ML17213A703

Mechanized Preservice Exam of Selected Components of St Lucie Plant,Unit 2.

ML17213A703
Person / Time
Site:	Saint Lucie
Issue date:	07/31/1982
From:	SOUTHWEST RESEARCH INSTITUTE
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ML17213A704	List: ML17213A703 ML17301A010
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NUDOCS 8211150459
Download: ML17213A703 (159)

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SOUTHWEST RESEARCH INSTITUTE Post Office Drawer 28510 6220 Culebra Road San Antonio, Texas 78284 MECHANIZED PRESERVICE EXAMINATION OF SELECTED COMPONENTS OF THE ST. LUCIE PLANT, UNIT2 VOLUME I FINAL REPORT WITH APPENDICES SwRI Project 6831 Prepared for Florida Power and Light Company 9250 W. Flagler Street Miami, Florida 33174 July 1S82 Prepared by Approved by Wayne T. Flach Director Reviewed and pproved by: Department of Engineering Services Quality Assurance Systems and Engineering Division T. Carr FPL PNS aff FPL PNS Staff 82111504'21110 05000389 PDR ADQCK Section Supervisor i, 8 PDR

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INTRODUCTION LPLEMENTATION OF REGULATORY GUIDE 1.150 "ULTRASONIC TESTING OF REACTOR VESSEL MELDS DURING PRESERVICE AND INSERVICE EXAMINATIONS"

INTRODUCTION I

Implementation of Regulatory Guide 1.150, "Ultrasonic Testing of Reactor. Vessel Welds During Preservice and Inservice Examinations"

.1. Introduction The reactor vessel examinations performed at St. Lucie Plant, Unit 2, were performed in accordance with, the 1977 Edition of Section XI with Addenda through Summer 1978 (77S78) and Regulatory Guide 1.150 to the extent practicable. This Introduction is intended to summarize the impact of Regulatory G'uide 1.150 and the methods by which Southwest Research Institute (SwRI) implemented its requirements.

The examination of the St. Lucie Plant, Unit 2, reactor vessel commenced on January 28, 1982. The planning. activities associated with these examina-tions were based upon the requirements as set forth in the Regulatory Guide and prior implementation at Florida Power and Light's (FPL) Turkey Point Plant, Unit 3. Due to the nature of the Regulatory Guide, several areas required fur-ther clarification in order to assure that its intended requirements could be implemented. As a consequence, this provided the basis'or the comments in-cluded in Section 3. of this Introduction relative to the St. Lucie Plant, Unit 2.

2. Im lementation of Re ulator Guide.1.150 As A lied to St. Lucie Plant, Unit 2 The following is a transcript of .Regulatory Guide 1.150 with SwRI com-ments inserted. These comments represent, SwRI's position i.n addressing the intent of the Regulatory'Guide as the Institute has interpreted the require-ments and, in some cases,'ur proposed method of'erforming examinations in compliance with the Regulatory Guide. These comments'are made relative to the Regulatory Position portion of'the Regulatory Guide only, as SwRI under-stands that this is the portion to which the NRC will audit for compliance.

C. REGULATORY POSITION Ultrasonic examination of reactor vessel welds should be performed according to the requirements of Section XI of'he ASME BGPV Code, as referenced in the Safety Analysis Report (SAR) and its amend-ments, supplemented by the following:

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INSTRUMENT PERFORMANCE 'CHECKS The checks described in paragraphs 1.2 through 1.5 should be made for any UT system used for the recording and sizing of reflectors in accordance with regulatory posi-tion 6 and for reflectors that exceed the Code-allowable criteria.

Frequency of Checks As a minimum, these checks should be verified within 1 day before and within 1 day after examining all the welds that need to be examined in a reactor pressure vessel during one outage. Pulse shape and noise suppression controls should remain at the same setting during examination and calibration.

1.2 Screen Height Linearity Screen height linearity of the ultrasonic instrument should be determined according to the mandatory Appendix I to Article 4,Section V of the ASME Code, within the time limits specified in regulatory posi-tion 1.1.

1.3 Amplitude Control Linearity Amplitude control linearity should be determined according to the mandatory Appendix II of Article 4,Section V of the ASME Code, 1977 edition, within the time limits specified in regulatory position 1.1.

1.4 Frequency-Amplitude Curve A photographic record of the frequency-amplitude curve should be obtained. This record should be available for comparison at the inspection site for the next two successive inspections of the same volume. The reflector used in generating the frequency-amplitude curves as well as the electronic system (i.e., the basic ultrasonic instrument, gating, form of gated signal, and spectrum analysis equipment) and how it is used to capture the frequency-amplitude information should be documented.

SwRI believes that it is inappropriate to photographically document a frequency-amplitude curve of a sample situation. The frequency spectrum analysis of,a waveform provides only a record of the relative frequencies in a signal produced from a particular situation. Also,'he equipment needed to provide the frequency spectrum analysis is relatively delicate laboratory-type equipment which is not amenable to field use.

is in use, whichever is less) or each time any component (e.g., transducer, cable, connector, pulser, or receiver) in the examination system is changed.

SwRI agrees with the intent of the above requirement, and it has long been our standard operating practice to conduct calibration verification checks .more frequently than required by the Regulatory Guide. During the examinations at St. Lucie 2, it was SwRI practice to completely check cali" bration of the mechanized ultrasonic instruments (FTS MK II) a maximum of every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the manual ultrasonic instruments (FTS MK I) a maximum of every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. During mechanized examinations, this check coincided with the shift change so that operators from both shifts had an oppor-tunity to observe the calibration and repeat their own calibration tech-niques. This procedure has proved to be a significant aid in maintaining consistent instrument sensitivity while minimizing the effect of different operators during long examinations.

Additionally, in accordance with the procedures used at St. Lucie 2, if a calibration could not be verified to within the plus or minus 2 dB toler-ance, all examinations since the last qualified calibration were'erformed over. Under these circumstances, it was unwise to extend mechanized calibration checks for a period greater than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. It was also SwRI practice to check all points on the DAC curve during each calibration veri-fication. When a mechanized examination did not last for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the calibration was performed and verified at the end of each particular exami-nation setup. SwRI also complied with the requirement that calibration be verified each time that there was a change in any component of, the exami-nation system, i.e., transducer, cable, instrument pulser, etc.

Where possible, the same calibration block should be used for successive inservice examinations of the same RPV. The calibration side drilled holes in the basic calibration block and the block sur-faces should be protected so that their characteris-tics do not change during storage. These side holes or the block surface should not be modifed in any way (e.g., by polishing) between successive exam-inations. If the block surface or the calibration reflector holes have been polished by any chemical or mechanical means, this fact should be recorded.

SwRI agrees with the intent of the above requirement. All cali-bration blocks used during the St. Lucie 2 RPV examination are the property of FPL and are subject to these requirements.

Establishment of a correction factor was not necessary, as all data utilized for Code sizing and analysis of unidentified reflectors was obtained in the same direction as used during calibration. Mhen per-forming examinations for the purposes of detecting reflectors orientated transverse to the weld, scanning was performed in a circumferential mode (perpendicular to the orientation of transverse indications ) In this case, calibration and examination were performed in the same direction.

c. For mechanized scanning, signals should not be maximized during the establishment of the DAC curve.

This statement is ambiguous by implying that signals should not be maximized during the calibration. Such a practice is simply inconsistent with normal, reasonable operating procedures. It is SwRI's interpretation that the intent of this requirement was to maintain the direction of the sound beam to be essentially perpendicular to the cali-bration block's side-drilled hole. SwRI standard practice precludes skewing of the search unit toward the intersection of the side-drilled hole and the side of the block.

d. One of the following alternative guidelines should be followed for establishing the DAC curve:

The DAC curve should be established using a moving transducer mounted on the mechanism that will be used for examination of the component.

(2) Correction factors between dynamic and static response should be established using full-scale mockups.

The above statement is essentially the mechanism SwRI used in order to preclude some of the other requirements. SwRI conducted a comparison of the response between dynamic and static conditions on a full-scale mockup.

Iri this comparison, a calibration block was used that accurately repre-sented the full section of a reactor pressure vessel wall. It was shown that a correction factor was inappropriate and that the results were considered to be consistent. Therefore, a correction factor of "1" was used and calibrations were performed statically. Scanning of the welds was performed in a direction parallel to the weld, except when taking flaw sizing data.

(3) Correction factors should be established using models and taking scaling factors into consideration (assumed scaling rela-tionship should'e verified).

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0 Code, 1980 edition, a correction factor should be used to adjust the DAC level to compensate for the larger reflector holes. Also, if the reactor pressure vessel has been previously examined by using a conventional block, a ratio between the DAC curves obtained from the two blocks should be noted (for reference) with the significant indications data.

3 ~ NEAR-SURFACE EXA"fINATION AND SURFACE RESOLUTION The capability to effectively detect defects near the front and back surfaces of the actual component should be estimated. The results should be reported with the report of abnormal degradation of reactor pressure boundary in accordance with the recommendation of regulatory position 2 '(3) of Regulatory Guide 1.16. In determining this capability, the effect of the following factors should also be considered:

a ~ If an electronic gate is used, the time of start and stop of the control points of the electronic gate should be related to the'olume of material near each surface that is not being examined-

b. The decay time, in terms of metal path distance, of the initial pulse and of the pulse reflections at the front and back surface should be considered.

C ~ The disturbance created by the clad-weld-metal interface with the parent metal at the front or the back surface should be related to the volume of material near the interface that is not being examined.

d~ The disturbance created by front and back metal surface roughness should be related to the volume of material near each surface that is not being examined.

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veld/parent-metal interface unless it can be demonstrated that unfavorably oriented planar flaws can be detected by the UT technique being used. Otherwise, use of alternative volumetric NDE techniques, as permitted by the ASME Code, should be considered. Alter-native NDE techniques may be considered to include high-intensity radiography or tandem-probe ultrasonic examination of the weld-metal interface.

The .requirement to examine the weld/parent metal interface with' sound beam that essentially intersects the fusion zone at +15 degrees was an impossibility for the majority of the vessel circumferential welds.

Due to the weld orientation as depicted in the vessel drawings and the geometry of the vessel shell, exception was taken to this requirements Vessel welds that were geometrically accessible were examined in accor-dance with the requirements. These areas were the vessel-to-flange and nozzle-to-shell welds. The vessel-to-flange weld was examined from the seal surface with sound beams essentially directed perpendicular to the weld. For nozzle-to-shell welds, the requirement was fulfilled by performing examinations from the nozzle bore.

The use of alternate volumetric NDE techniques was considered; however, under the circumstances involved, alternate techniques were impractical and essentially impossible due to accessibility and geometric conditions.

Furthermore, SwRI's experience has shown that the standard 45-and 60-degree search unit angles as required by the ASME Code are very successful in detecting flaws within the weld area.

6. SIZING Indications from geometric sources need not be recorded-6.1 Traveling Indications Indications that travel on the horizontal baseline of the scope for a distance greater than indica-tions from the calibration holes (at 20 percent DAC amplitude) should be recorded. Indications that travel should be recorded and sized at"

'20 percent DAC. Where the indication is sized at 20 percent DAC, this size may be corrected by subtracting for the beam width in the through-thickness direction obtained from the calibra-tion hole (between 20 percent DAC points) that is at a depth similar to the flaw depth. If the indication exceeds 50 percent DAC, the size should be recorded by measuring the distance between

This paragraph reduced the amplitude level to which data were recorded from 20 to 10 percent. SwRI complied with this requirement in as far as practicable with the exception of those areas where the signal-to-noise level prevented identification of low amplitude signals. SwRI contends that the 10 percent of DAC data is of debatable value in determining flaw size.

7. REPORTING OF RESULTS Records obtained while following the recommendations of regulatory positions 1, 2, 3, 5, and 6y along with discussions and explanations, if any, should be kept available at the site for examination by tPe NRC staff. If the size of an indication, as determined in regulatory positions 6.1 or 6.2, equals or exceeds the allowable limits of Section XI of the ASHE Code, the indications should be reported as abnormal degradation of reactor pressure boundary in accordance with the recommendation of regulatory position 2.a(3) of Regulatory Guide 1.16.

Along with the report of ultrasonic examination test results, the following information should also be included:

a. The best estimate of the error band in sizing the flaws and the basis for this estimate should be given.

When discussed with the NRC, it was noted that this statement is intended to assure that the examination agency would provide its best estimate of the true size of detected flaws.

b. The best estimates of the portion of the volume required to be examined by the ASlK Code that has not been effectively examined such as volumes of material near each sur-face because of near-field or other effects, volumes near interfaces between cladding and parent metal, volumes shadowed by laminar material defects, volumes shadowed by part geometry, volumes inaccessible to the trans-ducer, volumes affected by electronic gating, and volumes near the surface opposite the transducer.

Examination areas that received limited examination coverage are discussed in detail in Appendix F of this report. As previously cited, there were no limitations associated with the required examination volume as a result of inadequate near-surface resolution except in those areas identified as having physical or geometrical restrictions.

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Ac uisition S stem (See Fi re 3)

Sonic FTS MK II ultrasonic instruments were used for mechanized examinations. Recording of the mechanized data was accomplished by using the SwRI Data Acquisition System (DAS), which simultaneously recorded test data from three separate ultrasonic search units. Gating and positioning circuits were incorporated into the system to provide reflector location and amplitude information. The SwRI DAS is a portable, compact, modular system designed for rapid and accurate recording and/or processing of ultrasonic test information obtained during mechanized examinations.

Information obtained from UT examinations was processed by the SwRI DAS in the following manner. Signal information from each of the UT instruments was displayed on the appropriate 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 relative to the gate positions and lengths for each instrument. The time analog and ampli-tude analog voltages corresponded to the first triggering signal encoun-tered along the sound beam and the signal with the largest amplitude, respectively. These data were combined with location information and transmitted to a six-channel strip-chart recorder and the analog tape recorder.

This system produced the following types of examination records:

Videotape Strip chart Analog tape As a requirement of every examination, the TV videotape record-ing provided- a continuous record of all information displayed on the CRT unit and the analog-to-digital display. Thus, it furnished an exact record of the information which can be used as a more interpretative tool for the other record forms, and it also provides a redundant backup exami-nation record.

The six-channeled strip-chart recording provided a "hard copy" of test data for the gated regions of each of the three UT instruments.

Search unit module position was also recorded, providing exact correlation with other data records.

Analog tape recording of test data allows the largest degree of freedom for the SwRI DAS. It may be used in place of or in addition to the strip chart recorder.

