ML17309A414

Forwards Info Re Upcoming 10 Yr Inservice Insp of Facility Reactor Vessel.New Inservice Insp Techniques Will Be Demonstrated at Swri on 890110 & 11.Demonstration Agenda Also Encl

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: ML17261A805 ML17261A813 ML17261A814 ML17309A414 ML17309A416 ML17309A417
References
RTR-REGGD-01.150, RTR-REGGD-1.150 NUDOCS 8901100076
Download: ML17309A414 (42)

Text

..4C CE1Z RATED D1PIR1BUTION DEMONSTRATION SYSTEM REGULATORIa{FORMATION DISTRIBUTION S'EM {RIDE)

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)

SUBJECT:

Forwards info re upcoming 10 yr inservice insp.New inservice insp techniques will be demonstrated on 890110 & 11.

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR i ENCL ( SIZE:

TITLE: OR Submittal: Inservice Inspection/Testang/Relief from ASME C ode D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 0 PD1-3 PD 5 5 STAHLE,C 1 1 INTERNAL: AEOD/DSP/TPAB 1 1 ARM/DAF/LFMB 1 0 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NUD BSTRACT 1 1 OGC/HDS2 1 0 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: EGGG ROCKHOLD,H 1 1 LPDR 1 1 NL 007 HEMMING 1 1 NRC PDR 1 1 NSIC 1 1 h

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//dt's//gfli 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, 8901l00076 88l227 Robert C. credy PDR ADOCK pNU,'"- ',

05000244 ,,

'eneral M

Manager Production

uclear 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 of Reactor Vessel Ultrasonic Examination - SwRI Bill Clayton Review of the Results of the 1979 R.E. Ginna RG&E>> Mike Saporito Reactor Vessel Ultrasonic Examination Review of the Results of the 1986 Point Beach WE Jim Kohlwey/Gary Sherwood Unit 1 Reactor Vessel Ultrasonic Examination Discuss Indication Sizing Techniques Used SwRI Bill Clayton in 1979 R.E. Ginna and 1986 Point Beach Unit 1 Examinations Discussion of Heavy Wall Sizing Techniques NDEC ~

Frank Ammirato Discussion of Nozzle Flaw Sizing Program

1) Overview SwRI Bill Clayton

2) Mockups SwRI Bill Clayton

3) Techniques and Transducers SwRI George Gruber/Glen Light Buffet Lunch Demonstration

1) Presentation of Data Format SwRI Bill Clayton

2) Description of Demonstration SwRI Bill Clayton

3) Preselected Flaw, One or More Flaws to be Selected by NRC

4) Scanning of Selected Flaws SwRI Bill Clayton

5) Evaluation of Selected Flaws SwRI Bill Clayton Program Results SwRI Bill Clayton Closing Comments 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 following is a listing of mechanized ultrasonic emminations of the 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 of the 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% of the weld plus 1/2T each side of the weld. Examination of 100% of the weld length is the goal also for the circumferential vessel welds even though 74/S75 Section XI only 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 of the 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 utilizing the 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 of the RPV willbe performed in accordance with the requirements of the 74/S75 Section XI and Regulatory Guide 1.150, Rev. 1.

a) RPV Shell and Head Welds

1) 0-degree longitudinal wave (UTOL) emminations will be performed for detection of laminar reflectors which might acct interpretation of angle-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 of reflectors 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 of reflectors in the weld and base material oriented transverse to the weld.

5) In the case of the RPV, welds, SwRI 50/70 tandem search units willbe used to examine to a depth of approximately 2.25 inches for detection of reflectors in the clad-to-base metal interface area and also'in the volume between the examination surface and the depth of the 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

b) RPV Nozzle Areas i The inlet, outlet, and safety injection nozzle-to-vessel welds willbe examined from the bore utilizing 15-degree (for inlet nozzles), 10 degree (for outlet nozzles) 10-degree (for safety injection nozzle) and 45-degree beams for detection of reflectors in the weld and base material. In addition, UT45T and UT60T examinations willbe performed from the shell inside surface for detection of reflectors oriented transverse to the weld and base material. These transverse examinations willutilize a computer to control the X-Y-Z movements of the 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 of reflectors located in the clad-to-base metal interface region and also the volume between the examination surface end the first Code calibration reflector for the purpose of satisfying the requirements in Section XI.

c) Piping Welds Nozzle Pi in Welds

'or the inlet safe end-to-nozzle welds, a UTOL scan willbe used for detection of reflectors which might aQ'ect interpretation of the angle-beam results. UT45 and UT 60 s'cans willbe used for detection of reflectors parallel to the weld from both sides of the weld. A UT45T scan willbe used for detection of reflectors oriented transverse to the weld. The acoustic properties of the 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 proximity of these components. Other limitations are listed.

