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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A8301997-03-31031 March 1997 Wppss WNP-2 RPV Surveillance Matls Testing & Analysis. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B1751995-12-31031 December 1995 Reactor Power Uprate Startup Test Rept, for WNP-2. W/951215 Ltr ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. 1999-08-27
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291B1621995-03-0606 March 1995 Rev 9 to Procedure Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii. ML17291A1341994-06-16016 June 1994 Pages 9 & 10 to Rev 11 to PPM 13.12.15,inadvertently Omitted from Original Submittal ML17291A6661994-04-30030 April 1994 WNP-2 Odcm. ML17290A9951993-12-31031 December 1993 Amend 16 to Odcm. ML17290A3771993-05-27027 May 1993 Amend 1 to Inservice Insp Program Plan,First Insp Interval. New Relief Request Will Be Submitted to Define Areas of Limited Exam of RPV nozzle-to-shell Welds ML17272B0141993-04-28028 April 1993 Amend 1 to Vols 1-3 of ISI Program Plan. ML17289B2621993-02-22022 February 1993 Rev 1 to LTI7.4, Operations Liaison Responsibilities. ML17289B1931993-01-31031 January 1993 Offsite Dose Calculation Manual. ML17289A7811992-07-31031 July 1992 Revised Plant Procedures Manual Including Rev 10 to 13.8.2, Backup Emergency Dose Projection Sys Operations & Rev 7 to 13.11.1, Recovery Manager Duties. ML20097H7511992-04-23023 April 1992 Plant Procedure 10.25.89, One Hour - Three Hour Fire Barrier Installation ML17289A5031992-04-0101 April 1992 Washington Nuclear Plant - 2 Licensed Operator Requalification Program Corrective Action Plan Resolution Documentation. ML17286B1791991-11-21021 November 1991 Rev 4 to Pump & Valve Inservice Test Program Plan,WPPSS-2. ML17286A9051991-06-28028 June 1991 Odcm. ML17286A7381991-04-30030 April 1991 Revised Plant Procedures Manual Including,Procedures 13.7.7, 12.7.8,13.8.1 & 13.11.15 ML17286A4971990-12-0505 December 1990 Revised Epips,Including Rev 8 to 13.8.2,Rev 10 to 13.10.9, Rev 8 to 13.11.13,Rev 8 to 13.14.1,Rev 6 to 13.14.3,Rev 10 to 13.14.4 & Rev 7 to 13.14.9 ML17285B0621990-02-26026 February 1990 Amend 7 to Odcm. ML17285B0501990-02-22022 February 1990 Rev 6 to Plant Procedures Manual 13.8.2, Manual Offsite Dose Calculations. W/900222 Ltr ML20066K0451989-03-28028 March 1989 Rev 5 to Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii ML17285A2621988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML17285A2511988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML20090M2951987-11-17017 November 1987 Rev 4 to FATE-84-100, Vipre Code Maint Procedures Manual ML20236N3071987-11-0606 November 1987 Corrected Page 16 of Rev 7 to Procedure 13.14.2, Process for Determining Protective Action Recommendations & Protective Action Decisions ML17279A5931987-10-0808 October 1987 Rev 3b to Pump & Valve Inservice Test Program Plan. ML17284A3901987-06-30030 June 1987 Draft A-3453-87-6, Washington Nuclear Plant 2 Generic PRA- Based Insp Plan. ML17278B1221986-11-17017 November 1986 Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency). ML20215B7551986-07-24024 July 1986 Rev 3 to NDE & I Instruction Qci 6-4, Ultrasonic Exam BWR Nozzle Inner Radius ML20215B7631986-03-20020 March 1986 Rev 3 to NDE & I Instruction Qci 6-13, Ultrasonic Exam of Piping Welds (Manual) ML17278A5681986-01-0606 January 1986 Rev 5 to Emergency Plan Implementing Procedure 13.14.7, Emergency Training. ML17278A5341985-12-20020 December 1985 Rev 3a to Pump & Valve Inservice Test Program Plan. ML17278A4731985-11-0101 November 1985 Revised Emergency Procedures,Including Rev 1 to Procedure 5.0.0, Emergency Procedure General Precautions, Rev 0 to Procedure 5.0.1, Emergency Operating Procedure Flow Chart & Rev 1 to Procedure 5.1.3, Reactor Power Control. ML17278A5491985-09-24024 September 1985 Rev 0 to Procedure Tp 8.6.6, Special Test Procedure for Tdas Class 1E Isolators. ML20133N3611985-09-0909 September 1985 WPPSS-2 Emergency Preparedness Exercise Manual for 850909-13 ML20129B5491985-05-0606 May 1985 Vol 1 of Rev 0 to Inservice Insp Program Plan ML17278A4291985-03-20020 March 1985 Rev 1 to Operating & Engineering Test Procedure 8.2.92, UHS Performance. ML17277B6461985-03-0505 March 1985 Amend 4 to 85-01, Preservice Insp Program Plan, Vols 1-4 ML17277B3101984-02-29029 February 1984 Control Room Design Review Program Plan. ML17277B3091984-02-17017 February 1984 Function & Task Analysis of Emergency Operating Procedures. ML17277B7331983-12-28028 December 1983 Rev 2 to 23A1900AA, RHR Sys. ML17277B0401983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.3.8, Equipment Clearance & Tagging. ML17277B0421983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.5.1, Tech Spec Surveillance Testing Program. ML17277B0361983-11-0707 November 1983 Rev 5 to Administrative Procedure 1.3.1, Standing Orders/ Night Orders. 1999-08-27
[Table view] |
Text
No A WASIIINGTON PVSI IC POWEA SUPPI Y SYSTBM QCI 6-4 Rcv. No.