2. Reactor Vessel Examination Device (Fi re 4)

The Reactor Vessel Examination Device, fabricated by Prograauned and Remote Systems, Inc. with technical input from SwRI, was adapted to the St. Lucie Plant, Unit 2, RPV by the use of tripod legs specially designed and built for that purpose. The examination positioning

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STe LUCIE PLAttTi UNIT 2 SUHHARY OF THE PRESERVICE EXAHINAT'ION e

PAGE . 1 Rl'.ACTOR PRESSURE VESSEL (FIGURES REFERENCED BELOH)

N I 0 ONGT ASHE ASHE SHRI SUHHARY R S E H SFCT XI ITEM SECT XI MELO NUHBER AND/OR EXAH ~ PROCEDURE SHEET E IOE NO CATGY EXAHINATION AREA 1DENTIFICATION HETHOD NO ~ /REV ~ NUHBER C G H R REHARKS W W W ~ >> ~

CIRCUHFEMENlIAL SHELL MELDS (SEE FIGUME A-1)

Hl. 1 1 B A 106-121 UTOL 700~6/10 001000 e LIHITED UTOL, UT45 AND UT60 UPPER SHELL-TO HIDDLE UTOH, X FROH THE UPPER SHELL SIDE DUE SHELL UT45 X TO NOZZLE INTERFERENCE. SEE UT45T X ~ w APPENDIX F FOR HELD COVERAGE UT60 X LIHITATIONS~ ONE UTOM AND OttE UT60T X UT60 CODE ALLOHABLE INIDCA-I ION

• • DIBASIC CALIBRATION BLOCK*+*

UT-1 UT-2 Ul.ll B-A 101-171 UTOL 700 6/10 001100 X LIHITED EXAHIHATION IN THE HIDOLE SHELL TO LOMER UTOH X AREAS CONTAINING SURVEILLANCE SHELL UT45 X CAPSULE HOLDERS'EE APPENDIX UT45T X F. FOR MELD COVERAGE UT60 X LIHITATIONS~

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• • • BASIC CALIBRATION BLOCKsa*

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X LUG INTERFERENCE AND FROH THE UT45'T45T X LOMFR HEAD SIDE DUE TO THE UT60 X CORE STOP LUGS ~ LIHITED HANUAL UT60T X UTOL AND UT60 FROH THE LONER UTOL 600 15/46 X tlEAD SIDE DUE TO MELD LOCATION UTOH OEV ~ 2 X PADS'EE APPENDIX F FOR MELD UT15RL X COVERAGE LIHITATIONS~ HANUAL UT45 X UT PERFORHED FROH THE OUTSIDE UT45T X SURFACE TO HAXIHIZE COVERAGE ~

UT60 X UT60T X

• • • BASIC CALIBRATION BLOCK***

UT 2 UT 4

'T ~ LUCIE PLAHTi UNIT 2 SUHHARY OF THE PRESERVICF EXAHINATION PAGE REACTOR PRESSURE VESSEL (FIGURES REFERENCED BELOW)

(CONTD)

H I 0 OHGT ASHE ASWE SWRI SUHHARY R S E H

• SECT XI SEC1 XI WELD NUHBER AND/OR EXAM, PROCEDURE SHEET E I 0 E ITEN HO CATGY EXAHIHATIOH AREA IDENTIFICATION HETHOD NO ~ /REV ~ NUMBER C G M R REHARKS LONGITUDINAL SHELLi HELDS (SEE FIGURE A"4) 0'2 B>>A 101 124A HIDDLE SHELL AT 15 DEG ~

UTOL UTOH 700 6/10 001600 X X

FIVE UTOLr THO UTOHe AND ONE UT45 CODE ALLOMABLE IHDICA UT45 X X T ION(S) ~

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as*BASIC CALIBRATION BLOCK*wa UT 2=

81.12 8-A 101 1248 UTOL 700%6/10 001700 X ONE UTOL AND ONE UTOH CODE HIDOLE SHELL AT 135"DEG, UTOH X ALLOHABLE INDICATION, UT45 ~ w X UT45T )(

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• • • BASIC CALIBRATIOH BLOCK***

UT 2 81 ~ 12 B-A 101 J124C UTOL 700 6/10 001800 )( a m w LIMITED UTOLg UT45 ~ AHD UT60 HIDOLE SHELL AT 255"DEC ~ UTOM X OUE TO SURVEILLANCE CAPSULE UT45 X HOLDER IHTERFEREHCE, SEE UT45T X w ~ ~

APPENDIX F FOR HELD COVERAGE UT60 X LIHITATIOHS~ TWO UTOMg TMO UT60T X UT45 ~ AND TWO UT60 CODE ALLOH ABLE INDICATIONS~

a**BASIC CALIBRATION BLOCK*~a UT 2 01,12 B-A 101 142A UTOL 700 6/10 001900 X w a w ONE UTOH CODE ALLOWABLE LOWER SHELL AT 15-BEGS UTOH X IHOICATIOH~

UT45 X UT45T X UT60 X UT60T X a*~BASIC CALIBRATION BLOCK**a UT-2

ST ~ LUCIE PLANTi UNIT 2 SUHHARY OF THE PRESERVICE EXAHINATION PAGE 5 REACTOR PRESSURE VESSEL (FIGURKS REFERENCED BELOM)

(CONTD)

N I 0 ONGT ASHE ASHE SMRI SUHHARY R S E H SECT XI SECT XI MELO NUHBER AND/OR EXAH ~ PROCEDURE SHEET E I 0 E ITEH NO CATGY EXAHINATION AREA IDENTIFICATION HETHOP NO./REV ~ NUHBER C G H R REMARKS HERIDIONAL HEAD MELDS (SEE FIGURE A 3) 01.22 8-A 101-154A UTOL 700"6/10 002300 X LIHITED HKCH UT DUE TO FLOM LONER HEAD AT 30 DECL UTOM X -X SKIRT AND CORE STOP LUG UT45 SEE APPENDIX F FOR INTER'ERENCE X X ~

UT45T X X HELD COVERAGE LIHITATIONS, UT60 HANUAL UT HAS PERFORHED FROM UT60T THE OUTSIDE SURFACE TO MAXI HIZK COVERAGE'UHEROUS UTOH UTOL 600 15/46 COOK ALLOMABLE INDICATIONS~

UTOM DEV ~ 2 UT45 UT45T UT60 UT60T

• • DIBASIC CALIBRATION BLOCXa**

UT 4 81,22 8-A 101 1548 UTOL 700-6/10 002400 X LIHITKD HECH UT DUE TO FLOM LOMER HEAD AT 90"DEC ~ UTOM X SKIRT AND CORE STOP LUG INTER UT45 X FERENCE ~ LIHITED HANUAL UTOL UT45T X ANO UTOM OUE TO HELD LOCATION UT60 X PAD INTERFERENCE'EE APPENDIX UT60T X F FOR HELD COVERAGE LIHITA-TIONS ~ HANUAL UT MAS PERFORHED UTOL 600-15/46 X FROM THE OUTSIDE SURFACE TO UTOM DEV ~ 2 X MAXIMIZE COVERAGE ~

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ST ~ LUCIE PLANTi UNIT 2 SUHHARY OF THE PRESERVICE EXAHINATION PAGE REACTOR PRESSURE VESSEL (FIGURES REFERENCED BELOH)

(CONTO)

N I 0 ONGT ASHE ASHE SHRI SUHHARY RSEH SECT XI SECT XI HELD NUHBER AND/OR EXAH, PROCEDURE SHEET E IOE 1TEH NO CATGY EXAHINATION AREA IDENTIFICATION HETHOD NO ~ /REVS NUHBER CGHR REHARKS HERIDIONAL MEAD HELUS (SEE FIGURE A 3)

(CONTD) 81.22 8 A 101-154E UTOL 700 6/10 002700 X LIHITED HECH UT OUE TO FLOH LONER HEAD AT '270"DEG ~ UTOH X SKIRT AND CORE STOP LUG INTER UT45 X FERENCE ~ LIHITEO HANUAL UTOL UT45T X X ANO UT60 FROH THE COUNTER UT60 X CLOCKHISE SIDE DUE TO SURFACE UT60T X GOUGE SEE APPENDIX F FOR HELD COVERAGE LIHITATIONS~

UTOL 600 15/46 X HANUAL UT HAS PERFORHED FROH UTOM DEY, 2 >>>>>> X THE OUTSIDE SURFACE TO HAXI UT45 X HIZE COVERAGE'NE UTOH AND UT45T X ONE UT60 CODE ALLOXABLE INDI UT60 X CATION ~

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• • • BASIC CALIBRATION BLOCK**~

UT-4 01.22 8-A 101 154F UTOL 700"6/10 002800 X LIHITEO HECH UT DUE TO FLOH LONER HEAD AT 330 DEG ~ UTOH X SKIRT AND CORE STOP LUG INTER UT45 X FERENCE ~ LIHITED HANUAL UTOL UT45T X X AND UT60 FROH THE CLOCKHISE UT60 X SIDE DUE TO THE HELD LOCATION UT60T >> PAO INTERFERENCE'EE APPENDIX F FOR HELD COVERAGE LIHITA UTOL 600 15/46 X>>>> TIONS, HANUAL UT HAS PERFORHED UTOW OEV ~ 2 X FROH THE OUTSIDE SURFACE TO UT45 X HAXIHIZE COVERAGE ~

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ST ~ LUCIE PLANTr UNIT 2 SUHHARY OF THE PRESERVICE EXAHINATION PAGE 9 REACTOR PRESSURE VESSEL (FIGURES REFEREtlCED BELOM)

(CONTD)

N I 0 0 N G T ASHE ASHE SMRI SUHHARY R S E H SECT XI SECT XI MELD NUHBER AND/OR EXAH ~ PROCEDURE SHEET E I 0 E 1TEH NO CATGY EXAHIttATION AREA IDENTIFICATION HETt{OD NO ~ /REV ~ NUHBER C G H R REHARKS NOZZLE VESSEL HELOS (SEE FIGURE A-2)

(CONTD) 03.90 B-0 105 1218 UTOL 700" 6/10 003100 X UT15 AND UT45 PERFORHED FROH OUTLET NOZZLE AT 180"BEGS UTOM THE NOZZLE BORE, LIMITED (tTOLr UT45 UT45 ANO UT60 1:ROH THE VESSEL UT45T X SHELL DUE TO THE FLANGE TAPER, UT60 X LIHITED UTOH, UT45T AND UT60T UT60T X DUE TO THE INTEGRAL EXTENSION UT15 X a CONFIGURATIONS SEE APPENDIX F UT45 X FOR HELD COVERAGE LIMITATIONS~

NUHEROUS UTOM THO UT45 ~ AND FOUR UT60 CODE ALLOMABLE INDI CAT IONS ~

• • • BASIC CALIBRATION BLOCK*~~

UT 1 TAPERED UT-10 O3 ~ 90 0 D 103-121A UTOL 700 6/10 003200 UT15 AND UT45 PERFORHED FROM INLET NOZZLE AT 60 DEGe UTOM THE NOZZLE BORE ~ LIMITED UTOL UT45 X -AND UT60 FROM THE VESSEL SHELL UT45T X DUE TO THE FLANGE SEE UT60 X APPENDIX F FOR MELD COVERAGE UT60T X LIHITATIONS~ NUHEROUS UTOL UT15'T45 X AND UTOM CODE ALLOMABLE INDI-X CATIONS ~

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-0 ST ~ LUCIE PLANTt UNIT 2 SUHHARY OF THE PRESERVICE EXAHINATION PAGE ll RLACTOR PRESSURE VESSEL (FIGURES REFERENCED BELOW)

(CONTO)

N I 0 ONGT ASHE ASHE SHRI SUHHARY R S E H SECT XI SECT XI HELD NUHBER ANO/OR EXAH ~ PROCEDURE SHEET E I 0 E ITEN NO CATGY EXAHINATION AREA IDENTIFICATION HETHOD NO ~ /REV ~ NUMBER C G H R REHARKS NOZZLE INTEGRAL EXTENSIONS (FIGURE A"2)

U3. 100 B-D ON-IE-A 60T 700 6/10 003600 X OUTLET NOZZLE AT 0 DEG ~

• a*BASIC CALIBRATION BLOCK***

IR CSCL 66 SLC 83 100 8-D ON-IE-8 60T 700i6/10 003700 X OUTLET NOZZLE AT 180 OEG ~

• • • BASIC CALIBRATION BLOCK*i*

IR-CSCL 66 SLC NOZZLE INSIDE RADIUS SECTIONS (SEE FIGURE A 2) 83 ~ 100 8-D ON-IR-A UT90 . 700 5/9 003800 X OUTLET NOZZLE AT 0"BEGS

~*~BASIC CALIBRATION BLOCKi**

IR"CSCL"66"SLC 83 ~ 100 B-D ON-IR-8 UT90 700 5/9 003900 X OUTLET NOZZLE AT 180 DEG ~

• w*BASIC CALIBRATION BLOCK***

IR CSCL 66"SLC 03,100 8-D IN IR A UT90 700 5/9 004000 X INLET NOZZLE AT 60"DEG ~

• • DIBASIC CALIBRATION BLOCK*w*

IR-CSCL 66"SLC

APPENDIX A CLASS 1 WELD IDENTIFICATION FIGURES (Reactor Pressure Vessel)

APPENDIX A CLASS 1 WELD IDENTIFICATION FIGURES (Reactor Pressure Vessel)

Table of"Contents Fi ure No. Title ~Pa e A-1 Reactor Pressure Vessel Outline and Weld A-1 Identification A-2 Reactor Pressure Vessel Nozzle Outline and A-2 Weld Identification A-3 Reactor Pressure Vessel Upper Shell and A-3 Lower Head Outline and Weld Identification A-4 Reactor Pressure Vessel Middle and Lower A-4 Shells Outline and Weld Identification A-5 Reactor Pressure Vessel and Associated Butt A-5 Welds

REACTOR PRESSURE VESSEL OUTLINE AND WELD IDENTIFICATION RPV SUPPT. LUO IOI- IZ I 20I-I4 I IOI.ITI 106 -I2 I OUTLET IOI -I 5 I RE BRL. AMPLINO TUBE ANTI.ROT LU TUBE SUPPORT TUBE CORE BRL.

SUPP'U SUPPORT MATINS SURFACE

~

CORE BRL.

SUPPT. LU ORE BR ANTI~ ROT LU IOAMENT INLET FIGURE A- I

REACTOR PRESSURE VESSEL UPPER SHELL AND LOWER HEAD OUTLINE AND WELD IDENTIFICATION 101-1228 180o UT TA11OET ISSo UT TA1102T 90'01-151 IOI 154C ISOo 150o 210o 101-154 0 101-122 2SSo 101-1548 101-154 90o ZTOo ZTOo 101-154 A 101.154 30o 330o Oo 101-122A 0.

201-141 UT TAROET FIG UR E A -S

REACTOR PRESSURE VESSEL AND ASSOCIATED BUTT WELDS RC 201-128A RC- 201-1288 RC-112-6 AC-121-6 I

904 RC- 401-128A RC- 401 1288 RC 114 I R 0-125-I 00 180

~ NOHTH 27 04 AC-II5-6 RC-124-6

/

RC- 201 1280 AC 201 1280

• SHOP WELD No.

