ML17309A414
| ML17309A414 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/27/1988 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Stahle C NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML17261A806 | List: |
| References | |
| RTR-REGGD-01.150, RTR-REGGD-1.150 NUDOCS 8901100076 | |
| Download: ML17309A414 (42) | |
Text
SUBJECT:
Forwards info re upcoming 10 yr inservice insp.New inservice insp techniques will be demonstrated on 890110
& 11.
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TITLE: OR Submittal: Inservice Inspection/Testang/Relief from ASME Code D
05000244 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
..4C CE1Z RATED D1PIR1BUTION DEMONSTRATION SYSTEM REGULATORIa{FORMATION DISTRIBUTION S'EM
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ACCESSION NBR:8901100076 DOC.DATE: 88/12/27 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas s Electric Corp.
RECIP.NAME RECIPIENT AFFILiATION STAHLE,C.
Document Control Branch (Document Control Desk)
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/llldFIIIA ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649.0001 December 27, 1988 TKLKPHONK ARKA COOK 7ld 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Carl Stahle PWR Project Directorate No.
1 Washington, D.C.
20555
Subject:
Demonstration of ISI Technique at Southwest Research Institute R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Stahle:
Enclosed is information concerning the upcoming 10-year ISI of the Ginna Reactor Vessel.
This also includes historical information from the 1979 Ginna reactor vessel inspection and the 1986 Point Beach reactor vessel inspection.
The new In-Service Inspection techniques to be employed for the 1989 inspection will be demonstrated at the Southwest Research Institute facilities in San Antonio on January 10 and 11, 1989.
The NRC has expressed interest in this topic, and are invited to this demonstration.
An agenda for January 10 is included.
The 11th will be set aside to discuss any questions arising from the demonstration.
Very truly yours, PDR ADOCK 05000244 Robert C.
M credy 8901l00076 88l227pNU,'"- ', 'eneral Manager
uclear Production GJWN011 Enclosures xc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Robert Winters, Region I Bob Hermann, NRR
January 10, 1989 Enclosure 1
Introduction RG&E>>
John Smith Description ofReactor Vessel Ultrasonic Examination SwRI BillClayton Review ofthe Results ofthe 1979 R.E. Ginna Reactor Vessel Ultrasonic Examination RG&E>>
Mike Saporito Review ofthe Results ofthe 1986 Point Beach Unit 1 Reactor Vessel Ultrasonic Examination WE Jim Kohlwey/Gary Sherwood Discuss Indication Sizing Techniques Used in 1979 R.E. Ginna and 1986 Point Beach Unit 1 Examinations SwRI BillClayton Discussion ofHeavy Wall Sizing Techniques Discussion ofNozzle Flaw Sizing Program 1)
Overview 2)
Mockups 3)
Techniques and Transducers NDEC
~ Frank Ammirato SwRI BillClayton SwRI BillClayton SwRI George Gruber/Glen Light BuffetLunch Demonstration 1)
Presentation ofData Format 2)
Description ofDemonstration SwRI BillClayton SwRI BillClayton 3)
Preselected Flaw, One or More Flaws to be Selected by NRC 4)
Scanning of Selected Flaws 5)
Evaluation ofSelected Flaws Program Results Closing Comments SwRI BillClayton SwRI BillClayton SwRI BillClayton RG&E<
John Smith
nclosure 2
1989 REACTOR VESSEL EXAMINATIONS The 1989 Ginna Station Reactor Vessel Examination will consist of two phases, a visual examination of the internal
- surfaces, nozzles and internal components of the reactor vessel and an ultrasonic examination of the vessel welds.
These examinations will satisfy the requirements of the Ginna Second Interval Inspection
- Plan, ASME Section XX (1974 Edition including Addenda thru Summer 1975) and Regulatory Guide 1.150, Rev.l.
The visual examination will utilize the Benthos Mark II Mini-Rover Submersible Camera System',
which has been used successfully by Surry and Point Beach for reactor vessel examinations.
The examination plan will allow 100% inspection of all the internal
- surfaces, nozzles and internals.
The internal surfaces will be examined by moving the submersible in a vertical motion and then indexing around the vessel circumference until all surfaces have been covered.
The inlet and outlet nozzles will be inspected to the extent feasible by driving the submersible into the nozzle and tilting the TU Camera to view the nozzle ID surface and its weld.
