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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C6321999-09-30030 September 1999 Proposed Tech Specs 3/4.17.B, Control Room Emergency Filtration Sys, Eliminating Unnecessary in-place Testing of HEPA & Activated Charcoal Filters Based on Sys Operating Time ML20211G0391999-02-10010 February 1999 Revised ODCM, Including Revs to Revised ODCM Index,Odcm 01.01 Page 2 Paragraph 1,ODCM 02.01 Page 2 Section 1.0,ODCM 05.01 Page 2 Sections 1.0,2.0 & 3.0 & ODCM 13.05 Page 2 ML20203B3191999-01-28028 January 1999 Proposed Tech Specs Page 60d,incorporating Approved Amend 103 Changes for Use by NRC in Issuing SER ML20206P1331998-12-31031 December 1998 Proposed Tech Specs,Revising pressure-temp Limit Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4,deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR for SLCS ML20154L9551998-10-12012 October 1998 Proposed Tech Specs Re Rev of Statement on Normal Shift Length & Other Misc Changes ML20154L9041998-10-0909 October 1998 Proposed Tech Specs,Incorporating Proposed Changes Re Surveillance Test Interval/Aot Extension Program ML20153F0191998-09-25025 September 1998 Proposed Tech Specs Pages Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20237E9771998-08-20020 August 1998 Rev 4 to EWI-09.04.01, Inservice Testing Program ML20236P5421998-07-0101 July 1998 Proposed Tech Specs Pages 30,50 & 53 Containing Administrative Changes Re Power Rerate Program ML20249C5121998-06-19019 June 1998 Proposed Tech Specs Pages Re Rev 2 to 960726 LAR to License DPR-22,to Establish TS Requirements That Are Consistent W/Analysis Inputs Used for Evaluation of Radiological Consequences of MSLB Accident ML20247K6341998-05-12012 May 1998 Proposed Reprinted Tech Specs Bases Pages,Containing Spelling & Grammatical Corrections ML20216D0021998-03-19019 March 1998 Proposed Tech Specs,Providing Consistent Wording Throughout TS & Providing Sound Basis for Frequency of Actions Required Each Shift ML20248L2001998-03-13013 March 1998 Proposed Tech Specs Revising SLMCPR B210059, Rev 1 to GE-NE-B2100594-1, Radiological Analyses of Design Basis Accidents1998-03-0909 March 1998 Rev 1 to GE-NE-B2100594-1, Radiological Analyses of Design Basis Accidents ML20248L4101998-03-0606 March 1998 Revised Page 39 to Proposed TS Change ML20202H7061997-12-0404 December 1997 Proposed Tech Specs Increasing Plant Max Power Level from 1670 Mwt to 1775 Mwt ML20203A9771997-11-25025 November 1997 Proposed Tech Specs Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20199H5281997-11-0606 November 1997 Software Requirement Specification (SRS) ERDS-SRS-1-3, Process Computer Sys - Emergency Response Data Sys (ERDS) - Data Point Library ML20211J9801997-09-29029 September 1997 Proposed Tech Specs Page 249b & Cleaned Typed Page 249b, Adding Footnote to Topical Rept NEDE-24011-P-A Stating That Topical Rept Is Approved for Cycle 18 Only ML20210Q2971997-08-21021 August 1997 Proposed Tech Specs Re Safety Limit Min Critical Power Ratio ML20141B9181997-06-19019 June 1997 Proposed Tech Specs Re Update of Design Basis Accident Containment Temp & Pressure Response ML20137W2201997-04-11011 April 1997 Proposed Tech Specs 3.6.C Re Coolant Chemistry & TS 3/4.17B Re Control Room Emergency Filtration Sys ML20137B5081997-03-12012 March 1997 Rev 2 to Inservice Insp Exam Plan ML20149M7281997-01-23023 January 1997 Proposed Tech Specs 3.5/4.5.C of TS Bases Describing Min RHR & RHRSW Pump Requirements for Post Accident Containment Heat Removal & Submit Update to Design Basis Accident Containment Temp & Pressure Response ML20132C6531996-11-25025 November 1996 Proposed Tech Specs,Sections 2.1.A Re SLMCPR & 3.11.C Re Olmcpr.Changes Revise SLMCPR Values & Deletes