PP NOT USE SUBASSEMBLY FIGURE A-5

APPENDIX B MODULE CONFIGURATION SKETCHES

APPENDIX B MODULE CONFIGURATION SKETCHES Table of Contents Drawin No. Title ~Pa e A-SK 683 Wall Scrubber Module Configuration Nos. 1 and 2 B-1 A-SK 678 Wall Scrubber Module Configuration Nos. 3 and 4 B-2 SK 783 Transverse Wall Scrubber Configuration Nos. 5 and 6 B-3 SK 781 Transverse Wall Scrubber Configuration Nos. 7 and 8 B-4 SK 684 Inlet/Outlet Nozzle Butt Weld Shoe Away from Vessel C/L 6 CWT Configuration No. 9 B-5 SK 760 Inlet/Outlet Nozzle Butt Weld Shoe Toward Vessel C/L & CCWT Configuration No. 10 SK 868 Inlet Nozzle, I.D. Inspection Configuration No. 11 B-7 SK 872 Nozzle/Shell Outlet Configuration No ~ 12 B-8 SK 799 Computer Controlled Module Nozzle"to-Shell Configuration Nos. 17 and 18 B-9 A-SK 710 Vessel Plange Configuration No. 19 B-10 SK 870 Outlet and Inlet Nozzle Used with Configuration Nos. 11 and 12 B-11

CONF IOUflATION tIO. 2 COIIFIOUAATION NO. I Tof'F VESSEL 60 0 I 0

o J DlflECTION OF ANOLE DEALl O WELD O

45 4

O DIIIECT IOtl 0 OF AIIOLE SEAM WALL SCflUBDEA MODULE 80 0

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A-SK 683

CQNF36UR ATION NO. 5 TQP OF VKSSKL BEAM QIRKCTIQN C W SwRI ROTATOR at CTS.

ii 1.5 60 OF WEt 0 C ONFl GV RAT I QN NO. 6 J.

6Q BEAi4 QIRE CTIQN CCW ta SwRI ROTATOR at '4 I a~

TPANSVPRSK 'NALL SCRUBc" R SX 783 B-3

l; L

INCIDENCE I'OINT INCIDENCE POINT 882 GW T llAHSVEIISE Q VESSEL PIVOT POINT INLET/OUTLET NOZZLE OUTl WELD SIIOE AWAY FIIOhl VESSEL 4 Il CWT CONF lbunATION Ho. g Sk- 684

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0

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INC IDEN CE POINT 5.9 Inlet Nozzle I.D. Inspection Configuration No. 11 SK 868 S T. LUG I E 2 B>>7

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CQHRQURATIOH .I-. 18 9EA M OIR ECTIOH C'H SCAN OIRKC< IOH C7f 5 iC 799 B-9

LO N G I TU D IN A L I5 3.2 VESSEL CENTERLINE OUTLET 8 INLET NOZ ZLE USED WITH CONFIGURATION NOS. 11 AND 12 SK 870 ST. LUG IE 2

APPENDIX C SwRI Nuclear Projects Operating Procedures.

Administrative in nature; therefore, not included as part of the Technical Report.

APPENDIX D SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURES

APPENDIX D C

SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURES Table of Contents Procedure/Rev. No. Title SwRI-NDT-600-15/46 Manual Ultrasonic Examination of Pressure Dev. 2 Vessel Welds SwRI-NDT-700-5/9 Mechanized Ultrasonic Examination of Vessel Components, Vessel Welds, and Piping Welds SwRI-NDT-700-6/10 Mechanized Ultrasonic Examination of Ferritic Vessels Greater than 2.0 Inches in Thickness SwRI-NDT-800-78/0 Mechanized Ultrasonic Examination of Devs. 2 and 3 St. Lucie RPV Nozzle-to-Piping Butt Welds SwRI-NDT-900-7/3 Visual Examination of Nuclear Reactors

1I P ROCEDURE DEVIAT)ON SI TE t PROCEDURE / REVISION HO.

St. Lucie Unit 600-15/46 l40. 2'EVIATION PAGE "

DATE REQUESTED I SECT IOk: PAGE I

2 OP 9

)

Peb. 25, 1982 .0,6.0,8.0

• OP 33 I. lit Hs I H s S Fos' List socs sosclf Ic stse st csnlooneli I f0 oe s soistne4 In occord onc s

<<ith this ssvlof ton stot ~ ~ so inInotton F or sod, coinoonont 14entlfl cotlon, Ilns idsntlf lection, <<oi4 identtflcotlen, etc. )

Manual examination of reactor pressure vessel welds to be conducted during the Ci i

1982 PSI shall be affected by this deviation.

IJ Cl

• Pages 2, 9, 23, 32

~dVu 10 II I folio<<s l uss scoot r

<<ordlno th t srooossd, II w 0 scdltlonol b I shoots I

iney h

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If 4 /

sscssscry )i hi ~ I fr sin es Change 2.1 to read as follows:

The following documents, as applicable, form a part of this'procedure.

ASME Boiler and Pressure Vessel Code,Section XI, 1977 Edition, with Addenda through Summer 1978, "Rules for Inservice Inspection of Nuclear Power Plant Components."

(2) ASME Boiler and Pressure Vessel Code,Section V, 1977 Edition with Addenaa through Summer 1978, "Nondestructive Examination."

,(3) SwRI Nuclear Quality Assurance Program Ywnual (NEPH).

(4) NRC Regulatory Guide 1.150 entitled, "Ultrasonic Testing of Reactor Vessel kvelds During Preservice and Inservice Examinations."

6.1.3 I7aveform Photos Photographs shall be taken of the RP waveform of a reflector and of the unloaded initial pulse. This shall be performed during initial and final calibration and upon change of ultrasonic instrument, search unit, search unit cable, or use of another calibration block.

W CV ltd'a C4 Lt tv JI!s. tFIc ytois i !tucson oneness is necsssery ond <<not it is ntenoe4 to occoinotish I use C44tttonot snouts if 0 necessary ) ~

dI These changes are necessary to reflect the code requirements for the St. Lucie Unit 2 PSI, to comply with the requirements of NRC Reg. Guide 1.150 and to provide the examiner with new forms which are more compatible with the Reg. Guide require-ments.

s<<nt vonii ft

Deviation 2

<<RI NDT-600-15/46 DEVIATION: {Continued)

Page 3 of 9 (4) Check the CBZ sweep iateasity for enough brightness fax a good photograph. Vith the CRT camera, obtain a Polaroid picture oi the KF waveform. Label the picture as to ultrasonic instrument serial number,,os~~oscope delay ~

control settings, i.e., VOLTS/DXV, TZK/DIV and DELE'iHE, position coatrol.

Change 8.0 eo z'ead as follows:

8.0 RECORDS AND SIZING CRZ3.:.RZA 80TE It is recoga"red that not all ule asonic reflectors iad" cate flaws, since certain meeallurgical discontinuities aad geo-me~c conditions may produce iadicati'oas that are noe relevant. Inc'uded ia this category are plate segregates in the heat-af ec ed roue, cLad iaterface aad backs>>

re"lectioas. Plate segz'egaees in the heat>>affected tone may become reflective azter fabrication; these may, appear's spot or ~~ e iadicatioas when ezra~~ ed using stra"ghe-beam long ending. wave techniques. These indications shall not be considered a repor aole cond"eioa.

8.1 Recordia Criteria Ultrasonic reflectors producing a response 20K or g eater of the reference 1evel shall be recorded. Ultrasoa"c plaaar surface reflectors obeained at 100K or g eater oi the response from s~e notch shall be recox'ded.

Ult asoaic reflectors detected at 20X or greater of the, reiereace level aad planar sur=ace reilectoxs MOX or greater oi ehe response f=om the square notch aad not re-solved as geome~ by the ezax~er shaLL remi e additional data to be recorded.

Iadicatioas noe resolved as geome~ shaLL be recorded to the 1QX ~~ts along the length aad Wdth of the indication.

Deviation 2 SwRI M)T-600-15/46 Page 5 of 9 DEVIATION: (Cant>>wued)

I 8.3 ~Revortin Ktzasanic reflectors 20X or greater of the reference level and planar surxace ref lectoxs 100X or g eater ox the response fxam the square notch investigated and found to be other than geometrical in nature shall be reported to the customer for evaluation.

Zf the sMe ox the indication, as deteraxLned in accaxdance with Paragx'aph 8.2, eauals or exceeds the allowable limits of Sect>>an XZ of the fLPaH 3oiler and Pressux'e Vessel Code, the indications shall be reported.

The following s~~ also be reported:

(1) The best estimate of the erxar band in si ing the flaws and the basis for this estimate should be gLven o (2) The best estimate ox the port>>on of the volume required to be ezaMed by the A&K Bailer and.

Pzessu=e Vessel Cade that has not been effectively examined, such as:

(a) Volumes of material near each suxfzce due to near-field or othe ezfects.

(b) Volumes near interfaces between clad~>> and paxent material.

(c) Volumes shadowed by 3.aminar defects.

(d) Volumes shadawed by par" geometry.

(e) Volumes inaccessible to the search unit.

(z) Volumes affected by electronic gat>>~g.

(g) Volumes near the sux=ace opposite fram the sea-ch un>> t.

Change the second paragraph of 10.0 to read as follows:

Documents generated in'ccordance with this procedure shall be stored and retained as a portion of,the e~mination report. The examination report shall be stored by the iMnager of the Support and Administration Section, Quality Assurance Systems and Engineering Division, in the Data Storage Facility for the period specified by the contxactual agxee-ment with the customer.

PnOJECT No.

S I R l SITE PRESSURE 0

VESSEL EXAMlNATION RECORD E:DA- ot- n T El 2 In.c ocK SIIEET tlo.

EXAM STAIIT ED EQM ENDED SYSTEM COMPOIIEtlT LltlE SUDASSEMOLY IDENTIFICATION ip LOCATION Wp LOCATION EXAMINEn SNT LEVEL pnocEounE CALIDnaTlot o EXAMltlATION SUDFACE SUNFACE TEMP.

SIIEET (S) ANGLE No. USED INSIDEQ OUTSIDEQ OF EXAMINEn SNT LEVEL nEv. WELD LENOTI WELD TYPE SCAtltlln0 OEV. DO IND No. MAX o/o OF OAC SEancll UNIT At(OLE SEAncll UtllT LOCATION L

loo/ DAC 20o/ DAC Soo DAC IOO% Oac W MAX 100/o DAC 5O% Oac 20 / OAC Io / DAC MEAsltnEMEIITs nEMANKs h'IP Wtl MP Wl MP Wl MP Wl hIP W2 MP MP W2 MP WI IO%LI 20% LI 50% L I l00%LI L MAX 00% L2 50%L2 2O%I.2 I0%L2 M III'o C

L POS OO Q

A4 MV Ol M rt o~HOQ L POS I P nEYIEwED DY SNT L EVEL DATE ~a~ C3 PAGE OF I SWhl Fohll NO. NOIh IF-IOO lit I-4II

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SN R I PRESSURE VESSEL INDICATION RECORD CONTINUATION SHEET PROJECT tl0. SIZE DATE I DAY- MOH - YA kZ A

E: 24 life Cj OCK S

EXAM ENDED IIZKD SIIEET HO.

SYSZEM COMPONEtlT LINE SUBASSEMBLY IDE T F C TION CONTINUED FROM SIIEET EXAtAIIIEII SHZ I.EVEL EXAMINEII SHT LEVEL CONTltlUED ON SIIEET IHD HO. MAX  % OF DAC SEAACII UNIT ANGLE SEAIICII UtlIT LOCATION L

I0% DAC 20 j DAC 50% DAC IOO /o DAC W MAX 100 jo DAC 50% DAC 20% DAC too/o DAC MEASUAEMEHZS AEMAIIKS WI MP Wl Vll MP WI MP VI MP Wl MP W2 MP VI2 MP W2 MP L POS L POS L POS L POS L POS L POS L POS L POS L POS L POS L POS IIEVIEWED DY SHT LEVEL DATE PAGE OF SWRI SORM llO. HD'fR ll l07 II1 l Sl)

I J'

SOUTHWEST RESEARCH lNSTlTUTE SwRI-%)T-600-15 NUCLEAR PROJECTS Revision 46 OPERATING PROCEDURE September 1981 Page 1 of 33 Title Manual Ultrasonic Examination of Pressure Vessel. fields EFFECTlVITY AND APPROVAL Revision 4d oi this procedure became eiiective on >oi h i 9> . Other revisions oi the base documem may be effective con"-urrentiy.

1 Approvals g(P v

Date s/i</r<

I Manager of CLA. Date Cog i nt Director Date dEe . Pd~E f~~/r lne following information may be used for convenience. mpletion of this portion is not mandatory.

Deviation No.

Date Effective Procedure Section(s)

Affected Notes:

SwRI Form daAMOAW

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SwRI-NDT-600-15 SOUTHWEST RESEARCH INSTITUTE Revision 46 September 1981 tS- NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 33 Screen Block Distance Block T e Dimension 5 Qrr SwRI Half-Round, 1.0" AWS Type DC 1.0" rr IIW 0 10 ~ 0" t 20 0" IIW 4.0" Screen Block Distance Block T e Dimension 5.0" SwRI Half-Round, 1.0" Radius AWS Type DC 1.0" and 2.0" Radii 10.0" SwRI Half-Round, 1.0" Radius AWS Type DC 1. 0" and.

lr Q Radii IIW 4.0" Radius 20.0", 40.0" IIW 4.0" Radius 5.3 Basic Calibration Block Where the component material is clad, the basic calibration block shall be clad to the component clad nominal thickness of ~1/8 inch.

Deposition of clad shall be by the automatic method used on the component.

Whexe the automatic method is impxactical, deposition of clad shall be by 'the manual method used to cover the circumferential welds of the component.

Side-drilled basic calibration hole reflectors in accordance with Figure T-434.1 of Article 4 of Section V of the ASIrE Boiler and Pressure Vessel Code shall be placed in a block manufactured from one of the following:

(1) the component nozzle dropout; (2) the component prolongation,'r (3) mate-rial of the same specification, product form, and heat treatment as one of the materials being joined. The basic calibration block thickness shall be .detex-mined by the average thickness of the weld. The requirements for basic cali-bration block curvature limits, heat treatment, surface condition, and scribe lines shall be in accordance with Article 4 of Section V.

sw4I Form OA 3 2'

(0 SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-15, Revision 46 September 1981 S

NUCLEAR PROJECTS OPERATING PROCEOURE Page 7 of 33 The exit point of the sound beam and the actual refracted beam angle of shear-wave search units shall be determined on an IIW block. The exit point of the sound beam shall be marked on the search unit wedge.

Search unit wedges shall be fabricated to produce 45'2'nd 60'2'efracted shear-waves as demonstrated on the IIW block. A search unit producing 0'traight-beam longitudinal-waves shall also be used.