Reactor vessel internals will be examined after they have been removed from the vessel, but while still under water in the reactor t
vessel cavity.
The entire examination will be performed in accordance with written RG&E Visual Inspection Procedures.
The ultrasonic examination will be performed on the reactor vessel welds and nozzle to piping welds from the inside surface utilizing The Southwest Research Institute (SWRI)
Programmed and Remote (PAR) ISI-2 Device and Fast PAR Equipment.
In addition, the
.SWRI Enhanced. Data Acquisition System (EDAS), will be utilized for data collection, correlation and analysis of ultrasonic data.
EDAS provides color graphics and data analysis and presents the data in easy to interpret displays.
The ultrasonic examination will include 1004 examination of all the reactor vessel welds as shown in Attachment 1.
The Ginna examination will include 1004 of the weld length even though the ASME Code requires only 5% of the weld length to be examined.
Ultrasonic transducers will be utilized that satisfy the requirements of Section XI of the ASME Code.
Described in Attachment 2
are the results of the Reactor Vessel Exam performed during the 1979 (end of the first inspection interval) outage.
This exam included both a visual and ultrasonic examination.
The visual exam was performed utilizing cameras mounted on poles and on the PAR device.
The ultrasonic examination was done utilizing the PAR device and the SWRI Standard Data Acquisition System (SDAS).
This examination identified an indication in the "N2B" Inlet Nozzle to Vessel Weld.
This indication was detected from the nozzle bore utilizing the 15 degree angle beam longitudinal wave technique.
Based on beam spread correction the indication was sized as approximately Ac=
.160" X Lc = 4.52", as described in Figure 3 of Attachment 3.
This size indication is allowable per the ASME Code Table IWB-3510.
A Fracture Mechanics Evaluation of the indication was also performed to demonstrate its acceptability and is described in Attachment. 4.
In conjunction with the two previously discussed evaluations, a review of the original fabrication radiographs confirmed the presence of slag at the identified location.
As a result of these evaluations it is believed that this indication is a code allowable thin planar slag inclusion located mid-wall of the vessel to nozzle weld.
During the 1989 examination of the Ginna Reactor Vessel new techniques and technology will be applied to better resolve any indications identified.
To accomplish this the following actions are being taken:
A joint flaw sizing program has been initiated by Wisconsin Electric (WE) and Rochester Gas and Electric
{RGE) utilizing SWRI and EPRI for support.
The purpose of the program is to develop optimized techniques for flaw sizing.
Two full size mockups have been being fabricated; one representative of the inlet/outlet configuration and the other representative of the safety inspection nozzle.
The mockups have built-in defects similar to indications in the RGE/WE nozzles.
Focused Transducers and Time-of-Flight Techniques are
/
being investigated for more accurately sizing indications.
These technologies will be integrated with the Southwest Research Xnstitute EDAS System.
A demonstration has been scheduled for mid-January 1989.
The purpose of the demonstration will be to compare 1979 flaw sizing techniques with the enhanced techniques developed through this program.
Representatives of RG&E and WE will witness this demonstration and representatives of the NRC 'and the, Authorized, Nuclear Insurers will be invited to attend.
More specific information regarding the Nozzle Sizing Program can be found in Attachment, 5.
M.J. Saporito Rev.0 11/28/88
The followingis a listing ofmechanized ultrasonic emminations ofthe reactor pressure vessel welds and adjacent piping wells. These examinations willinclude 1/2T base material for vessel welds and 1/4 inch base material for piping welds. Also shown are the anticipated examination angles and the direction ofthe beam component.
The lower head is forged and has no meridional welds and the shell courses are ring sections with no longitudinal welds. In all cases the goal is to examine 100% ofthe weld plus 1/2T each side ofthe weld. Examination of 100% ofthe weld length is the goal also forthe circumferential vessel welds even though 74/S75 Section XIonly requires 5%. Interference from other vessel components may limitthe desired examination coverage. Ifthis was the case in previous examinations, it has been noted. A complete discussion ofthe individual examination area coverage willbe provided in the Qnal report of" the examinations as required by Regulatory Guide 1.150 Rev. 1.
Mech UT examinations willbe performed on the reactor vessel welds and selected reactor coolant piping welds from the inside surface utilizingthe PaR ISI-2 Device and SwRI Fast PaR equipment. Examination areas include vessel circumferential, nozzle-to-shell, and nozzle piping welds.