Sentence Re OLMCPR Limit Penalty for Single Recirculation Loop Operation ML20117A1551996-08-15015 August 1996 Proposed Tech Specs Re Revision to TS Administrative Controls Section 6.1.F.1 Stating That Either 8 or 12 H Shifts Will Be Considered Normal & 40 H Will Be Considered Nominal ML20116G8951996-07-26026 July 1996 Proposed Tech Specs Increasing Max Power Level by 6.3% to 1,775 from 1,670 Mwt.Summary of Plant Mods for Power Rerate Implementation & Power Rerate Environ Evaluation Encl ML20116D8361996-07-26026 July 1996 Proposed TS Sections 3.6.C & 3/4.17.B Re Reactor Coolant Equivalent Radioiodine Concentration & CR Habitability ML20115D8621996-06-28028 June 1996 Rev 3 to Engineering Work Instruction (Ewi) EWI-09.04.01, Inservice Testing Program ML20100Q3861996-03-0101 March 1996 Proposed Tech Specs Re Periodic Replacement of Containment Purge & Vent Valve Seat Seal ML20095J4341995-12-20020 December 1995 Proposed Tech Specs Re Main Steam Isolation & App J Leak Rate Test Requirements ML20095E7121995-12-11011 December 1995 Proposed Tech Specs,Removing TS SR 4.7.D.4 & Replaces Seat Seals for Drywell & Suppression Chamber Purge & Vent Valves Every Five Yrs ML20094M1981995-11-14014 November 1995 Proposed Tech Specs,Incorporating Requirements of Option B, Section Iii.A for Type a Testing (Primary Containment ILRT) ML20100M4821995-08-29029 August 1995 Revised Sections to Odcm,Including Rev 1 to ODCM-03.01,Rev 1 to ODCM-12.05 & Rev 1 to ODCM-13.05.5 ML20091K6821995-08-18018 August 1995 Proposed Tech Specs Section 3.7/4.7 SGTS ML20087J4251995-08-15015 August 1995 Proposed Tech Specs,Revising Max Individual MSIV Leak Rate Acceptance Criteria of 11.5 Scfh to Overall Criteria That Encompasses Four Main Steam Lines Into One Limit of 46 Scfh ML20086D8011995-07-0505 July 1995 Proposed Tech Specs Extending Surveillance Test Intervals & Allowable out-of-svc Times for Selected Instrumentation ML20085N0991995-06-22022 June 1995 Proposed Tech Specs Supporting Implementation of BWR Thermal Hydraulic Stability Solution ML20083Q8411995-05-18018 May 1995 Rewrite of Rev 2 to Engineering Work Instruction (Ewi) EWI-09.04.01, Inservice Testing Program ML20082N8711995-04-20020 April 1995 Proposed Tech Specs Re SBGTS & Secondary Containment ML20077S4551995-01-0909 January 1995 Startup Physics Testing Rept,Cycle 17 ML20069J1061994-06-0808 June 1994 Proposed TS Re SGTS & Secondary Containment ML20072P8011994-05-17017 May 1994 Rev 8 to Process Control Program, Installed Atcor Solidification Sys ML20065B6691994-03-28028 March 1994 Proposed Tech Specs Re Approved Analytical Methods for Developing Core Operating Limits Rept ML20065B6991994-03-28028 March 1994 Proposed Tech Specs Re Standby Gas Treatment Sys Initiation Instumentation ML20072P8101994-02-22022 February 1994 Offsite Dose Calculation Manual, Rev 0 ML20063C9941994-01-26026 January 1994 Proposed Tech Specs,Requiring Valves to Be Tested at Pressure Greater than or Equal to Calculated Peak Containment Internal Pressure Re Design Basis LOCA ML20062N8731994-01-0404 January 1994 Proposed Tech Specs 3.11, Reactor Fuel Assemblies & Bases Re Methodology for MCPR ML20059E6041994-01-0303 January 1994 Proposed Tech Specs,Revising Surveillance Requirement 4.6.E.1.a to Require Valves to Be Tested Per Section XI Inservice Testing Requirements of ASME Boiler & Pressure Vessel Code ML1132102881993-11-30030 November 1993 Proposed Tech Specs Re Removal of Chlorine Detection Requirements & Changes to Control Room Ventilation Sys Requirements 1999-09-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211G0391999-02-10010 February 1999 Revised ODCM, Including Revs to Revised ODCM Index,Odcm 01.01 Page 2 Paragraph 1,ODCM 02.01 Page 2 Section 1.0,ODCM 