The nominal search unit frequency shall be 2.25 MHz.

5.5 Ultrasonic Instrument

. The examiner shall select an appropriate ultrasonic instru-ment from the following:

(1) Sonic PTS Mark I (2) Sonic PTS Mark II (3) Sonic UWA Mark'II Each instrument shall be aligned and shall display an alignment calibration sticker as required by NQAP 10-1.

5.6 Couolant (1) USP-grade glycerine or deionized water (with or without wetting agent) shall be used when performing ultrasonic calibrations and examinations in accordance with this procedure.

(2) Couplant materials used for examinations shall be the same as used for the calibration.

(3) Light oil or other compounds, which in the opinion of the Level II examiner concurrence provide adequate ultrasonic coupling, of the Project Manager may be used upon responsible for the examination.

(4) All couplants other than deionized water shall be certi-fied for sulfur content and total halogens in accordance with ASTM D-129-64 and ASTM D-808-63. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Deionized water, when used, shall be supplied by the customer.

SwRI Fnrm OA-3 2~

t. SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-15 Revision 46 lg September 1981

q. $g NUCLEAR PROJECTS OPERATING PROCEDURE

] Page 9 of 33 6.1.2 Am litude Control Linearit (1) Position a shear-wave search unit on a basic calibration block to obtain maximum amplitude from the 1/2T hole.

(2) Without moving the search unit and according to the following table, set the indication to the required percent of FSH and increase or decrease the dB as specified. The signal shall be estimated and recorded to the nearest 1% of FSH and shall fall within the limits of the following table:

Indication Indication Set at X of dB Control Limits, % of Full Screen Chan e* Full Screen 80X -6 dB 32 to 48%

80X -12dB 16 to 24%

,e 40X 20X

+6dB

+12 dB 64 64 to to 96X 96%

• Minus denotes decrease in amplitude; plus denotes increase.

6.2 Calibration The complete ultrasonic examination system calibration shall be performed prior to the examination.

NOTE The "REJECT" control shall be maintained in the "0" position during calibration and examination.

The "FREQ MHz" control shall be turned to "2" when a 2.25 MHz search unit is used.

The centerline of the search unit shall be at least 1-1/2 inch from the nearest side of the block. (Rotation of the beam into the corner formed by the hole and the side of the block may produce a higher amplitude at a longer beam pass; this beam pass shall not be used for calibration.)

swRI FOrm OA 3 2

t-e, SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-15 Revision 46 September 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 11 of 33 (2) Position the 45'earch unit on the appropriate reference block and observe the radius echoes.

(3) Construct a linear screen as specified in Paragraph 6.2.2.

(4) Record reference block data required on the appropriate SwRI Sonic Instrument Calibration Record.

Do not change the "MAT 'L CAL," "RANGE,"

or 'DELAY" controls during the next step or attempt to compensate for any slight difference observed between the 45'nd 60'creen distance calibrations.

(5) Position the 60'earch unit on the appropriate refer-ence block and observe the maximum amplitude and loca-tion of the first echo from the radius.

(6) Record reference block data required on the appropriate SwRI Sonic Instrument Calibration Record.

6.2.3 Strai ht-Beam Distance Am litude Correction for Material Greater than 2.0- to 12.0-Inches in Thickness (1) Position straight-beam search unit on the basic calibra-tion block to obtain maximum response from the calibra-tion hole with the highest amplitude from the following:

Hole 1/4T 1/2T 3/4T lf (2) Adjust gain controls to obtain the primary reference response at 80% +5X of PSH and mark this amplitude on the instrument screen.

NOTE Ensure that instrument gain controls are not changed once the primary reference response has been established.

SwRI ForfTI Oa 3 2

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~ SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-15 Revision 46 September 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 17 of 33 I

(4) Type, size, beam angle, and serial number of the ultra-sonic search unit (5) Nominal search unit frequency (6) Couplant (which shall be the same type as used in the actual examination)

(7) Signature and ultrasonic certification level of exam-iner conducting calibration (8) Date calibrated (9) Time of calibration and calibration verification (10) Temperature of calibration block (ll) Length and type of search unit cables (12) Serial number of thermometer used.

7.0 EXAMINATION 7.1 Surface Condition The contact surfaces must be free from weld spatter, rough-ness, or other conditions which interfere with free movement of the search unit or impair the transmission of ultrasound.

7.2 Reference Points for Ph sical Measurements 7.2. 1 Nozzle-to-Shell Welds A concentric reference circle around each nozzle which encom-passes the scan area shall be marked on the shelf. This circle shall be refer-enced to the centerline of the respective nozzle by indicating its radius'he location of the 0'zimuth of each nozzle shall be noted on the appropriate SwRI examination record. The 0', 90', 180', and 270'zimuth shall be marked along the concentric reference circle for any nozzle weld examined. All azi-muth locations marked on the shell shall be numbered in a clockwise direc-tion as viewed from the vessel exterior. Each 30 degrees of azimuth shall be marked around the reference circle for nozzle welds with a radius greater than 4 inches. Each 15 degrees of azimuth shall be marked on nozzle welds with a radius greater than 12 inches . Nozzle welds with a radius greater than 24 inches shall be marked along the reference circle each 5 degrees of azimuth.

A concentric reference circle shall also be marked within 1/2 inch of the weld SwRI Fnrm QA 3 2

SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-15 Revision 46 Ig September 1981 NUCLEAR PROJECTS OPERATING PROCEDURE

,y A3 Page 19 of 33 (2) Add 6 dB of gain by adjusting the fine gain control only.

Observe the signal amplitude.

(3) Add 6 dB of gain by adjusting a combination of both fine and coarse gain controls. Observe the signal amplitude.

(4) Add 6 dB of gain by manipulating the 6 dB switch, if present. Observe the signal amplitude.

(5) Choose the method above which yields a signal response closest to 80X FSH.

(6) The method chosen shall be used during the valid calibra" tion period for all scanning at 2 times the reference level sensitivity.

The examiner shall ensure that the signal response of the method chosen is within ~2 dB of 100% FSH. Record this amplitude and method on the SwRI Sonic Instrument Calibration Record.

Instrument gain settings for scanning shall be recorded on the appropriate SwRI examination record.

The search unit movement rate for scanning shall not exceed 6 inches per second.

7.5 Scannin Overla Scanning overlap shall be a minimum of lOX of the search unit piezoelectric element dimension perpendicular to the direction of scan. Scan-ning performed in a direction perpendicular to the weld shall extend as required to examine 1/2t of base material from the weld fusion line. Scanning performed in a direction parallel to the weld shall extend a minimum distance of 1/2t on each side of the weld, when possible. \

7.6 Lon itudinal and Circumferential Butt Welds in Vessels Longitudinal and circumferential butt welds in ferritic pres-sure vessels greater than 2.0- to 12.0-inches nominal thickness shall be examined.

Manual ultrasonic examination of pressure vessel welds and adjacent base material shall be performed from the inside or outside surface of the vessel.

SwRI Form 0 JL 3 2'

SOUTHWEST RESEARCH INSTITUTE SvRI-NDT-600-1'evision 46 September 1981

.[s .

NUCLEAR PROJECTS OPERATlNG PROCEOURE r~ A) Page 21 of 33 7.6.4 Strai ht-Beam Examination of Melds A straight-beam examination shall be applied when possible, to the surface of the weld crown and 1/2t of base material on each side of the weld. Calibration for the straight-beam examination shall be in accordance with Paragraphs 6.2.1 and 6.2.3.

7 ~ 6.5 An le-Beam Examination for Indications Per end'icular to the Meld Angle-beam examination shall be conducted using a 45'2'nd 60'2'hear"wave search unit. This examination shall be conducted by placing the search unit on the weld with the sound beam directed into and parallel with the veld to detect indications perpendicular to the weld. The length of the weld as specified in the applicable examination plan and 1/2t of base material on each side of the weld shall then be scanned with the search unit sound beam directed in this manner. The search unit shall then be turned 180'nd the scan repeated. Calibration for these examinations shall be in accordance with 6.2.2 and 6.2.4 (or '6.2.5). 'aragraphs 7.7 Nozzle-to-Vessel But t Melds Manual ultrasonic examination of nozzle"to-vessel butt welds in ferritic vessels greater than 2.0- to 12.0-inches nominal thickness shall be performed from the inside or outside surface of the vessel.

Base material ad)acent to the weld for a distance of 1/2t from the fusion line of the weld shall be examined.

I 7.7.1 Base Material Lamination Scan A lamination scan using a straight-beam search unit shall be performed before'he angle-beam examination. This examination shall cover as much as practical of the area through which the angle-beam is later to be passed. Screen distance calibration for this examination shall be conducted in accordance with Paragraph 6;2.1. Scanning sensitivity shall be as required to maintain the first back reflection at an amplitude of 80X of PSH.

Intermediate echoes having an amplitude equal to or greater than the remaining back reflection shall be recorded. To record an inter-mediate indication, obtain a back reflection signal from an indication-free area and ad5ust the instrument gain controls until this signal is at 80X ~5/ o:

PSH; then record the intermediate indication when its amplitude is equal to the remaining back reflection- If total loss of back reflection accompanies the intermediate echo, the area of total loss of back reflection shali be recorded on the appropriate SwRI examination record.

swRr Fnrm QA 3 2'

S OUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-15'evision 46 September 1981 IS- NUCLEAR PROJECTS OPERATING PROCEOURE

,, .I~P Page 23 of 33 8.0 RECORDING CRITERIA.

Ultrasonic reflectors producing a response 50Z or greater of the refer-ence level and planar surface reflectors equal to or exceeding the response from the square notch shall be recorded on the appropriate SwRI examination record.

Indications shall be recorded utilizing the techniques outlined in the applicable revision of SwRI Nuclear Projects Operating Procedure IX-PE-118.

Indications producing a response 50Z or greater of the reference level and planar surface reflectors equal to or exceeding the response from the square notch shall be investigated by a Level II or a Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector.

Indications 50Z or greater of the reference level and planar surface reflectors equal to or exceeding the response from the square notch investi-gated and found to be other than geometrical in nature shall be reported to the customer for evaluation.

When an examination is performed from the unclad side of a clad vessel and the calibration is as specified in Paragraph 6.2.5, indications observed past the 4/8 vee-path shall not be recorded.

Scanning limitations shall be recorded-9.0 EVALUATION Evaluation of reportable indications shall be the responsibility of the customer, or the customer's representative, and shall be conducted in accor dance with the ASME Boiler and Pressure Vessel Code,Section XI, IWA-3000. The applicable year and Addenda of the Code shall be as specified in Paragraph 2.1(1) of this procedure.

10.0 RECORDS The customer shall receive copies of documents generated in accordance with this procedure in the examination report.

The onsite control of examination records generated in the field shall be in accordance with SwRI Nuclear Projects Operating Procedure X-PE-3.01-1.

SwRI r:arm QA 3 Z

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SMRI-NDT-600-1S Revision 46 September 1981 Page 27 of 33 IIW REFERFiMCE ELOCK 40'0'0 2 CA TYP 325 ~IR ii ~

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SwRI-NDT-700-5 SOUTHWEST R ES EAR CH INSTITUTE Revision 9 NUCLEAR PROJECTS December 1981 OPERATING PROCEDURE Page 1 of 23 Title MECHANIZED ULTRASONIC EXAMINATION OP VESSEL COMPONENTS, VESSEL WELDS, AND PIPING WELDS Revision ~

be effective oi this nrocedure concurrently.

EFFECTlVITY AND APPROVAL became attentive on Jan. ' 04,1982 . Other revisions oi tha base document may SA Approvals Date Technical Review Date

<<n IQ~ 8( Mvmps ~/~~

Date

~ized~, (Pf/7 '~/e The following information may be used for convenience. mpletioh of this portion is not mandatory.

r u Deviation No.

Date Effective Procedure Sec:ion(sl Affected Notes:

swRI Focm oA-40A.0

SwRI-NDT-700-5 SOUTHWEST RES EARCH INSTITUTE Revision 9 December 1981 NUCLEAR PROJECTS OPERATlNG PROCEDURE Page 3 of 23 calibration block to be either "t," no more than 25X less than "t," or closer in thickness to the produc-tion material than the 3/4-inch alternate thickness allowed by Article 5 for production material thick-nesses up to and including 1 inch. This exception will assure a more accurate calibration than the Article 5 basic calibration block design allowed by Code.

(b) Subsubparagraph T-535.1 (d) of Article 5 states that transfer (attenuation compensation) be accomplished between the production material and basic calibration block and a correction made for the difference. No attempt shall be made by the examiner to compensate for observed difference in "the acoustic properties between the basic calibration block and the produc-tion material, as referenced in 7.1.

(3) ASME Boiler and Pressure Vessel Code,Section IX, 1977 Edition with Addenda through Summer 1978 "Welding and Brazing Qualifications" (4) SwRI Nuclear Quality Assurance .Program Manual (NQAPM) 3.0 RESPONSIBILITY (1) The Director of the Department of Engineering Services within the Quality Assurance Systems and Engineering. Division shall be responsible for the preparation, review, control, and approval of this procedure.

(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan.

(3) The examiner shall be responsible or implementing the require-ments of this procedure.

I (4) The Manager of the Support and Administration Section of the Quality Assurance Systems and Engineering Division shall be responsible for storage of records generated in accordance with this procedure.

swRI Form QA3-2

SwRI-NDT-700-5 SOUTHWEST RESEARCH INSTITUTE Revision 9 December 1981 NUCLEAR PROJECTS OPERATING PROCEOURE Page 5 of 23 5.0 PERSONNEL AND E UIPHENT 5.1 Personnel Certification Personnel performing examinations in accordance with this procedure shall be certified in accordance with-SwRI NQAP ll-l, "Special Process Control.",

5.2 Reference Block Reference blocks to be used for screen distance calibration and verification shall be as follows:

(1) SwRI Half-Round (Sketch 1)

(2) AWS Type DC (Sketch 2)

(3) IIW (Sketch 3)

The reference block shall be of the same basic material as the production material; i.e., carbon steel or stainless steel.