I. Circumferential welds Estimated time - (2.5 shifts)

Ring forging-to-lower head weld (RPV-E)

Examination area Angle Beam Component 0- 360 0,45,60,50/70 up/dn 0- 360 0,45T,60T,50/70T av/ccw Lower shell-to-ring forging weld (RPV-D)

Examination area Beam Component 0- 360 Angle',45,60,50/70 up/dn 0-360 0,45T,60T,50/70T cw/ccw Limitations due to proximity of core support lugs 0 from (344.20 - 15.90) CG-1 I

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 Angle Beam Component 0- 360 0,45,60,50/70 up/dn 0- 360 0,45T,60T,50/70T cw/cd

D. Upper shell-to-intermediate shell weld (RPV-B)

Examination area Angle Beam Component 0- 360 0,45,60,50/70 up/dn 0- 360 0,45T,60T,50/70T cw/ccw II. Upper shell region area (A) Estimated time - (3.0 Shifts)

A. Flange-to-upper shell weld (RPV-A) from shell Examination area Angle Beam Component 0- 360 0,45,60,50/70 up 0- 360 0,45T,60T,50/70T cw/ccw B. Outlet nozzle-to-shell welds (N1A), (N1B) from sheH Emmination area Angle Beam Component nozzle (0 - 860) 0,45T,GOT,50/70T nv/cnv C. Inlet nozzle-to-shell welds (N2A), (N2B) from shell Examination area Angle Beam Component nozzle (0 - 860) 0,45T,GOT,50/70T cw/ccw D. Safety injection nozzle-to-shell weld (AC-1002), (AC-1003) from shell Examination area ~

Angle Beam Component nozzle (0 - 860) 0,45T,GOT,50/70T cw/cnv III. Upper shell region area (B) Estimated Time - (1.5 shifts)

A. Flange-to-upper shell weld (RPV-A) from seal surface Examination area Angle Beam Component 0- 360 18, 11,4 dn B. Vessel support lugs Examination area Angle Beam Component Vessel support (RPV-VSL-1) 0,45,60,50/70 up/dn Vessel support (RPV-VSL-1) 0,45T,60T,50/70T cw/ccw Vessel support (RPV-VSL-2) 0,45,60,50/70 up/dn Vessel support (RPV-VSL-2) 0,45T,60T,50/70T 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 Angle Beam Component Outlet A (N1A-IHS) 10,45,50/70 To Vessel C/L cw/ccw Outlet B (NlB-IRS), 10,45,50/70 To Vessel C/L cw/ccw Outlet A (NlA-IE) 50/70 To Vessel C/L

'utlet B (N1B-IE) 50/70 To Vessel C/L Inlet nozzle inside radius region Examination area Angle Beam Component Inlet A (N2A-IRS) 50/70 cw/cv,v Inlet B (N2B-IRS) 50/70 cw/ccw C. Nozzle-to-shell welds from nozzle bore Examination area Angle Beam Component Inlet A (N2A) 15,45,50/70 To Vessel C/L cw/ccw Inlet B (N2B) 15,45,50/'70 To Vessel C/L cw/ccw D. Safety injection inside radius region and nozzle bore Examination area Angle Beam Component Safety injection A(AC-1003-IHS) 0,10 To Vessel C/L Safety injection B(AC-1002-IHS) 0,10 To Vessel C/L E. Safety injection nozzle integral mtension Examination area Angle Beam Component Safety injection A(AC-1003-IE) 70 cw Safety injection B(AC-1002-IE) 70 cw V. Nozzle-to-piping welds Estimated Time - (3.5 Shifts)

Elbow-to inlet nozzle welds Examination area Angle Beam Component Inlet A (PL-PW-V) 0,45,60 Away from Vessel C/L Inlet B (PL-FiV-VII) 0,45,60 Away from Vessel C/L Inlet A (PL-FW-V) 45RLT cw/cnv Inlet B (PL-FW-VII) 45RLT cw/cd Inlet A (PL-FW-V) 45RL To Vessel C/L Inlet B (PL-FW-VII) 45RL To Vessel C/L

B. Nozzle-to piping welds Examination area Angle Beam Component Outlet A (PL-FW-II) 0,45,60,45T,60 Away from Vessel C/L Outlet A (PL-FW-Il) 0,45,60,45T,GO To Vessel C/L Outlet B (PL-FW-IV) 0,45,60,45T,60 Away from Vessel C/L Outlet B (PL-FW-IV) 0,45,60,45T,60 To Vessel C/L C. Safe end-to-nozzle welds Examination area Angle Beam Component Safety injection A(AC-1003-1) 0,45>45T,60 Away from Vessel C/L Safety injection A(AC-1003-1) 0,45,45T,60 To Vessel C/L Safety injection B(AC-1002-1) 0,45,45T,60 Away from Vessel C/L Safety irjection B(AC-1002-1) 0,45,45T,60 To Vessel C/L D. Piping-to-safe end welds Examination area Angle Beam Component Safety injection A(AC-1003-2) 0,45,45T,60 Away from Vessel C/L Safety injection A(AC-1003-2) 0,45,45T,60 To Vessel C/L Safety injection B(AC-1002-2) 0,45,45T,60 Away from Vessel C/L Safety injection B(AC-1002-2) 0,45,45T,60 To Vessel C/L A1-5