The Mech UT examinations ofthe RPV willbe performed in accordance with the requirements ofthe 74/S75 Section XIand Regulatory Guide 1.150, Rev. 1.
a)
RPV Shell and Head Welds 1) 0-degree longitudinal wave (UTOL) emminations willbe performed for detection of laminar reflectors which might acct interpretation ofangle-beam results.
2) 0-degree longitudinal wave (UTOW) examinations willalso be performed for detection of reflectors in the weld and base material.
3) 45-degree and 60-degree shear wave (UT45 and UT60) examinations willbe performed for detection ofreflectors in the weld and base material oriented parallel to the weld.
4) 45-degree and 60-degree transverse shear wave (UT45T and UT60T) examinations willbe performed for detection ofreflectors in the weld and base material oriented transverse to the weld.
5)
In the case ofthe RPV, welds, SwRI 50/70 tandem search units willbe used to examine to a depth ofapproximately 2.25 inches for detection ofreflectors in the clad-to-base metal interface area and also'in the volume between the examination surface and the depth ofthe first Code calibration reflector.
These dual-element tandem search units develop an interactive beam with longitudinal wave propagation and produce an examination with significantly improved signal-to-noise ratio over conventional near-surface techniques.
ATTACHMENT SCOPE OF ULTRASONIC EXAMINATIONS OF THE REACTOR PRESSURE VESSEL WELDS
i b)
RPV Nozzle Areas The inlet, outlet, and safety injection nozzle-to-vessel welds willbe examined from the bore utilizing 15-degree (forinlet nozzles), 10 degree (for outlet nozzles) 10-degree (for safety injection nozzle) and 45-degree beams for detection ofreflectors in the weld and base material. In addition, UT45T and UT60T examinations willbe performed from the shell inside surface for detection ofreflectors oriented transverse to the weld and base material. These transverse examinations willutilize a computer to control the X-Y-Zmovements ofthe PaR device to assure accurate positioning around the nozzle during examinations.
50/70 tandem search units willbe utilized from the bore and shell inside surfaces for detection ofreflectors located in the clad-to-base metal interface region and also the volume between the examination surface end the first Code calibration reflector forthe purpose ofsatisfying the requirements in Section XI.
c)
Piping Welds Nozzle Pi in Welds
'or the inlet safe end-to-nozzle welds, a UTOLscan willbe used for detection ofreflectors which might aQ'ect interpretation ofthe angle-beam results. UT45 and UT 60 s'cans willbe used for detection of reflectors parallel to the weld from both sides ofthe weld. AUT45T scan willbe used for detection of reflectors oriented transverse to the weld. The acoustic properties ofthe inlet elbows preclude lamination from the elbow side; therefore, a UTOW scan willbe performed in addition to the scans identified above..
Limitations are expected around the vessel support lugs, safety injection and inlet nozzles due to the proximityofthese components.
Other limitations are listed.
I.
Circumferential welds Estimated time - (2.5 shifts)
Ring forging-to-lower head weld (RPV-E)
Examination area 0- 360 0- 360 Angle 0,45,60,50/70 0,45T,60T,50/70T Beam Component up/dn av/ccw Lower shell-to-ring forging weld (RPV-D)
Examination area 0- 360 0-360 Angle',45,60,50/70 0,45T,60T,50/70T Beam Component up/dn cw/ccw Limitations due to proximityof core support lugsI 0 from (344.20
- 15.90) CG-1 90 from (74.20 - 105.80) CG-2 180 from (164.20 - 195.80) CG-3 270 from (255.25
- 284.75) CG-4 Intermediate shell-to-lower shell weld (RPV-C)
Examination area 0- 360 0- 360 Angle 0,45,60,50/70 0,45T,60T,50/70T Beam Component up/dn cw/cd
D.
Upper shell-to-intermediate shell weld (RPV-B)
Examination area 0- 360 0- 360 Angle 0,45,60,50/70 0,45T,60T,50/70T Beam Component up/dn cw/ccw II.
Upper shell region area (A)
A.
Flange-to-upper shell weld (RPV-A) from shell Estimated time - (3.0 Shifts)
Examination area 0- 360 0- 360 Angle 0,45,60,50/70 0,45T,60T,50/70T Beam Component up cw/ccw B.