5.2.1 Reference Block Selection Reference blocks shall be used as follows for screen distance calibration:

Screen Block Distance Block Tyne Dimension 1.0", 2 SwRI Half-Round ] plf AWS Type DC P 5" or 1 0" IIW pll

.5",

5.0"l 10.0" SwRI Half-Round pll AWS Type DC pll IIW ] plf 20.0" IIW 4 plf SwRI Farm OA 3-2

SwRI-NDT-700-5 SOUTHWEST RESEARCH INSTITUTE Revision 9 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE of 23 Page 7 A flat basic calibration block or block of essentially the same curvature as the part to be examined shall be used for examinations on contact surface curvatures greater than 20 inches in diameters For contact surfaces 20 inches or less in diameter, a single curved basic calibration block may be used to establish sensitivity calibration for examinations conducted on contact surfaces in the range of curvature from 0.9 to 1.5 times the basic calibration block diameter.'.4 Search Units The size of search units shall be selected according to the following table: ~

(1) An le Beam Nominal Production Material Thickness Nominal Search Unit Size 0.4" to 1.0" 1/4" x 1/4", 1/4" Round 0.4" to 2.0" 3/8" x 3/8", 3/8" Round 0.75" to 4.0" 1/2" x 1/2", 1/2" Round 2.0" to 7.0" 1/2" x 1", 3/4" Round 5.0" to 12.0" 1" x 1", 1" Round, 1-1/8" Round Nominal Production Material Thickness Nominal Search Unit Size 0.4" to 2.0" 1/4" Round 1.0" to 3.0" 3/8" Round 2.0" to 4.0" 1/2" Round 3 0I to 7.0"

~

3/4" or 1" Round 5.0" to 12.0" 1" Round or 1-1/8" Round The exit point of the sound beam and the 'actual refracted beam angle of shear-wave search units shall be determined on an IIV block. The exit point shall be marked on the search unit wedge.

Search unit wedges shall be fabricated to ensure that the proper angle of refracted snear- or longitudinal-waves are produced in accordance with the appropriate SwRI Scan Plan.

SwRI Farm QA 3-2

SwRI-NDT-700-5 SOUTHWEST RESEARCH INSTITUTE Revision 9 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 23 (3) Light oil or other compounds which, in the opinion of the Level II examiner, provide adequate ultrasonic coupling may be used upon concurrence of the Project Manager respon-sible for the examination.

(4) All couplants other than deionized water shall be certified for sulfur content and total halogens in accordance with ASTM D-129-64 and ASTM D-808-63. The residual amount of total sulfur or halogens shall not exceed 1X by weight.

Deionized water, when used, shall be supplied by the customer.

5.7 Thermometer Quicktemp thermometer Model 5X-666, calibrated and certified in accordance with SwRI Nuclear Pro)ects Operating Procedure XII-PM-104 shall be used as required to measure basic calibration block and component surface temperature.

6+0 CALIBRATION METHOD Calibration details such as vee-path positions and sweep distance shall be described in the applicable SwRI Scan Plan.

The complete ultrasonic examination system calibration shall be per-formed prior to the examination.

NOTES The "REJECT" control shall be maintained in the "0" position during

'calibration and examination.

The nominal piping production material thickness shall be used to deter-mine the correct calibration block and search units for the examination of piping components which may be thicker than the nominal pipe size and welded to the pipe. The Level II examiner shall ensure that complete coverage of the thicker piping component is obtained. Additional cali- ~

bration vee-path positions and larger screen sizes may be required to assure this coverage. The additional calibration vee-path positions and larger screen size shall be used for the examination from the thicker component and the nominal pipe side of the weld.

The "PREQ MHz" control shall be turned to "1" when a 1.5 MHz search unit is used and to "2" with a 2.25 MHz search unit.

SwRI Form QA 3.2

SwRI-NDT-700-5 SOUTHWEST RESEARCH INSTITUTE Revision 9 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 11 of 23 (4) With the larger indication at 100X, record and the position of the smaller indication, estimated to the nearest 1X of FSH.

(5) Successively set the larger indication from 100X to 20X of FSH in 10X increments (or 2 dB steps if a fine control is not available) ~ Observe and record the smaller indication, estimated to the nearest 1X of FSH, at each setting. The reading must be 50X of the larger amplitude within 5X of FSH.

6.1.2 Amnlitude Control Linearit EXCEPTION Am amplitude control linearity check is not required if an electronic DAC is utilized and/or the gain controls are not to be manipulated.

(1) Position a shear~ave search unit on an SwRI Half-Round reference block to obtain maximum amplitude from the radius.

(2) Without moving the search unit and according to the following table, set the indication to the required percent of the FSH and increase or decrease the dB as specified.

The signal shall be estimated and recorded to the nearest 1X of FSH and shall fall within the limits of the following table:

Indication Indication Set at X of dB Control Limits, X of Full Screen Chan e* Full Screen 80X -6 dB 32 to 48X 80X -12dB 16 to 24X 40X +6dB 64 to 96X 20X +12dB 64 to 96X

• Hinus denotes decrease in amplitude; plus denotes increase.

6.2 Strai ht-Beam Distance Calibration Distance calibration for circumferential welds and longitudinal welds shall be constructed by observing the back reflections from an applicable reference block and adjusting the "KKTrL CAL," "DELAY," and "RANGE" controls swRI Form QA 3-2

SwRI-NDT-700-5 SOUTHWEST RESEARCH INSTlTUTE Revision 9 December 1981 NUCLEAR PROJECTS OPERATING PROCEOURE Page 13 of 23 Position the search unit to obtain maximum response from the basic calibration hole at 1/2T. Adjust this amplitude to the primary reference level at 50% ~5% of full screen height (PSH) and mark the amplitude on the screen. A straight horizontal line shall then be drawn on the instrument screen at the amplitude of the primary level. The line shall extend a distance equal to the nominal thickness of the production material. All indications recorded shall be referenced as a percentage of this line for signal amplitude.

6.5 Electronic Distance Amnlitude Correction Electronic DAC is used to set reflector responses from a cali-bration block equal in amplitude regardless of the distance of the reflector from the search unit.

6.5.1 An le Beam and Strai ht Beam for Welds Electronic DAC curves shall oe constructed by utilizing the responses from the basic calibration hole(s). The initial point on the DAC curve is established by manipulating the search unit to obtain maximum response from the nearest suitable position. The instrument gain is then adjusted so that this response is 50% ~5% PSH. This is the primary reference response and shall be marked on the instrument screen. The search unit shall be placed similarly at other required positions. Using the electronic DAC controls, adjust remaining responses to the primary reference level and mark their amplitudes on the screen. These points shall be joined by a straight hori-zontal line, not to extend more than 1/8 vee-path or 1/4T beyond the last qualified calibration point.

6.5.2 Multinle-Point Zone Calibration Maximum response from the nearest suitable reflector shall be obtained by manipulating the search unit. Adjust the instrument gain to set response at 50X ='5% PSH. This is the primary reference response and shall be marked on the instrument screen. The search unit shall be placed to obtain maximum response from the other required reflectors. Using the electronic DAC controls, adjust their maximum responses to the primary reference level and mark their amplitudes on the screen. These points shall be joined by a straight horizontal line, not to extend more than 20% of the wall thickness to either side of the calibrated zone.

6.5.3 Sin le-Point Zone Calibration for Inner Radius Without Usin Electronic Distance Am litude Correction Examination of the inner radius from the inside surface shall be conducted without using the electronic DAC controls. Two search units shall be SwRI Form QA 3-2

0 SwRI-NDT-700-5 SOUTHWEST RESEARCH INSTITUTE Revision 9 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 15 of 23 (3) The last calibration verification at the end of a shift shall be conducted during the interface period and in conjunction with the oncoming crew. The two crew leaders shall verify the calibration together as a handoff. Both crew leaders'nitials should appear on the calibration sheet for verification conducted in this manner.

NOTES The mechanized positioning equipment calibration shall be verified in conjunction with the instrument calibration verification or at least every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during the exami-nation. Device counts per increment shall be verified to coincide with counts per increment as specified in the Scan Plan examination tables'he "0" position and linearity of the X and Y readout shall be veriried in accordance with the appropriate Operating Guide.

Ultrasonic instrument functional checks shall be conducted every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during scanning to determine if any apparent functional changes have occurred in the instrument. H'ny reflector from the function block has moved on the sweep line more than 5X of full screen width or changed in ampli-tude more than 20X or 2 dB, the instrument calibration shall be verified on the appropriate reference and basic calibration blocks.

6 6.2 Calibration Chan es (1) Perform the following if any point on the DAC curve has decreased more than 20X or 2 dB in amplitude, any point on the DAC has moved on the sweep line more than 5X of full screen width or more than 10/ of the sweep division reading, whichever is less:

(a) Void all examinations referring to the calibration in question and performed after the last valid calibra-tion verification.

(b) Conduct a new calibration.

(c) Reexamine the areas for which examinations have been voided.

SwRI Farm OA3.2

SwRX-NDT-700-5 SOUTHV/EST R ES EAR CH INSTITUTE Revision 9 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 17 of 23 (5) Nominal search unit frequency (6) Couplant (which shall be the same as used in the actual examination)

(7) Signature and ultrasonic certification level of examiner making calibration (8) Date calibrated (9) Time of calibration and calibration verification

'I 7.0 EXAMINATION 7.1 Examination Areas The following are specific areas on which mechanized ultrasonic examination of pressure vessel welds, piping welds, adjacent base material, and components from the inner or outer surface of pressure vessels shall be performed:

(1) Piping welds and adjacent base material in a thickness range of greater than 0.4 inch and up to 5.0 inches (2) Vessel welds and adjacent base material in a thickness range of greater than 0.4 inch and up to 2.0 inches (3) Nonwelded vessel'omponents (i.e., nozzle inner radius, and integral extensions)'n a thickness range of greater than 0.4 inch and up to 12.0 inches Attempts to determine differences in the acoustic properties between the basic "calibration block and the production material which would result in an instrument gain change are not permitted.

F 1.1 Vessel Welds Examinations shall be performed on components in their completed condition. Examination of vessel welds shall include the weld and base mate-rial for 1/2t from the fusion line of the weld. The required 1/2t examination area on base material thicknesses that differ on each side of the weld shall be determined by the nominal thickness of the base material on the side or the weld from which the examination is to be performed. The 1/2t to be examined shall be measured from the outside sur ace fusion 1'ine at the weld crown.'he examination of vessel welds and adjacent base material shall be conducted with a 45'2'nd a 60'2'earch unit . The 45'2'nd the SwRI Form QA 3-2

SwRI-NDT-700-5 SOUTHWEST RESEARCH INSTITUTE Revision 9 December 1981 NUCLEAR PROJECTS OPERATlNG PROCEDURE Page 19 of 23 coverage for piping welds shall be adequate to examine the required portion of the weld and base material for 1/4 inch, as measured from the fusion line on each side of the weld. Scanning coverage for nonwelded components shall be specified in the applicable SwRI Scan Plan.

Examination techniques including search unit angles, contact surface and examination coverage will be described in the detailed SwRI Scan Plan for the particular examination. The SwRI Scan Plan shall be approved by the Director of the Department of Engineering Services.

Scanning shall be performed at the primary reference level sensitivity.

The search unit movement rate for scanning shall not.exceed 6 inches per second.

Before the angle-beam examination of welds, a lamination scan using straight-beam shall be performed, covering as much as practical of the area through which the angle beam is later to be passed. Screen distance cali-bration for this examination shall be conducted in accordance with Paragraph 6.2 of this procedure. Scanning sensitivity shall be as required to maintain back reflection at an amplitude of between 50X and 90% of FSH.

This lamination scan is performed by noting whether back echoes are lost or intermediate echoes are observed in any of the areas to be examined with an angle-beam search unit. Intermediate echoes having an amplitude equal to or greater than 50% of the initial back reflection shall be recorded. To record an intermediate indication, obtain a back reflection signal from an indication-free area and adjust the instrument gain control until this signal is at 75% ='5% of FSH. Record the intermediate indication when its amplitude is equal to 50X of the initial back reflection and accompanied by a 50X loss of back reflection. If total loss of back reflection accompanies the intermediate echo, the area of total loss of back reflection shall be recorded.

7.4 Postexamination Cleanin Arrangements shall .be made with thecustomer for postexamination removal of couplant materials.

8.0 RECORDING CRITERIA-Ultrasonic reflectors producing a response greater than 50% of the refer-ence level shall be recorded. Indications found to be greater than 50% of the reference level and not readily attributable to geometry by the examiner, when scanning in the X direction (length of indication), shall require scans in the s wRI Form QA 3-2

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SwRI-NDT-700-6 I

SO UTHW EST R ES EAR C H I N STITUTE Revision 10 Ah NUCLEAR PROJECTS December 1981 OPERATING PROCEDURE Page 1 of 27 l'itle MECHANIZED ULTRASONIC EXAMINATION OF FERRITIC VESSELS GREATER THAN 2.0 INCHES IN THICKNESS EFFECTIVITY AND APPROVAL Revision >0 ot this qrocedure became eifective on ~hh ~ ~ . Other revisions of the base document may be effective concurrently.

Approvals Wrinan By r Date Technical Review Datev

.inert -

~( / Ifnj r I

v Manager of Q.A Date Date I

J following information may be used tor convenience. Completion of this portion i'he is not mandato~.

Deviation No.

Date Effective Procedure Section(sl Affec:ed Notes:

swRI Fare QA-'0A-0

SwRI-NDT-700-6 SOUTHWEST RESEARCH INSTITUTE Revision 10 December 1981 C

R"' NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 27 3.0 RESPONSIBILITY (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible for the preparation, review, approval, and control of this procedure.

(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan.

(3) The examiner shall be responsible for implementing the requirements of this procedure.

(4) The Manager of the Support and Administration Section of the Quality Assurance Systems and Engineering Division shall be responsible for storage of reco'rds generated in accordance with this procedure.

4.0 CODE AND PROCEDURE RE UIREMENTS The requirements listed below shall be applied when performing mecha-nized ultrasonic examinations in accordance with this procedure.

Re uirements Section (1) Weld types and configurations to be 7.0 examined, including thickness dimensi,ons and product form (2) The examination surface(s) 7.0 (3) Surface condition 7.0 (4) Couplant 5.0 (5) Technique used 2.0 (6) Angles and mode of wave propagation in 5.0 the material 'I (7) .Type and size of search unit 5.0 swRI Farm QA 3.2

SwRI-NDT-700-6 SOUTHWEST RESEARCH INSTITUTE Revision ~

10 December 1981 MW I'UCLEAR R'- PROJECTS OPERATING PROCEDURE Page 5 of 27 5.2.1 Reference Block Selection Reference blocks shall be used as follows for screen distance calibration:

Screen Block Distance Block T e Dimension 5.0" SwRI Half-Round 1.0" AWS Type DC 1.0" IIW 1.0" 10.0", 20.0" IIW 4.0" (2) An le-Beam Screen Distance 5 0 11 Block Tv SwRI AWS Type e

DC

'.0" Half-Round Block Dimension Radius 1.0" and 2.0" Radii 10.0" SwRI Half-Round, 1.0" Radius AWS Type DC 1.0" and 2.0" Radii IIW 4.0" Radius 20.0", 40.0" IIW Block 4.0" Radius 5.3 Basic Calibration Block If examinations are to be conducted on a clad component, the basic calibration block shall be clad to the nominal thickness of the component cladding 21/8 inch. Deposition of clad shell be by the automatic method used on the inside of the component. Where the automatic method is impractical, deposition of clad shall be by the manual method used to cover the circum-ferential welds of the component .