Effccuvc Date NDE dk I INSTRUCTION 3I20I95
//YES + No ULTRASONIC EXA1VHNATIONFEEDWATER NOZZLE INNER RADII 1.0 P RP E AND P 1.1 This procedure defines the requirements for manual, pulse-echo ultrasonic examination of the feedwater nozzle inner radians, (Zones 1, 2, and 3), ASME Section XI, Category B-D. Scanning by this procedure is done from the reactor vessel O.D. wall and nozzle surfaces using refracted. shear wave search units, Figure 1 illustrates the Zones which can be effectively scanned .from the outside surfaces of the vessel plate and nozzle, 1.2 This procedure covers the angle beam shear wave technique that is unique to the nozzle design. Specific refraction angles have been determined by individual nozzle geometry as depicted in Figures 3a, 3b, 4 and 5.
1.3 This instruction is intended to meet the requirements of Sections V and XI of the ASME Boiler and Pressure Vessel Code (1989, no Addenda).
1.4 BWR Calibration Data listed in Table I have been predetermined from the Supply System's feedwater nozzle mockup so the qualified examiner need only use the vessel 2.D ~S None calibration block representing the shell course containing the nozzle.
3.0 ~EU NT 3.1 Personnel ualifications 3.1.1 Contractor and Supply System personnel performing examinations to the requirements of this instruction shall be certified to at least Level II in ultrasonics in accordance with the requirements of Reference 7.2. Additionally, the examination team shall consist of at least one Level II or Level III in ultrasonics qualified using the Supply System BWR feedwater nozzle mockup and this ultrasonic examination procedure per paragraph 4.3.
CIKClKDBY/DATE r'-C -e~
DEFr.APPROVhL/DA WFM2 Rg j
-./> ~
SUPERSEDES ISSUE: (
Rev. 8,Mated 03/10/93 PAGE I of 21
~.QCVQCI I 9512180151 951208
...PDR FDR 9
ADOCK 05000397
QCI 6-'4 Rev. 9 3.1.2 Personnel not specifically qualified on the BWR feedwater nozzle mockup, but designated as Trainee, Level I, II or III UT may assist a qualified examiner in performance of examinations to this instruction.
3.1.3 At least one person responsible for reviewing the results of the ultrasonic examination shall be a Supply System person certified as an ultrasonic Level III in accordance with Reference 7.2.
3.2 1 ni Instrument 3.2.1 The pulse-echo, ultrasonic flaw detection instruments shall be equipped with a stepped gain control, graduated in units no larger than 2 dB. Examples of instruments considered acceptable for examination are listed below.
Krautkramer USIP-11
- . Krautkramer USL-48 f
6 3.2.2 The pulse repetition rate of the instrument shall be set between 250 Hz and 2000 Hz.
NOTE: Pulse repetition rates are automatically set by the Krautkramer USL-48 depending on the selected sweep range. The Sonic 136 automatically sets pulse rates in the selected sweep range unless changed by the operator in /'epetition the "special" menu.
'.3 Transducers 3.3.1 Single element ceramic transducers, having an area of .44 to 1.0 square inch, with a nominal frequency of 2.25 MHz shall be used with specific wedges as shown in Figure 2. The refracted angle within the material shall be within the limits shown in Table I. Additionally, data may be taken with other transducer sizes, frequencies, wave modes, and angles, after completing the examination to the above requirements.
3.4 ~ale - The maximum length of cable shall be 25'or type RG-174/U with no more than one intermediate connector. The maximum length'of cable for type RG-58 shall be 100'ith no more than 2 intermediate connectors.
3.5 Qgygi~lan - Soundsafe by Sonotech, Ultragel II, glycerin, or a glycerin deionized water mixture may be used as the liquid couplant. Other couplants may be used provided they have been approved by the plant.