Outlet nozzle-to-shell welds (N1A), (N1B) from sheH Emmination area nozzle (0 - 860)
Angle 0,45T,GOT,50/70T Beam Component nv/cnv C.
Inlet nozzle-to-shell welds (N2A), (N2B) from shell Examination area nozzle (0 - 860)
Angle 0,45T,GOT,50/70T Beam Component cw/ccw D.
Safety injection nozzle-to-shell weld (AC-1002), (AC-1003) from shell Examination area
~
nozzle (0 - 860)
Angle 0,45T,GOT,50/70T Beam Component cw/cnv III.
Upper shell region area (B)
A.
Flange-to-upper shell weld (RPV-A) from seal surface Estimated Time - (1.5 shifts)
Examination area 0- 360 B.
Vessel support lugs Examination area Vessel support (RPV-VSL-1)
Vessel support (RPV-VSL-1)
Vessel support (RPV-VSL-2)
Vessel support (RPV-VSL-2)
Angle 18, 11,4 Angle 0,45,60,50/70 0,45T,60T,50/70T 0,45,60,50/70 0,45T,60T,50/70T Beam Component dn Beam Component up/dn cw/ccw up/dn cw/ccw
IV.
Nozzle inner radius, integral extention and nozzle bore Estimated time - (3.5 shifts)
A.
Outlet nozzle inner radius section integral extension region and nozzle bore.
Examination area Outlet A (N1A-IHS)
Outlet B (NlB-IRS),
Outlet A (NlA-IE)
'utlet B (N1B-IE)
Inlet nozzle inside radius region Examination area Inlet A (N2A-IRS)
Inlet B (N2B-IRS)
Angle 10,45,50/70 10,45,50/70 50/70 50/70 Angle 50/70 50/70 Beam Component To Vessel C/L cw/ccw To Vessel C/L cw/ccw To Vessel C/L To Vessel C/L Beam Component cw/cv,v cw/ccw C.
Nozzle-to-shell welds from nozzle bore Examination area Inlet A (N2A)
Inlet B (N2B)
Angle 15,45,50/70 15,45,50/'70 Beam Component To Vessel C/L cw/ccw To Vessel C/L cw/ccw D.
E.
Safety injection inside radius region and nozzle bore Examination area Angle Safety injection A(AC-1003-IHS) 0,10 Safety injection B(AC-1002-IHS) 0,10 Safety injection nozzle integral mtension Examination area Angle Safety injection A(AC-1003-IE) 70 Safety injection B(AC-1002-IE) 70 Beam Component To Vessel C/L To Vessel C/L Beam Component cw cw V.
Nozzle-to-piping welds Elbow-to inlet nozzle welds Examination area Inlet A (PL-PW-V)
Inlet B (PL-FiV-VII)
InletA (PL-FW-V)
Inlet B (PL-FW-VII)
InletA (PL-FW-V)
Inlet B (PL-FW-VII)
Angle 0,45,60 0,45,60 45RLT 45RLT 45RL 45RL Estimated Time - (3.5 Shifts)
Beam Component Away from Vessel C/L Awayfrom Vessel C/L cw/cnv cw/cd To Vessel C/L To Vessel C/L
B.
Nozzle-to piping welds Examination area Outlet A (PL-FW-II)
Outlet A (PL-FW-Il)
Outlet B (PL-FW-IV)
Outlet B (PL-FW-IV)
C.
Safe end-to-nozzle welds Examination area Safety injection A(AC-1003-1)
Safety injection A(AC-1003-1)
Safety injection B(AC-1002-1)
Safety irjection B(AC-1002-1)
D.