SwRI Form QA3-2

SwRI-NDT-700-6 SOUTHWEST RESEARCH INSTITUTE Revision 10 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 27 Avera e Weld Thickness Nominal Search Unit Size 1/2" x 1/2", 1/2" 2 '"

2.0" to 4.0" to 7.0" 5.0" to 12.0" 1" x 1", 1" Round, Round 1-1/8" Round The exit point of the sound beam and the actual refracted beam angle of shear-wave search units shall be determined on an IIW block. The exit point of the sound beam shall be marked on the search unit wedge.

Search unit wedges shall be fabricated to produce 45'2'nd 60'2'efracted shear-waves as demonstrated on the IIW block. A search unit producing 0'traight-beam longitudinal-waves shall also be used.

Other angles may be used for examination of:

(a) flange welds, when the examination is conducted from the flange face, (b) nozzles and nozzle welds, when the examination is conducted from the nozzle bore, (c)'xamination of double taper junctures.

The nominal search unit frequency shall be 2.25 MHz.

5.5 Ultrasonic Instrument and Scannin Mechanisms The examiner shall select an appropriate ultrasonic instrument from the following:

(1) Sonic PTS Mark II (2) Sonic UWA Mark III (3) Branson Sonoray Series 600 Rota ing, revolving, or scanning mechanisms used when performing mechanized ultrasonic examinations shall be described in the SwRI Scan Plan.

SwRI Form QA 3.2

SwRI-NDT-700-6 SOUTHWEST RESEARCH INSTITUTE Revision 10 S- December 1981 R~ NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 27 Linearity Verification Record and the sheet number referenced on the applicable SwRI Instrument Calibration Record. An angle-beam search unit and the )/2T and 3/4T holes in a basic calibration block shall be utilized to conduct the instrument, linearity checks.

6.F 1 Amplitude Linearity (1) Position an angle beam search unit on a basic calibra-tion block to obtain indications from the 1/2T and 3/4T holes.

(2) Adjust the search unit position to give a 2-to-1 ratio between the two indications, with the larger indication set at 80/ of full screen height (FSH) and the smaller indication set at 40% of FSH.

(3) Without moving the search unit, adjust the instrument sen-sitivity (gain) to set the larger indication'o '00% of FSH.

(4) With the larger incication at 100/, record the position of the smaller indication, estimated to the nearest 1% of FSH.

(5) Successively set the larger indication from 100/ to 20%

of FSH in 10% increments (or 2 dB steps if a fine control is not available); observe and record the smaller indication estimated to the nearest 1/ of FSH at each setting. The reading must be 50/ of the larger amplitude within 5% of FSH.

6.1.2 Amnlitude Control Linearit EXCEPTION An amplitude control linearity check is not required if an electronic DAC is utilized and/or the gain controls are not to be manipulated.

(1) Position an angle-beam search unit on an applicable basic calibration block to obtain maximum amplitude from the 1/2T hole.

(2) Without moving the search unit and according to the following table, se" the indication to the required swRI Farm QA 3.2

SwRI-NDT-700-6 SOUTHWEST RESEARCH,INSTITUTE Revision 10 December 1981 S

R" I'"

NUCLEAR PROJECTS OPERATING PROCEDURE Page ll of 27 I

(3) Using the oscilloscope controls obtain a stable RF wave-form. Using the delayed sweep function of the oscillo-scope expand the desired RF waveform to a suitable form for photographing.

(4)'heck the CRT sweep intensity for enough brightness for a good photograph. With the CRT camera, obtain a Polaroid picture of the RF waveform. Label the picture as to the UT instrument serial number, remote pulser channel, and oscilloscope control settings; i.e , VOLTS/DIV, TIME/DIV, and DELAY TDK, and delay time position control.

For the reflector RF waveform the following shall be performed:

(1) Preset control on Tektronix oscilloscope, capable of delayed sweep, or equivalent oscilloscope to measure an RF waveform of approximately 0.5 volts, peak to peak.

(2) Using a coaxial cable approximately four feet long connect oscilloscope channel one to the RF output )ack provided on the UT instrument.

(3) Using the oscilloscope controls obtain a stable RF waveform. Using the delayed sweep function of the oscilloscope expand the desired RF waveform to a suitable form for photographing.

(4) Check the CRT sweep intensity for enough brightness for a good photograph. With the CRT camera obtain a polaroid picture of the RF waveform. Label the picture as to.UT instrument serial number and oscilloscope control set tings; i.e., VOLTS/DIV, TIM/DIV, DELAY TDE, and delay time position control.

6.2 Calibration Calibration details such as vee-path positions and sweep dis-tance shall be described in the applicable SwRI Scan Plan. 8 The complete ultrasonic examination system calibration shall be performed prior to the examination.

swRI Form QA 3-2

SwRZ-NDT-700-6 SOUTHWEST RESEARCH INSTlTUTE Revision 10 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 13 of 27 shall be constructed by observing the back reflections from an applicable reference block and adjusting the "MAT'L CAL," "DELAY," and "RANGE" controls of the instrument to obtain the required linear sound path distance displayed along the screen baseline. The screen distance chosen shall be the shortest applicable size to include at least 1/4t beyond the nominal production material thickness.

Distance calibration for vessel-to-flange welds from the seal surface and nozzle-to-shell welds from the inner bore shall be constructed by observing the back reflections from an applicable reference block and adjusting the "MAT'L CAL," "DELAY," and "RANGE" controls of the instrument to obtain the required linear sound path distance displayed along the screen baseline'he screen distance chosen shall be the shortest applicable size to include at least 25% of the wall thickness beyond the anticipated examination distance.

6.2.2 An le-Beam Distance Calibration Distance calibration for the examination of nozzle-to-shell welds from the vessel surface, circumferential welds, and longitudinal welds shall be constructed by observing the radius echoes from an applicable ref-erence block for the material and th'ckness involved and adjusting the "HAT'L CPJ" "DELAY," and "RANGE" controls of the instrument to obtain the required linear sound path distance displayed along the screen baseline. The screen dis ance chosen shall be the shortest applicable size to include at least 1/8 vee-path beyond the examination range ~

Distance calibration for nozzle-to-shell welds from the inner bore shall be constructed by observing radius echoes from an applicable ref-erence block fo- the material and thickness involved and adjusting the "MTrL CAL," "DELAY," and "RANGE" controls of the instrument to obtain the required linear sound path distance displayed along the screen baseline. .The screen distance chosen shall be the shortest applicable si e to include at least 25%

of the wall thickness beyond the anticipated examination distance.

The search unit wedge shall be removed prior to the preliminary distance calibration for examinations in which angle-beam longitudinal-wave search units are used. Observing the back reflections from an applicable reference block, adjust the "FATrL CAL," "DELAY," and "RANGE" control of the instrument to obtain the required linear sound path distance displayed along the screen baseline.

Remount and couple the search unit wedge to the search unit after the preliminary distance calibration of the angle-beam longitudinal wave search unit. Position the search unit on the basic calibration block and obtain the maximum response from a reflector. Physically measure the metal path distance to this reflector and adjust the signal to the appropriate SwRI Form QA 3.2

SwRI-NDT-700-6 SOUTHWEST RESEARCH INSTITUTE Revision 10 December 198]

NUCLEAR PROJECTS OPERATING PROCEDURE Page 15 of 27 (2) The search unit shall be placed similarly at the other required vee-path positions. Using the electronic DAC controls adjust their responses to the primary reference response and mark their amplitude on the screen-(3) Join these points with a straight horizontal line.

(4) With the instrument gain set at the primary reference level, position the search unit to obtain maximum ampli-tude from the square notch on the opposite surface. Hark the signal amplitude with an "X." The indication from the square notch must be considered when evaluating reflectors at the opposite surface.

6.3.2.2 Distance Amnlitude Correction from the Unclad Side (1) Electronic DAC curves shall be constructed by utili ing the 1/8, 2/8, and 3/8 vee"path responses from the basic calibration holes at 1/4T, 1/2T, and 3/4T. The initial point on the DAC curve is established by manipulating the search unit to obtain maximum response from the 1/8 vee-path position. The instrument gain shall be adjusted to set this response at or between 40% to 80% PSH. This is the primary reference response and 'shall be marked on the instrument screen.

(2) The search unit shall be placed similarly at the othe".

required vee-path positions. Using the electronic DAC controls adjust the responses to the primary reference response and mark their amplitude on the screen.

(3 ) Join these points with a straight horizontal line, the length of which shall extend 1/4T beyond the last qualified calibration point ~

(4) With the instrument gain set at the primary reference level, position the search unit to obtain maximum amplitude from the square notch on the opposite surface.

Hark the signal amplitude with an "X." The indication from the square notch must be considered when evaluating reflectors at the opposite surface.

6.3.3 Hultinle-Point Zone Calibration Haximum response from the nearest suitable reflector shall be obtained by manipulating the search unit. Adjust the instrument gain so this response is set at 40% to 80% FSH. This is the primary reference response and SwRI Form QA 3.2

SwRI-NDT-700-6 SOUTHWEST RESEARCH lNSTITUTE Revision 10 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE 17 of 27 Page (5) Position the search unit to obtain maximum amplitude from the 1/4T hole. Move the search unit toward the hole until the indication equals the 50% DAC linc'easure and record the distance from the incident point of the search unit to the scribe line above the 1/4T hole (Wl) ~

(6) Hove the search unit away from the hole until the indica-tion equals the 50% DAC line. Measure and record the distance from the incident point of the search unit to the 1/4T scribe line (W2).

(7) Repeat steps (5) and (6), recording the measurements for the 1/2T'nd 3/4T holes.

(8) Plot these points on a 1:1 or 2:1 scale drawing of the basic calibration block thickness or on the graph on the back of the SwRI Beam Spread Record. "W's" are plotted using the horizontal scale of the graph, placing the points at the appropriate depth (1/4T, 1/2T, or 3/4T).

(9) Draw a separate line to eacn of the Wmax points from the incident point of the search unit.

(10) The angle to each of the points shall be measured using a protractor. The beam angle shall be established by deter-mining the average of the three Wmax angles measured.

This angle shall be recorded on the SwRI Beam Spread Record and considered'during resolution of indications ~

(ll) Connect the three Wl points extending the line to the search unit drawn at the top of the graph. Repeat this operation for the W2 points ~ If the three Wl or W2 points do not form a straight line, a line representing the average of the three points shall be drawn and extended until they cross (the three points must be projected along the same beam path on the block drawing to complete this task) ~

(12) Measure the angle between the Wl line and W2 line. This is the angle of beam spread.

6.6 Calibration Verification 6.6.1 Freauenc of Instrument Calibration Verification Sweep range calibration shall be verified on the appropriate reference block; and DAC curve calibration, if applicable, shall be verified on the basic calibration block:

swRI Form QA 3.2

SwRE-NOT-700-6 SOUTHWEST RESEARCH lNSTlTUTE Revision 10 December 1981 MW NUCLEAR PROJECTS OPERATING PROCEDURE Page 19 of 27 6.6.2 Calibration Chan es (1) Perform the following if any'point has moved on the sweep, line more than 5X of full screen width, or more than 10X of the sweep division reading, whichever is less, or -any point on the DAC curve has decreased by 20% or 2 dB in amplitude:

(a) Void all examinations referring to the calibration in question and performed after the last valid calibration verification.

(b) Perform and record a new calibration.

(c) Reexamine the areas for which examinations have been voided.

(2) Perform the following if any point on the DAC curve has increased by 20% or 2 dB in amplitude:

(a) Correct the calibration.

(b) Reexamine any indications recorded since the last valid calibration verification.

(c) Enter proper values on a new SwRI Examination Record.

6.6.3 Recalibration Substitution of any of the following, shall be cause for recalibration:

(1) Search unit (wedge, module, or transducer)

(2) Couplant (3) Ultrasonic instrument (4) Examination personnel (substitution of examination person-nel shall be defined as any substitution of the Level Tl or Level ZIi crew leader during a shift)

(5) Cable type or length (6) Change in type of power source; e.g., a change from alter-nating to direct current SwRI Form QA3.2

SwRI-K)T-700-6 SOUTHWEST RESEARCH INSTITUTE Revision 10 December 1981 n wrra RIl. NUCLEAR PROJECTS OPERATING PROCEOURE Page 21 of 27 1

(3) This procedure is applicable to ultrasonic examinations of components greater than 2.0 inches and up to 12.0 inches in thickness.

Examinations shall be performed on components in their completed condition. Veld examinations shall include the weld and base material for 1/2t from the fusion line on each side of the weld. The 1/2t to be examined shall be measured from the fusion line at the weld crown.

The transfer method shall not be used.

7.2 Surface Condition The contact surfaces shall be free from weld spatter, rough-ness, or other conditions whicn interfere with free movement of the search unit or impair the trandmission of ultrasound'.3

~Scannrn Scanning overlap shall be a minimum of 10% of the search unit piezoelectric element dimension perpendicular to the direction of scan. Scan-ning coverage for welded components shall be adequate to examine the weld and 1/2t of base material from the fusion line of the weld.

Examination techniques including search unit angles, contact surface, and examination coverage will be described in the detailed SwRI Scan Plan for the particular examination ~ The SwRI Scan Plan will be approved by the Director of the Department of Engineering Services.

Scanning shall be performed at the primary reference level sensitivity.

The search unit movement rate for scanning shall not exceed 6 inches per second.

Before the angle-beam examination, a lamination scan using longitudinal- -ave shall be performed, covering as much as practical of the area through which the angle beam is later to be passed'creen distance calibra-tion for this examination shall be conducted in accordance with Paragraph 6.2.1 of this procedure. Scanning sensitivity shall be as required to maintain the first back reflection at a minimum amplitude of 80% of PSH.

This lamination scan is performed by noting whether back echoes are lost or intermediate echoes are observed in any of the areas to be examinee with an angle-beam search unit . Intermediate echoes having an amplitude equal to or greater than the remaining back reflection shall be recorded. To record an intermediate indication, obtain a back reflection signal from an indication-free area, adjust the instrument gain control until this signal is at 80% of ll swhl Form QA 3.2

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'wRI-M)T"700-6 SOUTHWEST RESEARCH INSTlTUTE Revision December 10 1981

@ic NUCLEAR PROJECTS OPERATlNG PROCEDURE Page 23 of 27 I

one-half degree). The recorded information shall include the indication travel length (metal path) and the transducer position for 10%, 20%, 50%,'nd 100X DAC and the maximum amplitude of the signal.

~ Volumes of material not examined and the reason for the scanning limitation shall be recorded.

8.2 Investi ation and Sizin Ultrasonic reflectors producing a response 20% or greater of the reference level and planar surface rerlectors 100X or greater of the response from the square notch shall be investigated by a Level II or a Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector.

