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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210M7291999-08-0505 August 1999 Replacement Pages to PGE-1078, Trojan Nuclear Plant License Termination Plan. with D&D Modeling Runs for Determination of Screening Dcgls & Survey Area Maps Indicating Preliminary Survey Units ML20207D3951999-06-0101 June 1999 Rev 1 to Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20204B7691999-03-18018 March 1999 Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl ML20207J3911999-03-10010 March 1999 Trojan Nuclear Plant License Termination Plan ML20207J0831999-02-11011 February 1999 Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated ML20153D3081998-09-21021 September 1998 Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20151X8671998-09-10010 September 1998 Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown ML20238E8291998-08-27027 August 1998 Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area ML20199J5801998-01-29029 January 1998 Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20196J5131997-07-29029 July 1997 Rev 0 to Trojan Second Integrated Test Rept,Filter Media Processing Sys Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20196J5241997-07-29029 July 1997 Rev 2 to In-Canal Equipment,Filter Media Processing Sys, Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20137T9361997-04-0808 April 1997 Rev 1 to Trojan Proof of Principle Test Summary ML20137G1731997-03-20020 March 1997 Rev 6 to Trojan Plant Procedure,Tpp 20-2, Radiation Protection Program ML20137K5151997-03-0404 March 1997 Rev 0 to Trojan Proof of Principle Test Summary ML20138L1901997-01-30030 January 1997 Reactor Vessel & Internals Removal Plan ML20134C9901997-01-28028 January 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134B8631997-01-16016 January 1997 Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building ML20134B5881997-01-16016 January 1997 Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134A9571997-01-16016 January 1997 Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions ML20135B5071996-11-27027 November 1996 Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI ML20129E7341996-10-23023 October 1996 Proposed Tech Specs Re Spent Fuel Pool Debris Processing ML20059L1721993-11-30030 November 1993 Final Update to PGE-1043,Amend 3, Accident Monitoring Instrumentation Review, Identifying Rept as Historical by Placing Explanation in Preface to Be Inserted at Front of Document ML20059A5601993-10-21021 October 1993 Proposed Tech Specs Modifying Security License Conditions for Clarity ML20057F1631993-09-30030 September 1993 Updated Trojan Nuclear Div Manual ML20057D9131993-09-30030 September 1993 Amend 14 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan. W/Four Oversize Drawings ML20056F9971993-08-26026 August 1993 Rev 9 to Odcm ML20127P2121993-01-27027 January 1993 Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator ML20126B7231992-12-0303 December 1992 Rev 13 to Chemistry Manual Procedure CMP 1, Primary-to-Secondary Leak Rate ML20127M6391992-11-16016 November 1992 Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI ML20126B7491992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.3, Post- SG Tube Rupture Cooldown Using Steam Dump ML20126B7061992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.2, SG Tube Rupture W/Loss of Reactor Coolant - Saturated Recovery Desired ML20126B7331992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.3, SG Tube Rupture W/O Pressurizer Pressure Control ML20126B7411992-09-25025 September 1992 Rev 8 to Event-Specific Emergency Instruction ES-3.2, Post- Steam Generator Tube Rupture Cooldown Using SG Blowdown ML20126B7451992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.1, Post- SG Tube Rupture Cooldown Using Backfill ML20126B7601992-09-25025 September 1992 Rev 18 to Emergency Instruction EI-3, SG Tube Rupture ML20126B7181992-09-23023 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.1, SG Tube Rupture W/Loss of Reactor Coolant - Subcooled Recovery Desired ML20126B7141992-08-20020 August 1992 Rev 19 to Off-Normal Instruction ONI-12, High Activity Radiation Monitoring ML20210D5281992-06-0808 June 1992 Errata to Amend 6 to PGE-1025, Environ Qualification Program Manual ML20141M1901992-03-27027 March 1992 Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl ML20126B7201992-01-24024 January 1992 Rev 2 to Off-Normal Instruction ONI-3-12, SG Tube Leak ML20062F7391990-11-15015 November 1990 Amend 4 to PGE-1049, Trojan Nuclear Plant Inservice Insp Program for Second 10-Yr Interval,Jan 1987 - Dec 1996 ML20059L6701990-09-21021 September 1990 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8941989-07-19019 July 1989 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20245C8091989-06-12012 June 1989 Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20247E5331989-03-29029 March 1989 Rev 0 to Procedure QTS-VT-100, Visual Exam Procedure ML20248D3271989-03-27027 March 1989 Rev 0 to QAP-VT-108, Visual Exam ML20247E5491989-03-0202 March 1989 Rev 0 to Procedure TNP-QAP-VT108, Visual Exam ML20235L9441989-02-10010 February 1989 Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story ML20235Q9191989-02-10010 February 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches ML20154D1781988-09-0909 September 1988 Proposed Tech Specs Revising Pressurizer LPSI Setpoint 1999-08-05
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210M7291999-08-0505 August 1999 Replacement Pages to PGE-1078, Trojan Nuclear Plant License Termination Plan. with D&D Modeling Runs for Determination of Screening Dcgls & Survey Area Maps Indicating Preliminary Survey Units ML20207D3951999-06-0101 June 1999 Rev 1 to Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20207J3911999-03-10010 March 1999 Trojan Nuclear Plant License Termination Plan ML20153D3081998-09-21021 September 1998 Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196J5241997-07-29029 July 1997 Rev 2 to In-Canal Equipment,Filter Media Processing Sys, Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20137G1731997-03-20020 March 1997 Rev 6 to Trojan Plant Procedure,Tpp 20-2, Radiation Protection Program ML20138L1901997-01-30030 January 1997 Reactor Vessel & Internals Removal Plan ML20059L1721993-11-30030 November 1993 Final Update to PGE-1043,Amend 3, Accident Monitoring Instrumentation Review, Identifying Rept as Historical by Placing Explanation in Preface to Be Inserted at Front of Document ML20057F1631993-09-30030 September 1993 Updated Trojan Nuclear Div Manual ML20057D9131993-09-30030 September 1993 Amend 14 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan. W/Four Oversize Drawings ML20056F9971993-08-26026 August 1993 Rev 9 to Odcm ML20126B7231992-12-0303 December 1992 Rev 13 to Chemistry Manual Procedure CMP 1, Primary-to-Secondary Leak Rate ML20126B7061992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.2, SG Tube Rupture W/Loss of Reactor Coolant - Saturated Recovery Desired ML20126B7601992-09-25025 September 1992 Rev 18 to Emergency Instruction EI-3, SG Tube Rupture ML20126B7451992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.1, Post- SG Tube Rupture Cooldown Using Backfill ML20126B7491992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.3, Post- SG Tube Rupture Cooldown Using Steam Dump ML20126B7411992-09-25025 September 1992 Rev 8 to Event-Specific Emergency Instruction ES-3.2, Post- Steam Generator Tube Rupture Cooldown Using SG Blowdown ML20126B7331992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.3, SG Tube Rupture W/O Pressurizer Pressure Control ML20126B7181992-09-23023 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.1, SG Tube Rupture W/Loss of Reactor Coolant - Subcooled Recovery Desired ML20126B7141992-08-20020 August 1992 Rev 19 to Off-Normal Instruction ONI-12, High Activity Radiation Monitoring ML20210D5281992-06-0808 June 1992 Errata to Amend 6 to PGE-1025, Environ Qualification Program Manual ML20126B7201992-01-24024 January 1992 Rev 2 to Off-Normal Instruction ONI-3-12, SG Tube Leak