05.01 Page 2 Sections 1.0,2.0 & 3.0 & ODCM 13.05 Page 2 ML20237E9771998-08-20020 August 1998 Rev 4 to EWI-09.04.01, Inservice Testing Program ML20199H5281997-11-0606 November 1997 Software Requirement Specification (SRS) ERDS-SRS-1-3, Process Computer Sys - Emergency Response Data Sys (ERDS) - Data Point Library ML20137B5081997-03-12012 March 1997 Rev 2 to Inservice Insp Exam Plan ML20115D8621996-06-28028 June 1996 Rev 3 to Engineering Work Instruction (Ewi) EWI-09.04.01, Inservice Testing Program ML20100M4821995-08-29029 August 1995 Revised Sections to Odcm,Including Rev 1 to ODCM-03.01,Rev 1 to ODCM-12.05 & Rev 1 to ODCM-13.05.5 ML20083Q8411995-05-18018 May 1995 Rewrite of Rev 2 to Engineering Work Instruction (Ewi) EWI-09.04.01, Inservice Testing Program ML20072P8011994-05-17017 May 1994 Rev 8 to Process Control Program, Installed Atcor Solidification Sys ML20072P8101994-02-22022 February 1994 Offsite Dose Calculation Manual, Rev 0 ML20127P2321993-01-19019 January 1993 Revised Software Requirement Specification (SRS) ERDS-SRS-2-B, Emergency Response Data Sys (ERDS) Data Point Library ML20101Q3131992-04-21021 April 1992 Software Spec ERDS-SRS-1.00-1, ERDS Data Point Library ML20090C5071991-08-0202 August 1991 Rev 8 to Section 4.0 of PCP Manual, Dewatering of Resin & Other Filter Media ML20077C9221991-05-30030 May 1991 Rev 0 to TS Interpretation Manual, TS Interpretation 3.5.E.1 & 2-1 ML1131905021990-02-23023 February 1990 Rev 7 to Monticello Nuclear Generating Plant Odcm. ML20245L3661989-07-26026 July 1989 Plant,Emergency Plan Exercise,Section Ii:Exercise Objectives & Guidelines ML20237J7921987-07-31031 July 1987 Rev 8 to ASME Code Section XI Inservice Insp & Testing Program Manual,Second 10-Yr Insp Interval 810630- 920530 ML20207Q4661987-01-0101 January 1987 Rev 20 to Corporate Nuclear Emergency Plan Implementing Procedure, Table of Contents Record of Rev ML20203L3951986-04-18018 April 1986 Rev 6 to ASME Code Section XI Inservice Insp & Testing Program,Second 10-Yr Insp Interval 810630-920530 ML20095L2331984-02-29029 February 1984 Revised Radiation Environ Monitoring Plan ML20079P5761983-12-21021 December 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP 1.1.11 Re Accident Assessment,Epip 1.2.1 Re Emergency Plan Training & EPIP 1.2.2 Re Exercises & Drills ML20081A8161983-09-28028 September 1983 Public Version of Revised Emergency Plan Implementing Procedures A.2-101 Re Classification of emergencies,A.2-105 Re General Emergency & A.2-702 Re Response to Emergency at Prairie Island ML20077G6731983-07-29029 July 1983 Program for Recirculation Piping Replacement at Monticello Nuclear Generating Plant ML20077C1931983-05-20020 May 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP 1.1.1 Re Corporate Emergency Response Plan,Epip 1.1.2 Re Notifications & EPIP 1.1.3 Re Public Info.Rev 12 to Table of Contents Encl ML20072K6591983-02-22022 February 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures A.2-001 Re Emergency organization,A.2-101 Re Classification of Emergencies & A.2-108 Re Access Control During Emergencies ML20072C8491983-02-17017 February 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP 1.1.10 Re Offsite Surveys,Epip 1.1.11 Re Accident Assessment & EPIP 1.1.14 Re Vendor & Consultant Svcs ML20071D9051983-02-0202 February 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures A.2-406 Re Offsite Dose Projection & A.2-422 Re Stack Iodine/Particulate Sampling & Analysis ML20028F7001983-01-20020 January 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP 1.1.5 Re Startup Operation of Emergency Offsite Facility & EPIP 1.1.6 Re Emergency Organization Shift Turnover ML20028F7011983-01-0606 January 1983 Public Version of Revised Emergency