8.2.1 Travelin Indications Indications that travel on the horizontal baseline of the instrument screen for a distance greater than indications from the calibration holes (at 20X amplitude) shall be sized. Indications that travel shall be recorded and sized at 20X DAC. %hen the indication is sized at 20% DAC, this size may be corrected by subtracting the beam width in the through-thickness direction ootained from the calibration hole (between 20X DAC points) that is at a depth at or near the flaw depth. If the indication exceeds 50X DAC, the size shall be recorded by measuring the distance between 50% DAC levels without using the beam-width correction. The determined size shall be the larger of the two.

8.2.2 Nontravelin Indications Nontraveling indications above 20% DAC that continue for a scanning distance of more than 1 inch, plus the beam spread between 20% DAC points shall be sized. The size of these flaws should be determined by measur-ing the distance oeween points at 50X DAC and between points at 20X DAC where the beam-width correction is made only for the 20% DAC size. The recorded size of the flaw is the larger of the two determinations .

8.3 ~Reaortln Ultrasonic reflectors 20X or greater of the reference level and planar surface reflectors 100% or greater of the response from the square notch which are investigated and found to be other than geometrical in nature shall be reported to the customer for evaluation.

If the size of an indication, as determined in accordance with Paragraph 8.2, equals or exceeds the allowable'imits of Section ZI or the AS';E Boiler and Pressure Vessel Code, the indications shall be reported.

swRI Form QA 3.2

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SwRI-NDT-700-6 Revision 10 December 1981 Page 27 of 27 IIW REFt=Rl=iMCE BLOCK

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SKETCH 3

P ROCEDURK OEVlAT]0N SITE:,, r" RONDURE / REVISION NO.

St. Lucie, Unit 2 800-78/0 OEYIATION NO. lsAGE OATK REQU~I SEOTION t

) 11i 2  ! 1 OF 2 I 3 Februarv 1982 6.0 12 OF 23

~ 1tIIII I she 1 evr Y Ust tech Ieoeiflc true uf cstesonon t te tc ~ se&lnc4 Ih tccetccnc ~

vIIh Isis cculefIQI l stet ~ ~ 1onlleetlcn )or104 ~ cotneoncet lcentlfl cctleo ~ line i4ontlficctlon ~ vol4 i4entitlceticn ~

w ~ tc. I ct Hechanized ultrasonic examinations of RPV noz le-to-piping butt welds to be performed during tne 1982 PSI at St. Lucie, Unit 2 shall be affected by this deviation.

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'L ~OVM lO II i 1 lt l 3 1 I t* 1M ~ / t ~ \ C <on porlo4 L,l ~ t serb conponont specific oroe or colsponon t l4ontlll ection, line lo bo ~ soealned ln record coo ~

Idontltlcctlon, veld Identltlcotlon, ellb ISI ~ coslof ten ~ ~

etc. )

O Manual ultrasonic examinations of RPV nozzle-to-piping butt welds to be performed cc during the 1982 PSI at St. Lucie, Unit 2 shall be affected by this deviation.

O I

O 4I C

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Z *1.0, 2.0, 5.0, 6.0, 7.0, 8.0 cc

• • Pages 2, 6, 10, 11, 12, 15, 16, 17, 18 and 19 s~VI4TIOK II I K Ia Ih I Ih I a hh K I I Ih I h ~ / )aII lf nocossory I I I I I I tcllev ~ I s ~o ~ sect oordlnC pro poso4 ~ o44ltlooel shoots Dey bo oso ~

Change 1.0 to read as follows:

This procedure provides the technical information and detailed steps required to ensure a complete and accurate mechanized or manual ultrasonic examination of RPV ferritic nozzle-to-piping butt welds in accordance with the applicable ASME Boiler and Pressure Vessel Code.

Change the first paragraoh of 2.0 to read as followsl laa as Mechanized and manual ultrasonic examinations shall be performed using shear-wave angle-beam and longitudinal-wave angle- and straight-beam, contact, pulse-echo techniques.

sat I

O Add 2.2 to read as follows:

2.2 A licable Calibration and Examination Records lal SwRI NDTR Form No. Revision Date 0

sa cc 17-19 7-10-80 17-25 7-10-80 ss 17-36 9-22-76 laa I 17-18 7-31-75 17-17 12-10-79 17-37 2-18-80 lal I

O Add paragraph (4) to 5.5 to read as follows:

(4) Sonic FTS Mark T JU$ TtptchTtott > Rocson chonco Is necessary cn4 vhct It ls 'ntondod tc cccocspllsh ( ooo eddltloncl shoots It ahc necessary )a s

n lo O These changes are necessary to allow manual ultrasonic examinations to be performed cc with this procedure.

s'v nl feb st rc o s

'SwRI NDT-800-78/0 Deviation No. 3 March 30, 1982 Page 3 of 6 (4) Join the calibration points with a smooth curved line extended .to caver the examinations range but not more than 1/4T beyond the last qualified calibration point.

6.3.2 An le-Beam Distance Am litude Correction from the Clad Side or on Nonclad Blocks 6.3.2.1 First Half Vee (45'nd 60'.)

(1) Position the 45' 2'earch unit on the basic calibration block to obtain maximum response from the calibration vee-path position with the highest amplitude from the following:

Hole 45'ee-Path Position 1/4T 1/8 1/2T 2/8 3/4T 3/8$ 5/8 (2) Adjust the gain controls to obtain the primary reference response at 80X + 5% of FSH and mark this amplitude on the screen. The gain control shall not be adjusted once the primary reference has been established.

(3) Position the 45' 2'earch unit to obtain max-imum response from the three other vee-path positions and mark each amplitude on the instru-ment screen.

(4) Join the calibration points with a smooth curved line to establish the distance amplitude correc-tion (DAC) durve.

(5) With the instrument gain set at the primary reference level, position the search unit (45' 2') for max-imum amplitude from the square notch on the opposite surface. Mark the signal amplitude with an "X". The Mdication from the square notch must be considered when evaluating reflectors at the opposite surface.

(6) Repeat steps (1) through (5) using a 60' 2search unit.

SwRI NDT-800-78/0 Deviation No. 3 March 30, 1982 Page 5 of 6 (3) Position the 45' 2'earch unit to obtain maximum response from the two other vee-path positions and mark each on the instrument screen.

(4) Position the 45' 2'earch unit on the clad side of the block. Determine the dB difference between the 3/8 and 5/8 vee-path. Mark the location of the 5/8 vee-path on the baseline r

of the instrument.

(5) Position the appropriate search unit on the unclad side of the block. Adjust the instrument gain controls to the primary reference level established in step (2) and obtain the maximum response from the 3/8 vee-path.

(6) Decrease the signal from the 3/8 vee-path by the dB difference determined in step (4). Mark the amplitude of this signal at the predetermined location of the 5/8 vee-path determined in step (4). Join the marks on the instrument screen to construct the DAC curve.

(7) With the instrument gain set at the primary reference level, position the appropriate search unit to obtain maximum amplitude from the square notch on the opposite surface. Mark the signal amplitude with an "X". The indication from the square notch must be considered when evaluating reflectors at the opposite surface.

(8) Repeat steps (1) through (7) using a 60' 2'earch unit.

Change 6.6.1 (4) to read as follows:

(4) At least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the examination Delete the last two paragraphs and note of 6.6.1.

Change 6.6.3 (4) to read as follows:

(4) Examination personnel Change the first paragraph of 7.1 to read as follows:

Mechanized or manual ultrasonic examination of nozzle-to-piping butt welds and adjacent base material from the inner or outer surface shall be performed.

SOUTHWEST RESEARCH INSTITUTE SvRI-NDT-800-78

~

~ Revision 0 NUCLEAR PROJECTS December 1981 OP ERATING P ROC ED U R E Page 1 of 23 Title MECHANIZED ULTRASONIC EXAMINATION OF ST. LUCIE RPV NOZZLE-TO-PIPING BUTT WELDS EFFECTIVITY AND APPROVAL Revision~ oi this procedure became effe ive on Jhn ~ 5 1982, Other revisions of the base document may be effective concurrently.

Approvals yyritten 8y Date Technical Review Date mr C

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pC/

Manager of Q.A. Date Date l(&Pi 1 KJllZ The following information may be used for convenience. Completion of this portion is not mandatory.

Deviation No.

Date Effec:ive Procedure Action(s}

Affec:M Notes:

swRI Form cA~OAN

SwRX-NDT-800-78 SOUTHWEST RESEARCH INSTITUTE Revision 0 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 23 (2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRX Project Plan.

(3) The examiner shall be responsible for implementing the requirements of this procedure.

(4) The Manager of the Support and Administration Section of the Quality Assurance Systems and Engineering Division shall be responsible for storage of records generated in accordance with this procedure.

4.0 CODE AND PROCEDURE RE UXREMENTS The requirements listed below shall be applied when performing mecha-nized ultrasonic examinations in accordance with this procedure.

Reauirements Section (1) Weld types and configurations to be 7.0 examined, including thickness dimensions and product form (2) The examination surface(s) 7.0 (3) Surface condition 7.0 (4) , Couplant 5.0 (5) Technique used 2.0 (6) Angles and mode of wave propagation in 5.0 the material (7) Type and size of search unit 5.0 (8) Examination frequency 5.0 (9) Search unit wedges, shoes, or saddles 5.0 (10) Ultrasonic instrument alignment 5.0 (11) Calibration method used 6.0 (12) Scanning 7.0 SwRI Form QA3.2

SwRI-NDT-800-78 SOUTHVVEST RESEARCH INSTITUTE .

Revision 0 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 23 (2) An le-Beam Screen Block Distance Block e Dimension 5.0" SwRI Half-Round 1.0" Radius AWS Type DC 1.0" and 2.0" Radii 10.0" SwRI Half-Round, 1.0" Radius AWS Type DC 1.0" and 2.0" Radii IIW 4.0" Radius 20.0" IIW Block 4.0" Radius 5.3 Basic Calibration Block If examinations are to be conducted on a clad component, the basic calibration block shall be clad to the nominal thickness of the component cladding 91/8 inch. . Deposition of clad shall be by the automatic method used on the inside of the component. Where the automatic method is impractical, of clad shall be by the manual method used to cover the circum- 'eposition ferential velds of the component.

Side-drilled basic calibration hole reflectors, in accordance vith Figure T-434.1 of Article 4 of Section V of the ASlK Boiler and Pressure Vessel Code, shall be placed in a block manufactured from one of the following:

(1) the component nozzle dropout; (2) the component prolongation; or (3) mate-rial of the same specification, product form, and heat treatment as one of the materials being joined. The basic calibration block thickness shall be deter-mined from the average veld thickness. The requirements for basic calibration block curvature limits, heat treatment, surface condition, and scribe lines shall be in accordance with Article 4 of Section V.

Notches 2XT deep shall be machined in the basic calibration block surface, in accordance vith Article 4 of Section V.

A flat basic calibration block or block of essentially the same curvature as the examination contact surface shall be used for the examination of welds with a contact surface curvature greater than 20 inches in diameter.

A single curved basic calibration block may be used to estab-"

lish distance amplitude correction (DAC) curves fo" examinations on contact surfaces in the range of curvature from 0.9 to 1.5 times the basic calibration block diameter, when contact sur ace curvature is 20 inches in diameter or less.

SwRI Foram QA 3.2

SwRI-NDT-800-78 SOUTHWEST RESEARCH INSTITUTE Revision 0 December 1981 Ra NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 23 I

Automatic defect alarm and recording equipment to be utilized is specified in SwRI Nuclear Operating Procedures XII-PM-106, XII-PM-108, and XII-PM-129

'ach instrument shall be aligned and shall display an alignment calibration sticker as required by NQAP 10-1.

5.6 ~Cou lant (1) USP"grade glycerine or deionized water (with or without wetting agent) shall be used when performing ultrasonic calibrations and examinations in accordance with this procedure.

(2) Couplant materials used for examinations shall be the

'same as used for the calibration.

(3) Light oil or other compounds, which in the opinion of the Level II examiner provide adequate ultrasonic coupling, may be used upon concurrence of the Project Manager responsible for the examination.

(4) All couplants other than deionized water shall be certified for sulfur content and total halogens in accordance with ASTM D-129-64 and ASTM D-808-63. The residual amount of total sulfur or halogens shall not exceed 1X by weight. Deionized water, when used, shall be supplied by the customer.

5.7 Thermometer Quicktemp thermometer Model 5X-666, calibrated and certified in accordance with the applicable revision of SwRI Nuclear Projects Operating Procedure XII-PM-104, shall be used as required, to measure calibration block and component surface temperature.

6-0 CALIBRATION METHOD 6.1 Instrument Linearit The ultrasonic instrument shall be verified for amplitude lin-earity and amplitude control 1'inearity in accordance with Paragraphs 6.1.1 and 6.1.2. This verification shall be conducted at the beginning of each day in accordance with the linearity requirements in Article 4 of Section V. For the purpose of this procedure, a day shall be defined as a 24-hour period star"ing with the A.M. shift. Data required shall be recorded on the SwRI Instrument SwRI Form QA 3-2

SwRI-NDT-800-78 SOUTHWEST RESEARCH INSTITUTE Revision 0 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 23 specified. The signal shall be estimated and recorded to the nearest 1X of FSH and fall within the limits of the following table:

Indication Indi'cation Set at X of dB Control Limits, X of Pull Screen Pull Screen 80X -6 dB 32 to 48X 80X -12 dB 16 to 24X 40X dB 64 to 96X 20X +12 dB 64 to 96X

+Minus denotes decrease in amplitude; plus denotes incr ease .

6.2 Calibration Calibration details such as vee-path positions and sweep distance shall be described in the applicable SwRI Scan Plan.

The complete ultrasonic examination system calibration shall be performed prior to the examination.

NOTES The "REJECT" control shall be maintained in the "0" or "OPP" position during calibration and examination.

The "PREQ MHz" control shall be turned to "2" when a 2.25 MHz search unit is used'he instrument gain controls shall not be changed once the primary reference response has been established.

The temperature of the basic calibration block during calibra-tion and verifications shall be within 25'F of the component temperature. Por examinations from the inside sur ace of vessels, water temperature inside the vessel may be used for component temperature. Under no circumstances shall examinations be performed if the temperature of the basic calibration block is not within 25'P of the component to be examined.

The temperature of the basic calibration block during the initial calibration and the temperature during each verification shall be recorded on the applicable SwRI Instrument Calibration Record. The component temperature prior to performing the examination and upon completion of the examination shall be recorded on the applicable SwRI Examination Record.

swRI Focm QA 3 2

SwRI-NDT-800-78 SOUTHWEST RESEARCH INSTITUTE Revision 0 December 1981 NUCLEAR PROJECTS OPERATING PROCEOURE Page ll of 23 location on the screen baseline, using only the "DELAY" control The screen

~

distance chosen shall be the shortest applicable size to include at, least 25X of the wall thickness beyond the anticipated examination distance ~ This completes the distance calibration.