36 .~lib 3 l 3 -Tb < rr r rr y\l\
r r
r rl
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I r
rr
- 38. 8 UND BE.4hl GE ME nY INNCc~ E FOR ZCNE 1 FIGURES 3A and 3B Page 12 of 21
t ~ ~
0 QCI 6-4 Rev. 9 SCAN AREA ScCTIONAL VIEW OF NO~ BOOY FiGURE 4 SOUNO BEAM GEOMETRY-ZONE 2 FIGURE S SOUND BEAbA GE Ll~iRY. ZONES SF'ICNAL llEW CF NO@ ' CY':NOE.-.
FIGURES 4 and 5 Page 13 of 21
QCI 6-4 Rev. 9 NOZZLE NUMBER LOCATcO ON TAPE LINES MARKEO ON NO&LE SOOY RADIALLINES EX-,ENO AT LEcAST2 PAST REr CIRCLE 304 3Mc C:RC'=
3CC' 50'ONE >
2P57 X ~
2-I 04 255
.05'en n4 C
/ i
%4 335'BC
- 804 C,CM)
FIGURE 6 NOZZLE MARKING PLAN Page 14 of 21
V QCI 6-4 Rev. 9
'A SUPPLY SYSTEAI ULTRASONIC CALIBRATIONSHEET 2one I Cal fbratfon tRoltcTI NNP-2 SYSTtM RPY SHttT NO.R 503 CXAMINKAI J. Smfth LEVELI II CATER 2 15 95 THEIIMOMKTCR5012 4812 ExAMINtRR A~ 8rown LEYCLI III INSTRUCTION No 2 OCI 6-4 REVI5IOHR 0 RG-1746 NarisoniZP"~~ CASLE TYtE SERIAL MVMSCR UT 120 ~RR ~
t ZIR 2599
' ' ZRZ 16'KNCTH 6.6" .25 Soundsafe 1 H IC KN K 55 SWE tt IN ,zz 9 9 2 TEMtERA'TURK 80 AIN IM 04 ACTUALANCLK 70 SATCH <<o. 20922 CHART RCCOAOCR TYttl N IA VT IHSTRUIICMT TYttl Sonfc 136 34643 IN5TRUMENT CALISRATION tREVIOU5LY tERf CAMEO ON CALISAATIONSHECT NUMSCR SCRCKN HtlCHT LINEARITY SCRECN HCICHT LINEARITY AMtLITUOECONTAOL LIHEAIHTY fOR CONTINUOUS CAIN CONTROL fOR 204 STEI'AIN CONTROL LITVOK X I0 100 10 40 TO 40 40 lo 10 20 ~4 92 0 2 A A Q 10 12 Ii 949 CHANCE ~5 ~ 11 Low 50 45 KS 34 29 25 20 15 HICH 40 4 REAOINC X Low 50 to 31 25 20 15 13 10 8 LIMITSX Lt ~ 1l Sl ~ tt Sett INI'IIALCAL TIMEI SYSTEM CALISAATION flNALCAL TIME>
INSIRIPlKHT SE'TTIHCS Rtf LtCIORS AMtLI 1UO XfSH t SWttt At*CIRC SCIIE CN OAC tRtSENTATION C*LCHKCKS IN INCHES COAASE RANCE NI A 34 NOOK SOZ 17.0 09:39 J.S.
BAILIE OELAY COARSE N(A ft NOOK RANCE SALES 10 lt HOOK OKLAYCALIS 15 ~ 7 lt Moot fRCOUKMcv " 2.25 ft NOOK CAIN IN RAR 72 IS NOOK DAMtlMC IS MOOE REJECT - of f K II I SEARCH UIHT AXIAI R OAIKHTATIOH IK RRRKX N A WCLOSOR tART5KXAMINEO 0 1 2 1 ~ 4 4 10 fvLL5cRcEMSwtct 10" f14 to 2415M.