Response Plan Implementing Procedures,Including Procedures A.2-420 Re Containment Atmosphere Radiochemical Analysis & A.2-404 Re Airborne Iodine Sampling & Analysis ML20028D4361982-12-22022 December 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures A.2-001 Re Emergency organization,A.2-107 Re Activation of Operational Support Ctr & A.2-402 Re Contamination Control ML20064E9421982-12-0707 December 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP 1.1.2 Re Notifications & EPIP 1.1.4 Re Emergency Organization Records & Forms ML20027D2671982-10-0808 October 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP 1.1.1 Re Corporate Emergency Response Organization,Epip 1.1.2 Re Notifications & EPIP 1.1.3 Re Public Info ML20064M1091982-08-11011 August 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP 1.1.2 Re Notifications & EPIP 1.1.5 Re Startup & Operation of Emergency Operations Facility ML20063N4701982-08-0505 August 1982 Public Version of Revised Emergency Response Plan Implementing Procedures,Including Procedures A.2-001 Re Emergency organization,A.2-302 Re Assembly Point Activation & A.2-303 Re Search & Rescue ML20063H7891982-07-0101 July 1982 Public Version of Revision 3 to Emergency Plan Implementing Procedure A.2-101, Classification of Emergencies. Revised List of Current Pages Encl ML20052G9251982-05-12012 May 1982 to Inservice Insp & Testing Program. ML20040B2591982-01-18018 January 1982 Inservice Insp & Testing Program,Second Ten-Yr Insp Interval,810630-910629. ML20039G6901981-12-0707 December 1981 Public Version of Revision 1 to Emergency Plan Implementing Procedure A.2-001, Emergency Organization. ML20040A7801981-12-0303 December 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 1.1.2 Re Notifications, 1.1.4 Re Emergency Organization & Records & 1.1.5 Re Startup & Operation of Emergency Offsite Facility ML20040A8691981-11-19019 November 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures A.2-102 Re Notification of Unusual event,A.2-103 Re Alert & A.2-104 Re Site Area Emergency ML19350D1001981-03-27027 March 1981 ASME Code Section XI Inservice Insp & Testing Program,Second 10-yr Insp interval,810630-910629 ML1129906921981-03-27027 March 1981 to ASME Code Section XI Inservice Insp & Testing Program & Info Required for NRC Review of Requests for Relief from ASME Code Section XI Requirements ML19207B8711979-08-30030 August 1979 Rept NSP-37-005,Revision 1, IE Bulletin 79-14, Safety-Related Piping Sys Insp Plan,Monticello Nuclear Generating Plant. ML19225D0031979-07-27027 July 1979 of ASME Code Section XI Inservice Insp & Testing Program & Info Required for NRC Review of Requests for Relief from ASME Code Section XI Requirements. ML20090L6781975-01-10010 January 1975 Rev 4 to Special Process Std NUT-NC-3, Procedure for Automatic Recording of Ultrasonic Test Data ML20090L6701975-01-10010 January 1975 Rev 4 to Special Process Std NUT-NC-1E, Nuclear Ultrasonic Weld Exam Calibr Procedure ML20090L6621975-01-0101 January 1975 Rev 4 to Special Process Std NUT-NC-1A, Nuclear Ultrasonic Testing Procedure Ultrasonic Insp of Welds,In 1/4 to 2-1/2 Thickness Range ML20128D2131974-04-11011 April 1974 Operator Requalification Program Prairie Island & Monticello Nuclear Generating Plants 1999-02-10
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Text
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\ vs NUT-NC-3 SPECIAL PROCESS STANDARD , .n. h
.. ... . .,. .it u , cri c o.vi Procedure for Automatic Recording of T. O. Lambert 1/9/75 January 10, 1975 ae movie v oint e.s Ultrasonic Test Data h 7[ 1 or 1.0 SCOPE 1.1 This document covers the requirements and procedures to be used when automatically :'ecording ultrasonic test data on analog charts.