SCHEDULE OF HECHANIZED EXAMINATIONS FOR R ~ E ~ GINNA RPV Days On Day 1 Day 2 Day 3 Day 4 Day 5 Day 6 Day 7 <==Vessel xaeination Areas 2 2 1

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RPV-VSL1) RPV-VSL2I 5 RPV-A 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- I RS I - I E AC-1002 -IRSI-IE Piping Melds

>-------------------X 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

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ATTACHMENT 2 RESULTS OF 1979 REACTOR VESSEL EXAMINATIONS

ATTACHMENT2 INTRODUCTION The 1979 ISI of the R.E. Ginna Reactor Pressure Vessel (RPV) and associated nozzle piping welds was performed in accordance with Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1974 Edition with Addenda 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 of ultrasonic test information obtained during mechanized examinations. This system included Sonic Mark II ultrasonic instruments. These instruments were also used for thickness gauging and as an aid in determining the acoustic characteristics and attenuation of the 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 following manner. Signal information from each of the 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 first triggering 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 following types of examination records for this 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 of the 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 of the 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 of the 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 of the 1979 mechanized examinations of the 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 of the Distance

'Amplitude Correction (DAC) 'curve and the recording level.

"Insignificant" was applied when (1) the amplitude of any indication observed was equal to or greater than the recording level, but less than 100 percent of the 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 of the DAC curve, and were resolved and documented to be geometric in nature, or (2) indications that are less than 100 percent of the DAC curve but were suspected by the Level II examiners 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 following Table list all MECH UT indications; Insignificant, Geometric and Other, along with the type of search unit used, and how the indications were resolved.

Examination Area ~Insi iTicant Geometric Other Resolution Circumferential Welds RPV-3 Upper Shell to 45o Water Multiple Intermediate Shell 45o Redirected Shear due to Clad RPV-C Intermediate Shell to No recordable Indications Lower Shell 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-Z Ring Forging to Lower o'L Multiple ead onw Water Multiple 45o T Water Multiple 60o T 45'o'ater Water Multiple Redirected Shear to Outside Surface (OD)

Redirected Shear to OD RPV-A Vessel to Flange, o'L Water Multiple onW Water Multiple 45o Water Multiple 45o Redirected Shear to OD 4oRL} }Vessel OD Between Stud 11oRL} Holes 18 RL}

Vessel Su orts VSL-1 No Recordable Indications VSI 2 No Recordable Indications

Page 2

. amination Area ~insi ificsnt Geometric Other Resolution Loo B Outlet Nozzle N-1B Nozzle to Vessel 45o Water Multiple 15o Water Multiple, Integral Extension OD Geometry 60oT 'Water Multiple Nozzle Inside Radius and 60oT Water Multiple Integral Extension Safe End to Nozzle No Recordable Indications Loo B Inlet Nozzle N2B Nozzle to Vessel OoL Water Multiple 45o Water Multiple 45oT Water Multiple 15'RL Water Multiple 15oRL Slag like indications at 310 (A)

Nozzle Inside Radius SW Surface Irregularities (B)

Safe End to Nozzle OoL Water Multiple OoW Water Multiple 45o Water Multiple 45oT Water Multiple Denotes Appendix containing resolution information for that indication.

A2-4

Page 3 amination Area ansi ificant Geometric Other Resolution Loo A Outlet Nozzle NlA Nozzle to Vessel 1SoRL Water Multiple, Integral Pension Water Multiple, Inte'gral 4SO Extension Code Allowable (C) 4So Code AHowable (D) lsoRL Water Multiple 4SoT OD Geometry 60oT Nozzle Inside Radius and 60'T Water Multiple Integral Extension Nozzle to Safe End No Recordable Indications Loo A Inlet Nozzle N2A

. ozzie to Vessel 4So Water Multiple 1S'RL Water Multiple Nozzle Inside Radius SW Surface Irregularities (E)

Safe End to Nozzle 4so Water Multiple OoL ooW Water Multiple 4So Water Multiple 4SoT Water Multiple Water Multiple Denotes Appendix containing resolution information for that indication.

AZ-5

Page 4 xamination Area ~Insi ifiean< Other Resolution Loo B Safe In ection Nozzle

~AC-1002 Nozzle to Vessel 60'eometric Water Multiple 4So OD Surface 60'0 Redirected Shear to OD Integral Extension 45'oL 10o Integral Extension onL Metallurgical Conditions (F) 10o RL Metallurgical Conditions (F)

Nozzle Inside Radius No Recordable Indications Safe End to Nozzle Water Multiple 4s's'T Water Multiple Water Multiple Water Multiple oo A Safe In ection ozzie

~AC-10M 0'. Water Multiple Nozzle to Vessel 0oW Water Multiple Water Multiple 45oT Outside Surface OoL Integral Extension, Metallurgical 45'or, Conditions (F) 10o RL Integral Extension Nozzle Inside Radius Water Multiple, OD Surface 10oRL Water Multiple Safe End to Nozzle OoL Water Multiple Water Multiple 4s's'0o 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