy of the weld, provided that the toes of the weld have complete fusion.
1..1 ~t 4.5.10.1 Fillet welds joining turning vanes to turning vane rails or to heavier gauge ductwork may ex-ceed the profile and convexity limits as pre-viously described and are acceptable for this application. Minor burn-through on vanes will be permitted up to 1/4 inch in length, provided equivalent lengths of fillet welds are added to ccmpensate for welds weakened by burn-through 4.5.10.2. Burn-through is permitted provided there are no visible through-thickness holes.
Metal flow on the inside of the duct is per-mitted, provided it is fused completely with the parent metal and metal thickness is not reduced by greater than 50 percent.
4.5.11 Arc Strikes 4.5.11.1 Arc strikes are acceptable provided there are no cracks.
Attachment 2 (Page 8 of 9)
Page 18 of 19
QVI-09 Rev. 0
~ld tt 4.5.12.1 Weld spatter shall be acceptable.
4.5.13 Backin . Fit-U 4.5.13.1 The fit-up of backing bars is not basis for re-jection.
Attachment 2 (Page 9 of 9)
Page 19 of 19
%*as.