2.0 SPECIFICATIONS 2.1 This specification is to be used in conjunction with the following Nuclear Services Corporatien Special Process Standards.
2.1.1 NUT-NC-1A, Nuclear Ultrasenic Testing Procedure Ultrasonic Inspection of Welds.
2.1.2 NUT-NC-1B, Nuclear Ultrasonic Testing Procedure for Longitudinal Wave Inspection.
2.1.3 NUT-NC-lC, Ultrasonic Exanination of the Inner Radius of Pressure Vessel Nozzle Welds.
2.1.4 NUT-NC-lE, Nuclear Ultrasonic Weld Examination Calibration Procedure. ,
2.1.5 NtTI-NC-7, Nuclear Ultrasonic Examination of Reactor Pressure Vessel Butt and Nozzle Welds.
2.1.6 SNT-TC-1A, Qualification t.nd Certification of. Non-destructive Testing Persor.nel, Supplement C.
2.1 7 NUT-PQ-1, Nuclear Services Corporatien Personnel Qualification Procedure.
2.1.3 ASME B. & P.V. Code,Section XI, Inservice Inspection of Nuclear Eeactor Power Plant Components (Summer 197k).
2.1 9 ASME B. & P.V Oode Section V, Nondestructive Examination (Summer 197h).
3.0 PERSONNEL QUGIFICATIONS
! 31. All personnel performing ultrasonic inspections shall be qualified in accordance with Code accepted standards and procedures as either Level I (Operator), Level II (Inspector), or Level III (Examiner),
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NUT-NC-3, Rev. h SPECIAL PROCESS STANDARD ,
2 or 6 31 (continued) as defined in SNT 'IC-1A, Supplement C and NUT-PQ-1, Rev. O.
Only a Level II Inspector or Level III Examiner shall make judgment as to the acceptance or rejection of indications.
The Nuclear Services Corporation Level III Examiner vill submit to the Purchaser, upon request, a copy of personnel qualification and ultrasonic procedure. Personnel shall, at the request of the Purchaser, demonstrate their knowledge and understanding of pertinent specifications and procedures, and their ability to satisfactorily operate all required equipment prior to performing an ultrasonic $nspection.
33.1 Certification of personnel to NUT-PQ-1 requirements shall be directed by the authorined Level III Examiner.
32 Certifiestion of Personnel 3.2.1 Certification of personnel shall conform to SNT-TC-1A, Supplement C and Nuclear Services Corporation Persormel Qualification Procedure NUT-PQ-1.
3 2.2 In order to obtain certification of any level, the candidate must decenstrate to the Level III Ext. miner's satisfaction a thorough knowled6e of the procedures and requirements contained in ^,his document.
33 Visus.1 Acuity Requirebents l
l Visur.1 requirements for near distance acuity and color shall confcrm to SNT-TC-1A, Supplement C and Nuclear Services Corpora-tion Personnel Qualification Procedure, NUT-PQ-1.
l i
j 3.h Records l
3.h.1 Records of personnel certifications shall be maintained by the Nuclear Services Corporation Level III Examiner at the Campbell office and at the job site. These records i shall conform to SNT 'IC-1A, Supplement C and Nuclear i Services Personnel Qualification Procedure, NUT-PQ-1.
l 3.h.2 Records of instrumentation calibration shall be maintained by the Nuclear Services Corporation Level III Examiner at the Campbell office and at the job site.
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NUT-NC-3, Rev. h SPECIAL PROCESS STANDARD .
,a 3 or 8 h.0 INSPECTION METHODS b.1 The inspection methods which may be used with this recording procedure are ultrasonic pulse echo, and through transmission.
The ultrasonic energy may be transmitted in either the longi-tudinal or shear wave mode.