Piping-to-safe end welds Examination area Safety injection A(AC-1003-2)
Safety injection A(AC-1003-2)
Safety injection B(AC-1002-2)
Safety injection B(AC-1002-2)
Angle 0,45,60,45T,60 0,45,60,45T,GO 0,45,60,45T,60 0,45,60,45T,60 Angle 0,45>45T,60 0,45,45T,60 0,45,45T,60 0,45,45T,60 Angle 0,45,45T,60 0,45,45T,60 0,45,45T,60 0,45,45T,60 Beam Component Awayfrom Vessel C/L To Vessel C/L Awayfrom Vessel C/L To Vessel C/L Beam Component Awayfrom Vessel C/L To Vessel C/L Away from Vessel C/L To Vessel C/L Beam Component Awayfrom Vessel C/L To Vessel C/L Away from Vessel C/L To Vessel C/L A1-5
SCHEDULE OF HECHANIZED EXAMINATIONS FOR R ~
E ~ GINNA RPV Days On xaeination Areas Circunferential Maids RPV-E,-D,-C,-B Day 1
Day 2 Day 3 Day 4 1
2 i
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Day 5 2
I=====I=====
Day 6 I
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<==Vessel 1
2
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===I===I Upper Shell Region Area Maids (A)
RPV A NIAL NIBS H2A, N28, AC-1002, 5 AC-1003 Upper Shell Region Area Molds (8)
RPV-VSL1) RPV-VSL2I 5 RPV-A AC-1002 Piping Melds Elbow to Inlet Hozzle A
PL-FM-V 8
PL-FM-VII Outlet Nozzle to Pipe A
PL-FM-II 8
PL-FM.IV SI Safe End to Nozzle A
AC-1003-1 8
AC-1002-1 SI Pipe to Safe End A
AC-1003-2 8
AC-1002-2 Nozzle Inside Radius Sections and Integral Extension Outlet A (H1A-IRS,-IE)
Outlet 8 (N18-IRS,-IE)
Inlet A (N2A-IRS)
Inlet 8 (H28-IRS)
Safety Injection AC-1003-IRS I - I E
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ATTACHMENT 2 RESULTS OF 1979 REACTOR VESSEL EXAMINATIONS
ATTACHMENT2 INTRODUCTION The 1979 ISI ofthe R.E. Ginna Reactor Pressure Vessel (RPV) and associated nozzle piping welds was performed in accordance with Section XIofthe American Society ofMechanical Engineers Boiler and Pressure Vessel Code, 1974 Edition withAddenda through Summer 1975.
The SwRI Data Acquisition System (now referred to as the Standard Data Acquisition System or SDAS) was used for recording and processing ofultrasonic test information obtained during mechanized examinations.
This system included Sonic MarkIIultrasonic instruments.
These instruments were also used forthickness gauging and as an aid in determining the acoustic characteristics and attenuation ofthe materials. Various brands, sizes and frequencies of ultrasonic transducers were used to perform the examinations.
In general, information obtained from the examinations was processed by the SwRI Data Acquisition System in the followingmanner.
Signal information from each ofthe ultrasonic instruments was displayed on the analog cathode ray tube (CRT) for each instrument.
Amplitude and time analog information was channeled through electronic gates and examined
.according to preselected levels.:For the signals which exceeded these levels, calibrated voltages were generated which were analogous to the signal amplitude and the sound beam distance to the reflector. The time analog and amplitude analog voltages corresponded to the firsttriggering signal encountered along the sound beam and the signal with the largest amplitude, respectively.
These data were combined with location information and sent to a six-channel strip chart recorder and an analog tape recorder. The SwRI Data Acquisition System handled information from three ultrasonic instruments simultaneously.
This versatile system produced the followingtypes ofexamination records forthis ISI:
Video Tape Strip Chart Analog Tape The PaR Examination Device, fabricated by Programmed and Remote Systems Corporation, with technical design input from SwRI, was used to perform ultrasonic examinations ofthe RPV welds, components, or areas.
The system was utilized during this ISI for lamination from the interior of the nozzles and from the vessel inside surface.,The device was mounted on the top flange ofthe vessel by three legs which clamped to the guide studs for accurate reproducible positioning. Attached to the boom assembly were various SwRI accessories which enabled examination ofthe nozzle-to-shell welds, nozzle-to-safe end welds, the nozzle high-strain areas, the vessel shell-to-flange weld, the vessel circumferential welds, and the vessel support welds.
A2-I
Page 2 The results ofthe 1979 mechanized examinations ofthe R.E. Ginna RPV were put into four categories:
The term "No Recordable" was applied when no indications were observed greater than the recording level and no indications were observed between 50 percent ofthe Distance
'Amplitude Correction (DAC)'curve and the recording level.
"Insignificant"was applied when (1) the amplitude ofany indication observed was equal to or greater than the recording level, but less than 100 percent ofthe DAC curve, and not resolved as being relevant, or (2) nonrelevant indications, such as refiections due to standing waves, water multiples, etc., were observed.