AKYIKwtosY LEYEL IHR L~ 8l'een CATCI 2) 15 95 RKYIEwto 4YR J ~ Jones OATS 2)IS 95 fl ~ Rll ~ ~
FIGURE 7 Page 15 of 21
~ ~
QCI 6-4 Rev. 9 WASHINGTON PUBLIC POWER SUPPLY SYSTEM ULTRASONIC EXAMINATIONDATA SHEET - NOZZLE INNER RADIUS Rltonl No.I 1RPU-124 tsoIECTI MNP-2 YSTCMI RPY sI oRAIIUIO Ho.5 RPy-JPJ OCELCOESCRIt<<OH5 Reactor Feedkater Nozzle Inner Radius and Nozzle Sore N4-150-1R, N4-150-NB 5IATCRIALTYtCI Carbon Steel OHC NO.5 ONC HO.I 2 OIIC ko.5 3 o.otscAHOIRESTIOHS5 2 each zone iCM and CCM) ATC5 ATCI AIE5 2 15 95 2 15 95 2 15 95 5ksTRUcllok No.5 PC 6 4 EYIEION5 9 IMCSTART5 IME S TARSI 1 P94P JP53 TWE STAR'55 XAMIHCR5 J. 5EIIth CVCLI ll IMC STot5 1050 IMC STot5 1113 IME STot5 1129 A. Srokn CVEL5 111 TCMt5 SP t ART TEMt5 SP ART TCMts SU I. ETAHOARo Ho.I UT HICKNESS5 L EHlll Ho I ISO 5P3 70'RT L CHEST No.5 504 L CHEST Nou 5P5 ACCltTAHCE CRITCRIA5 LEI CLE5 25 LC5 25 IHOICATIOH ~ OIAR AZUIUTH D AMtL IT Vol METAL SCAN HUMSCR RCSCRlNCE ICCH) OISTANCt 5 ESH tATH ICH OR CCNI 45 2.25 1.25 90 14.75 CM 315 3.2 3.05 65 15.04 CCM 2.6 2.2 70 17.8 CCM 85 3.2 3.0 75 17.7 CM I4-30-JR 0 - 360 - No oth recordab e indicati ns-I4-30-NB 0 - 360 - No rec dable ind cations- 2, 3 5IEVIEI5CO SV LEVEL HI5 ATE 5,2 I 15 I 95 EVICWEO SY5 ATC5
~ I~ II I ~
~
FIGURE 8 Page 16 of 21
ZONE I RE~ RENCE CiRCI.ES QCI 6-4 345'5'0 Rev. 9 300'0
~
315>>
270'>>
295>>
255 5>>
05'0>>
35' So>>
65'igure 9A CIRCUMF:-RENTIALAND RADIALSCANNING 40NE 1 PEPERENCE CIRCLES ZCNE 1 REFERENCE A CIRCLES ScbiV SCAN P4 i r.'S Xccr ccinmr W+
PA <.-'.S .c~c Sere Xcc:Bet. y fiYPC L p ri Qkr,'1
~
rI
~
3cre I L i SC4N IN CW AND CCW DIRECTION SCAN IN CW biND CCW DIRECTION j
CIRCUMFEQQJTIA SCAiVNING AC i iCiV (MCVING AZlMUirI5C4N PA ir.'S)
RACIAL SCANNING MOTION (FIXED AZWUTH SCAN P>THS) r 'gt'N 98 Ftgccs C FIGURE 9 SCANNING MOTIONS FOR THE ZONE 1 EXAMINATION Page 17 of 21
QCI 6-4 Rev. 9 0'5'4 ZONE 1 REFERENCE CIRCLE,
~po 90 60'IST iVC" (0)
AZ.'LIUirl(A)
RE.-= %ENCE CIRCL=
NOTF.
AU (A) MEASUREMENTS SHALL BBiIN COUNTER CLOCKWISB DIRECTION FROM NEAREST RADIALUNE.
ALL(D) MEASUREMENTS SHALL BB FROM REFPJtENCB CIRCLE RADIALLYOUTWARD. I
'IGURE 10 MEASUREMENT CRITERIA FOR RECORDING UT Page 18 of 21
v QCI 6-4 Rev. 9 AZ(C A)
Far 0 distance measurerhent See rrgure t2 Mid Radius Scan Width (x3cP~)
acius -nd HC ZZLE CRCSS SGCTlON FIGURE 11 REQUIRED SCAN PATHS AND MEASUREMENT CRITERIA FOR ZONE 2 EXAMINATIONS Page 19 of 21
QCI 6-4 Rev. 9 CIRCUMFERENTIALSCANS SHAI 'E MAOE IN TWO OIRECTICNS AROUNO THE CYLINOR(CALScEC c cON OF THE NO~c FORGING MEASURE '0 QISTANCES FRCM GREAK POINT ON NOZZLe EFORGING (TOP)
SIDE 'llEW CF NC 27C4 ggO I
I ao.
Reference Az lines are each 15'round the nozzle. All Az measurements are made in a counterclockwise direction from these lines to the index mark on the search unit. View made looking toward the vessel.
FIGURE 12 ZONE 3 SCANNING AND LOCATION REQUIREMENTS
'Page 20 of 21
QCI 6-4 Rev. 9 0 15 30 45 315 330 3CO 50 285 270 90 255 05 120 21 19 lo5 1 5 lao Plot of lndlcation(s) for nozzle No.:
Report No.:
Scale 1/4 FIGURE 13 Page 21 of 21
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