50 RECORDING METHODS
, 51 The ultrasonic test data concerning indication range sad I amplitude are (shown in Figure 1) recorded on duel trace analog recording charts. Addition 11 information or test paraneters vill be written on the : hart using the stamped form i shown in Figure 2. Any further information such as transducer i position or direction run shall be hand written on the chart by the technician serving as data recorder.
J 6.0 EQUIPMENT 6.1 The ultrasonic examination shall be performed using a NORTEC i 130D or equivalent ultrasonic tester meeting the requirements of ASTM E-16h and certified to be calibrated according to ASTM E-317 The tester produces an analog output proportional to metal path and a second proportional to amplitude. The instrument also provides digital readout.
f 6.2 The analog signals generated by the tester shall be recorded usin6 a strip chart pen recorder certified to be electronically j calibrated within the past 90 days. A typical recorder for thic
' purpose is the Brush 220.
I 6.3 An ir.tercom system connecting the examiners at the recorder and I the f. ester shall be used where necessary for clear communicatior..
Battery povered, line connected phone systems are considered adequate for this purpose.
70 CALIBRATIO'j, i
i 71 For vessel examinations the ultrasonic tester shall be calibrated to meet the requirements of the ASME Boiler and pressure Vessel Code Sections V and XI, Summer 197h Addenda, and the resulting responses shall be recorded on a calibration record chart.
7 1.1 Amplitude and range readings taken from the digital display of the tester shall be recorded on the calibration chart.
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NUT-NC-3, Rev, h
.m i SPECIAL PROCESS STANDARD h or 8 I-4 8.0 RECORDING OF EXA)CNATION DATA l 8.1 Before the performance of an examination the following data i
shall be recorded on the recording chart using the form stamp j of Figure 2 as a guide.
- 1) Inspector Names 7) Transducer Size 1
j 2) Weld No. & Configuration 8) Test Frequency t.
- 3) Type 9) Transducer Angle l
b) Pipe Size & Schedule 10) Chart Speed *
- 5) Scan No. & Type 11) Sensitivity of Recorder i 6) Report No. 12) Scanning Sensitivity i
8.2 Before and after the performance of an examination, the stability l reference shall be scanned and the resulting trace becomes a 1 permanent part of the examination record.
8.3 The veld shall be scanned in a systematic manner, generally
- beginning at a dead center position which shall be noted as i 1200. As the scanning proceeds the 0300, 0600, and 0900 positions shall be noted on the chart record.
1 e
8.3 1 The orientation data essential to indicatien locaticn i shall be noted on the Inspection Report.-
8.h Detailed evaluation of an indication should be noted on the i
recorder chart and amplitude, metal path, and signal with i measurements taken from the digital meter recorded in
- . apprapriate locations on the chart.
t l 90 RECORDkNGCONVENTIONS l 91 The left hand ch' art section of the dual trace chart shall be connected to record signal amplitude with positive amplitudes l causing left pen deflection. A full scale deflection on this
! chart shall correspond to a full reale (100%) signal amplitude on the ultrasonic tester.
92 The right section of the dual trace chart shall be used to record metal path (range) with increasing range causing left pen deflections. A full scale deflection on this chart shall l .
correspond to a full range (100% of sucep) display on the l
ultrascnic tester screen.
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10.1 The chart record shall be attached to an ultrasonic report form l.
4 and technique sheet to constitute the permanent incpection record (HSC-TS-003-6/Th), which shall be signed by the examiner l
and his assistant. When requested, all rejectable indications vill be shown on a drawing of the joint.
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- 11.0 QUALITY ASSURANCE
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- 11.1 Inspection reords shall be maintained in a field file in such j
condition as to be readily available for audit.
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11.2 It shall be the responsibility of the Nuclear Services Corporatien
- Level III Examiner to enforce the requirements of this procedure.
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Page 8 of 8 RECORD OF REVIGTONS NUT-NC-3 1
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a b 1/10/75 Revised to meet 197h Code 3 8/20/Th Revised 2 3/1/7h Revined 1 7/1/73 Revised 0 7/27/71 Issued for Comments NO. DATE REVISION BY NSC-TS-010-7-71
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