"Geometric" indications were (1) those indications which had an amplitude equal to or greater than 100 percent ofthe DAC curve, and were resolved and documented to be geometric in nature, or (2) indications that are less than 100 percent ofthe DAC curve but were suspected by the Level IIexaminers to be other than geometric in nature, and were then resolved and documented to be geometric in nature.
"Other" ihdications include those indications evaluated to be other than "Insignificant" or "Geometric" indications, as described above.
A2-2
SUMMARY
OF RESULTS The followingTable list all MECH UT indications; Insignificant, Geometric and Other, along withthe type ofsearch unit used, and how the indications were resolved.
Examination Area Circumferential Welds
~Insi iTicant Geometric Other Resolution RPV-3 Upper Shell to Intermediate Shell RPV-C Intermediate Shell to Lower Shell 45o 45o Water Multiple Redirected Shear due to Clad No recordable Indications RPV-D Lower Shell to Ring Forging OOL Oow 45o T 60o T 45'ater Multiple
'ater Multiple Water Multiple Water Multiple Redirected Shear V-ZRing Forging to Lower ead o'L onw 45o T 60o T 45'o'ater Multiple Water Multiple Water Multiple Water Multiple Redirected Shear to Outside Surface (OD)
Redirected Shear to OD RPV-A Vessel to Flange, o'L onW 45o 45o 4oRL}
11oRL}
18 RL}
Water Multiple Water Multiple Water Multiple Redirected Shear to OD
}Vessel OD Between Stud Holes Vessel Su orts VSL-1 VSI 2 No Recordable Indications No Recordable Indications
Page 2
. amination Area Loo B Outlet Nozzle N-1B
~insi ificsnt Geometric Other Resolution Nozzle to Vessel 45o 15o 60oT Water Multiple Water Multiple, Integral Extension OD Geometry
'Water Multiple Nozzle Inside Radius and Integral Extension Safe End to Nozzle 60oT Water Multiple No Recordable Indications Loo B Inlet Nozzle N2B Nozzle to Vessel OoL 45o 45oT 15'RL 15oRL Water Multiple Water Multiple Water Multiple Water Multiple Slag like indications at 310 (A)
Nozzle Inside Radius SW Surface Irregularities (B)
Safe End to Nozzle OoL OoW 45o 45oT Water Multiple Water Multiple Water Multiple Water Multiple Denotes Appendix containing resolution information forthat indication.
A2-4
Page 3 amination Area ansi ificant Geometric Other Resolution Loo A Outlet Nozzle NlA Nozzle to Vessel 1SoRL 4SO Water Multiple, Integral Pension Water Multiple, Inte'gral Extension 4SoT 60oT 4So lsoRL Code Allowable (C)
Code AHowable (D)
Water Multiple OD Geometry Nozzle Inside Radius and Integral Extension Nozzle to Safe End 60'T Water Multiple No Recordable Indications Loo AInlet Nozzle N2A
. ozzie to Vessel Nozzle Inside Radius Safe End to Nozzle 4So 1S'RL 4so OoL ooW 4So 4SoT SW Water Multiple Water Multiple Surface Irregularities (E)
Water Multiple Water Multiple Water Multiple Water Multiple Water Multiple Denotes Appendix containing resolution information forthat indication.
AZ-5
Page 4
< xamination Area Loo B Safe In ection Nozzle
~AC-1002 Nozzle to Vessel Nozzle Inside Radius Safe End to Nozzle
~Insi ifiean<
45'oL 4s's'T 60'eometric Other 4So 60'0 10o onL 10o RL Resolution Water Multiple OD Surface Redirected Shear to OD Integral Extension Integral Extension Metallurgical Conditions (F)
Metallurgical Conditions (F)
No Recordable Indications Water Multiple Water Multiple Water Multiple Water Multiple oo A Safe In ection ozzie
~AC-10M Nozzle to Vessel Nozzle Inside Radius Safe End to Nozzle 0'.
0oW 45'or, 10oRL OoL 4s's'0o 45oT OoL 10o RL Water Multiple Water Multiple Water Multiple Outside Surface Integral Extension, Metallurgical Conditions (F)
Integral Extension Water Multiple, OD Surface Water Multiple Water Multiple Water Multiple Water Multiple Water Multiple Denotes Appendix containing resolution information for that indication.
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ATTACHMENT 3 ULTRASONIC EVALUATION OF INLET NOZZLE INSERVICE INSPECTION INDICATION