ML20062F7391990-11-15015 November 1990 Amend 4 to PGE-1049, Trojan Nuclear Plant Inservice Insp Program for Second 10-Yr Interval,Jan 1987 - Dec 1996 ML20247E5331989-03-29029 March 1989 Rev 0 to Procedure QTS-VT-100, Visual Exam Procedure ML20248D3271989-03-27027 March 1989 Rev 0 to QAP-VT-108, Visual Exam ML20247E5491989-03-0202 March 1989 Rev 0 to Procedure TNP-QAP-VT108, Visual Exam ML20153D6671988-08-31031 August 1988 Amend 5 to PGE-1025, Environ Qualification Program Manual ML20151D1061988-04-0808 April 1988 Rev 1 to Procedure PGE-1048, Inservice Testing Program for Pumps & Valves,Second 10-Yr Interval ML20235U8041987-09-30030 September 1987 Amend 1 to PGE-1043, Accident Monitoring Instrumentation Review ML20236J4451987-08-31031 August 1987 Amend 4 to Environ Qualification Program Manual for Trojan Nuclear Plant ML20235U8711987-08-28028 August 1987 Radiological Emergency Plan 1987 Annual Exercise ML20236N7821987-07-30030 July 1987 PGE-1025, Environ Qualification Program Manual ML20214A0661986-11-14014 November 1986 PGE-1049, Trojan Nuclear Plant Inservice Insp Program for First 10-Yr Interval 860520-960519 ML20212L2811986-10-0707 October 1986 Rev 2 to Ndp 600-1, Control of Nonconforming Matls,Parts & Components ML20212P8791986-08-29029 August 1986 Rev 0 to Procedure PGE-1048, Inservice Testing Program for Pumps & Valves Second 10-Yr Interval ML20204F4411986-07-22022 July 1986 Rev 0 to Temporary Plant Test Procedure TPT-175, RCS Thermal Expansion Long-Term Monitoring ML20198R0161986-06-30030 June 1986 Rev 0 to Temporary Plant Test TPT-166, RCS Thermal Expansion Test. Addl Info on Insp of Cast Stainless Steel Hot Leg Elbows Encl ML20212L2571986-06-24024 June 1986 Rev 0 to Nqap 100, Nuclear QA Dept Organization & Responsibilities ML20212L2941986-05-16016 May 1986 Rev 2 to Ndp 600-2, Control of Nonconforming Activities ML20214K6811986-03-31031 March 1986 Safety-Related Motor-Operated Valve Program ML20212L2711986-02-19019 February 1986 Rev 0 to Ndp 300-2, Selection of Procurement Sources ML20137N7701986-01-13013 January 1986 Rev 2 to Administrative Order AO-4-7, Procedure Generation Package for Emergency Operating Procedures ML20055B2751982-06-25025 June 1982 Public Version of Revision 3 to Radiological Emergency Response Plan Implementing Procedure EP-18, Fire Fighting ML20198R0661979-01-19019 January 1979 Amend 3 to Rev 2 to Procedure ISI-205, Manual Ultrasonic Exam of Full Penetration Circumferential & Longitudinal Butt Welds 1999-08-05
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Memphis 11esting Services, inc. -
- er 6 RECORD OF RIVISIONS .
VISUAL EXAMINATION PROCEDURE
_FROCEDURE # SECTION/PARAGRAPE REVISION # DATE ATTECTED PREPARED BY QA APPROVAL
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QTS-VT-100, 08/17/04 N/A T ~ ~ '~ p Rev.0 '.
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. VISUAL: EXAMINATION PROCEDURE 1.0 SCOPE-This procedure describes the requirements for the
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visual examination of welded components such .as listed below:
1.1 Full penetration butt welds
- 1. 2 ' Fillet welds .
'l.3 Welds on welded supports 2.0 REFEREUCES-2.1 American Society of Mechanical Engineers (ASME) '
- Boiler and Pressure vessel Code
' 2.1.1 Section V, Nondestructive Examination, ~
1983 Edition
> 2.1.2 Section XI, Inservice Inspection of Nuclear Power Plant Components, 1983 Edition 2.1.3 QTS-300, Training, Qualification and Certification 3.0 PERSONNEL REQUIREME:iTS Services 3.1 Personnel certified to i Memphia Testine Inc. certification program and meetihg the require-ments of paragraph 3.2 below, shall be deemed qualified.
3.2 Personnel shall receive additional documented training on components representative of those to '
be inspected when required. .
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3.3 Visual examination personnel shall have an annual visual acuity examination to assure natural or corrected near vision acuity sufficient to be able to read 3-1 letters on. standard Jaeger test.
1 t.ype charts for near vision or equivalent methods.
A far distance acui'ty examination such as. Snellen test at 20 feet. Natural or corrected'far distance aculty shall be a snellen fraction of 20/30 as a minimum.
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4.O CLEANING- ,
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4.1 - Visual- examinations that require i: lean surfaces -
for valid interpretation shall be preceded by-appropriate cleaning prpcasses.
4.2 Cleaning processes'are not covered under the pro-cadure.
4.3 In general, satisfactory results may be.obtained when the surface is in the as-welded condition.
4.4 Prior to visual examination the surface and all adjacent areas within at least 1 inch shall be dry and free of dirt, grease, scale, welding flux, weld spattar, oil or other matter that could obscure surface examination.
5.0 EXAMINATION AREAS Examination areas should be the weld under examination and 1/2 inch of each side.
6.0 VISUAL EXAMINATION METHODS 6.1 Direct Visual Examination Direct visual examination may be performed when access is sufficient to place tho' eye within 24 inches of the surface to be examined and at an angle not_less than 30 degrees to the surface to be examined. Mirrors may be used to improve the angle of vision and aids 'such as magnifying lens may be used to assist the examination.
Lighting shall be sufficient to resolve a 1/32 inch line vu a neutral gray card that proceduras an 184 reflectance.
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- l 6.1 Remote Visual Examination Where access does not permit dittect visual examination, .
remota. visual examinations may be performed, pro-vided resolution capability is aquivalent to that obtained by direct visual examination. Visual aids ;
such as mirrors, telescopes, borescopes, fibre '
optics or other suitable instruments may be used..
L 7.0.-EXAMINATION The visual examination shall be perforined to determine
[ the general condition of the weld and adjacent areas.
5.0 RECORDS' 8.1 A visual examination data sheet sha7,1_be prepared
- for all components examined. This shall include the following information as a min:. mums A. Examiner and level B. Datal of examination C. Procedure Number and Revision D. Type.of visual examination (direct / remote)
E. Illumination used.
F. Direct viscal aids if used G. Remote visual equipment H. Identification of Component I. Examination results J. Location and size of any indications 9.0 EVALUATION 9.1 Discontinuities at the surface shall be indicated.
Imperfections such as may occur from machining marks, surface conditions, may produce similar indications which are nonrelevant to the direction of unacceptable discontinuities. -
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9.2 Any indication which is believed to be nonrele-vant shall be regarded as a defect and shall be re-examinedito verify whether or not actual. defects are present.
9.3 Linear indications are those indications in which the length is .more than 3 times the width.- Indi-cations with major dimensions greater than 1/16th inch shall'be considered relevant.
9.4: The fo11osing relevant indications are unacceptable:
. A. lAny cracks or linear. indications B. -Rounded indications with dimensions greater than 3/16th inch.
C. Four or more rounded indications in a line sep& rated.by 1/16th inch or less edge to_ edge.
D. s Ten.or more rounded indications (such that would
' result from porosity on the surface of'the
-weld) in any 6 square inch of surface.-
E. Arc strikes and weld spatter.
10.0 PROCEDURE RESTRICTIONS 10.1 Examinations performed in accordance with this
. procedure will not be considered valid if combi-nations of lighting,. access, and angle of vision is not-adequate to resolve a-fine line of 1/32 inch or less in width, or some other artificial flaw locared on the surface' or stailar surface to that to be examined. The line or artificial flaw shall be placed in the least discernable location on the area examined, to prove the procedure.
11.0 Procedure Requalifications 11.1 Requalifications of this procedure shall be required:
A. For direct visual examinations at distances greater than 24 inches. -
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No. QTS-VT-100 Memphie Tksting Services, Inc.
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B. For direct visual examinations at angles less than 30 degrees to the surface to be examined.
C. The requirements of 10.0 of this procedure are.
not met.
11.1 Substituting one equipment manufacturer's equipment for another, or changes in the details of test arrangement, will not require procedure requali-fication.
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