6.3 Electronic Distance Am litude Correction Electronic DAC is used to set responses from a calibration reflector equal in amplitude xegardless of the distance of the reflector from the search unit.

6.3.1 Strai ht-Beam for Production Material Greater than 2.0 Inches in Thickness (1) Position the search unit for maximum response from the basic calibration hole at 1/4T. Adjust the instrument gain to obtain a signal amplitude at or between 40X to 80X FSH. This is the primary reference response and shall be marked on the instrument screen.

(2) Position the search unit for maximum response xrom the basic calibration hole at 1/2T. Using the electronic DAC controls, adjust the signal amplitude to the primary reference response and mark its amplitude on the screen.

(3) Repeat this operation for the 3/4T hole. Join these points with a straight horizontal line the length of which shall extend 1/4T beyond the last qualified calibration point.

6.3.2 An le-Beam 6.3.2.1 Distance Amplitude Correction from the Clad Side or on Nonclad Blocks (1) Electxonic DAC curves shall be constructed by utilizing the 1/8, 2/8, 3/8, and 5/8 vee-path responses from the basic calibration holes at 1/4T, 1/2T, and 3/4T. The initial point on the DAC curve is established by manip-ulating the search unit to obtain maximum response from the 1/8 vee-path position. The instrument gain shall be ad]usted to set this response at or between 40X to 80%

FSH. This is the primary reference response and shall be marked on the instrument screen.

(2) The search unit shall be placed similarly at the other required vee-path positions. Using the electronic DAC controls, adjust their responses to the primary reference response and mark their amplitude on the screens SwRI Form QA3-2

SwRX-NDT-800-78 SOUTHWEST RESEARCH INSTjTUTE Revision 0 December 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 13 of 23 6.4 Sin le-Point Zone Calibration Without Usin Electronic Distance Am litude Correction Maximum response from the applicable reflector shall be obtained by manipulating the search unit ~ Adjust the instrument gain to set this signal to 80X &5X PSH. This is the primary reference response and shall be marked on the instrument scr'een. The area to be examined shall extend no more than 20X of the wall thickness to either side of the calibrated point.

6.5 Beam S read and Beam An le Determination Angle-beam search units used for examinations shall be measured for beam spread and beam angle. These measurements shall be conducted accord-ing to the following steps for examinations calibrated in accordance with Paragraph 6.3 or 6.4 as applicable.

NOTE Beam spread and beam angle for zone calibrations shall be determined by recording the distance to the Wl 50Z DAC point, Wmax point, and W2 50X DAC point for each calibration reflector in a manner similar to that described below for vee" path calibrations.

(1) The instrument shall be calibrated as described in Para-graphs 6.2.2, 6.3, or 6.4 as applicable.

(2) With the instrument at the primary reference level sensi-tivity, position the search unit to obtain maximum ampli-

~

tude from the 1/4T hole (Wmax). Measure and record the distance from the incident point of the search unit to the scribe line above the 1/4T hole ~

(3) Repeat step (2), recording the distance to the scribe line for holey'ove both the 1/2T and 3/4T maximum amplitudes'4)

Determine the location and mark a line on the screen to represent the 50X DAC.

(5) Position the search unit to obtain maximum amplitude from the 1/4T the search unit toward the hole until the indication equals the 50% DAC line. Measure and record the distance from the incident point of the search unit to the scribe line above the 1/4T hole (Wl) ~

SwRI Form QA 3-2

SwRI-NDT-800-78 SOUTHWEST RESEARCH INSTITUTE Revision 0 e

December 1981

~,

R~ NUCLEAR PROJECTS OPERATING PROCEDURE Page 15 of 23 I

(3) With any substitution utilizing the same type of power source; e.g., a change from one direct current to another direct current source (4) At least every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during the examination (5) At the finish of a series of examinations (6) At any time when, in the opinion of the examiner, there is doubt as to the validity of the calibration When a group of examinations have been completed, the final verification shall be initialed by the crew leader in charge.

The last calibration verification of each snift sh'all be con-ducted during the interface period and in conjunction with the oncoming crew.

The two crew leaders shall verify the calibration together as a handoff. Both crew leaders'nitials should appear on the calibration sheet for verification conducted in this manner.

NOTE The mechanized positioning equipment calibration shall be verified in conjunction with the instrument calibration verification or at least eve'ry 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during the exami-nation. Device counts per increment shall be verified to coincide with counts per increment as specified in the SwRI Scan Plan examination tables'he "0". position and linearity of the X and Y readout shall be verified in accordance with the appropriate SwRI Nuclear Projects Operating Guide.

Ultrasonic instrument functional checks shall be con-ducted every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of scanning time to determine if any apparent functional changes have occurred in the instru-ment. If any reflector from the function block has moved on the sweep line more than 5% of full screen width or changed in amplitude more than 20% or 2 d3, the instru-ment calibration shall be verified on the appropriate reference and basic calibration blocks.

6.6.2 Calibration Chan es (1) Perform the following if any point has moved on the sweep line more than 5% of full screen width or if any point on the DAC curve has decreased by 20% or 2 d3 in amplitude:

SwRI Form QA 3-2

SwRI-NDT-800-78 SOUTHWEST RESEARCH INSTITUTE Revision 0 December '1981 NU CLEAR P RO J ECTS OP E RATING P RO CEO UR E Page 17 of 23 (1) Serial number of the basic calibration block (2) Serial number of the reference block (3) Type, serial number, and manufacturer of the ultrasonic instrument (4) Type, size, beam angle, and serial number of the ultra-sonic search unit (5) Nominal search unit frequency (6) Couplant (which shall be the same as used in the actual examination)

(7) Signature and ultrasonic certification level of examiner making calibration (8) Date calibrated (9) Time of calibration and calibration verification (10) Temperature 'of basic calibration block (11) Length and type of search unit cable (12) Serial number of the thermometer.

7.0 EXAMINATION 7.1 Examination Areas Mechanized ultrasonic examination of nozzle-to~iping butt, welds and ad)acent base material from the inner or outer surface shall be performed.

Examinations shall be performed on components in their completed condition. Weld examinations shall include the weld and base material for 1/2 inch from the fusion line on each side of the weld. The 1/2 inch to be examined shall be measured from the fusion line at the weld crown.

The transfer method shall not be used.

SwRI Form OA3 2

SwRI-NDT-800-78 SOUTHWEST RESEARCH INSTlTUTE Revision 0 December 1981 R NUCLEAR PROJECTS OPERATING PROCEOURE Page 19 of 23 lk 8 0 RECORDING CRITERIA NOTE It is recognized that not all ultrasonic reflectors indicate flaws, since certain metallurgical discontinuities and geometric conditions may produce indications that are not relevant. Included in this category are plate segregates in the heat-affected zone, clad interface, and back~all reflections ~ Plate segregates in the heat-affected zone may become reflective after fabrication; these may appear as spot or line indications when examined using straight" beam longitudinal wave techniques. These indications shall not be considered reportable conditions.

Ultrasonic zeflectors producing a response 50X or greater of the refer-ence level shall be recorded. Ultrasonic planar surface reflectors obtained at 100X or greater of the response from the square notch shall be recorded.

Ultrasonic reflectors detected at 50X or greater of the reference level and planar surface reflectors 100X or greater of the response from the square notch if not resolved as geometry by the examiner, shall require scans to be conducted in the Y direction (width of indication) ~

Scans in the Y direction shall extend to the 20X limits of the rezlector along the X axis and to the 20X limits of the reflector along the Y axis.

Y scan increments shall be one-tenth inch (when incrementing with the SwRI rotator the increments shall be one-half degree) ~ All Y scans shall be run in the same direction, upon completion of which an I-scan shall be run at the maximum amplitude location.

Ultrasonic reflectors producing a response 50X or greater of the refer-ence level and planar surface" reflectors 100X or greater of the response from the square notch shall be investigated by a Level II or a Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector.

Ultrasonic reflectors 50X or greater of the reference level and planar surface reflectors 100X or greater of the response from the square notch, investigated and found to be other than geometrical in nature, shall be reported to the customer for evaluation.

Scanning limitations shall be recorded.

9.0 EVALUATION Evaluation of indications shall be the responsibility of the customer, or the customer's representative, and shall be conducted in accordance with SwRI Form OA 3.2

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SOUTHWEST RESEARCH INSTlTVTE SwRI-NDT-900-7 NUCLEAR PROJECTS Revision 3 March 1981 OPERATlNG PROCEDVRE Page 1 of 9 VISUAL EXAMINATION OF NUCLEAR REACTORS AND APPROVAL 'FFECT1VITY Revision 3 of this procedure became effectiv on ~ . Other revisions of the base document may be effective concurrently.

SA Approvals Written By M 3 Manager of CLA.

Date Date l7gg/

/'ate ant Director

/

Wa

./4'/9'&'at it"fi The following information may be used for convenience. mpletion of this portion is not mandatory.

Deviation No.

Date Effective Procedure Section(s)

Affected Notes:

swnl arm QA~AN

SwRI-NDT-900-7 SOUTHWEST RESEARCH INSTITUTE Revision 3 March 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 9 (2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Prospect Plan.

(3) 'he examiner shall be responsible for implementing the require-ments of this procedure-(4) The Manager of the Support and Administration Section of the Quality Assurance Systems and Engineering Division shall be responsible for storage of records generated in accordance with th'is procedure.

4.0 CODE AND PROCEDURE REQUIREMENTS The requirements listed below shall apply when performing visual exami-nations in accordance with this procedure.

Re uirements Section (1) Personnel certification 5.0 (2) Examination area 7.0 (3) Surface condition and cleaning requirements 6.0 (4) Examination method 6-0 (5) Equipment 5.0 (6) Lighting requirements 6.0 (7) Resolution 6.0 5.0 PERSONNEL AND EQUIPMENT Personnel performing examinations shall be certified in accordance with SwRI NQAP 11-2, "Procedure For Certifying Visual Examination Personnel."

The Visual Examination Acceptability Test Card shall be made from Kodak Neutral Test Card No. R-27 or an equivalent, with an 18X neutral grey side having a 1/32-inch~ide black line down the center.

SwRI Form OA 3 2

SwRI-NDT-900-7 SOUTHWEST RESEARCH INSTITUTE Revision 3 Harch 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 9 Resolution shall be considered adequate when the combination of access, lighting, and angles of vision, either unaided or corrected, can resolve a black line, 1/32-inch~ide, on an 18Z neutral grey card placed on the surface to be examined or in a situation similar to the area to be visually examined.

6.2 VT-2 Examinations The examiner shall locate evidence of leakage from pressure retaining components, or abnormal leakage from components with or ~ithout leakage collection systems as required during system pressure or functional tests.

6-2.1 Noninsulated Com onents The accessible external exposed surfaces of pressure retaining components shall be examined for evidence of leakage.

Examination of the surrounding area, including the floor or equipment located underneath the component, shall be required for components with inaccessible external surfaces 6.2. 2 Insulated Components Examinations may be conducted without the removal of insulation, by examining the accessible exposed surfaces and joints of the insulation.

Vertical surfaces of insulation need to be examined only at the lowest eleva-tion where leakage may be detectable. Horizontal surfaces of insulation shall be examined at each insulation joint.

Inaccessible piping and components shall require an examination for evidence of leakage on the surrounding area, including the floor areas and equipment surfaces located underneath the component, or other areas where leakage may be channeled-Discoloration or residue on surfaces examined shall be given particular attention to detect evidence of boric acid accumulations from borated reactor coolant leakage.

swRI Form OA-3.2

S wRI-NDT-900-7 SOUTHWEST RESEARCH INSTITUTE Revision 3 March 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 9 Pipe clamps and U-bolts shall be examined to ensure that they are securely attached to the pipe.

7.0 Examination 7.1 Surface Cleanin Visual examinations which require c1ean surfaces or decontamina-tion for valid interpretation of results shall be preceded by appropriate cleaning processes.

Examinations may be required where the surface is painted or has other types of coatings. This shall be permitted if it is determined that such coatings do not interfere with valid interpretation of results .

7.2 Examination Areas Components, parts and areas to be examined shall be as specified in the applicable SwRI Examination Plan. Remote visual examinations utilizing mechanized scanning devices shall be as specified in the applicable Scan Plan.

Scanning parameters, if required, for the remote visual examination, shall be included in the applicable SwRI Scan Plan-8 0 RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in IX-FE-116.

Visual abnormalities shall be recorded on the "SwRI Visual Examination Record" and reported to the customer-The completed "SwRI Visual Examination Record" shall contain, but not be limited to, the following information:

(1) Identification of the examined part and the extent of the examina-tion, including surface preparation, if required (2) Method and techniques used in the examination SwAI Form OA.3.2

S W R I VISUAL EXAMINATION RECORD P RO JECT No. SITE DATE: (DAY - MON.- YR.) 4 IRC SHEET No.

EXAM STARTED EXAM ENDED EXAMINATION AREA:(SYSTEM/COMP.) (LINE/SUBASSEMBLY) ( IDENTIFICATION ) Wo LOCATION WELD TYPE: ( FLOW ~ )

EXAMINER SNT LEVEL PROCEDURE METHOD Lo LOCATION No. DIRECT Q REMOTE Q EXAMINER SNT LEVEL REV. DESCRIBE: VISUAL AIDES WELD LENGTH DE V.

LOCATION TYPE SIZE DIA.

IND. No. LOCATION LOCATION ROUND OR OR VT-IP VT-2 Q VT-SQ VT-40 IN I.

STREAM LINEAR LENGTH REMARKS

+ CA to I

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CO EXAMINATION AREA LIMITATION ( IF NONE SO STATE) I

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REVIEWED BY SNT LEVEL DATE PAGE swan ronu wo. ooro >r- as I oav. or- io-so)

APPENDIX E ULTRASONIC CALIBRATION BLOCK DRAWINGS AND CERTIPICATIONS

APPENDIX E ULTRASONIC CALIBRATION BLOCK DRAWINGS AND CERTIFICATIONS Table of Contents Drawin No. Title ~Pa e-

• UT-1 Upper Shell Block E-1

• UT-2 Lower and Intermediate Shell Block E-2

• UT-4 Bottom Head and Outlet Nozzle Safe End Block E-3

• UT-5 Inlet Nozzle Safe End Block E-4

• UT-6 3-1/2" Thick Primary Piping Block Assembly E-5

• UT-8 Vessel Flange and Ligament Block E-6

• UT-9 Inlet Nozzle Block

• UT-10 Outlet Nozzle Block E-8 5-CSCL-40-SLC Block Standard E-9 IR-CSCL-66-SLC Inlet and Outlet Nozzle Inner Radius E-15

• FPL Furnished Blocks (Certifications On Site)

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g NOM 2/I I TTP 5CA LE TUPICAL 3 PLACES 1)I I

SNIPE OI'&CE 04 RASE NEfAL I ~

CUT TO RtCEIYE C(ADOW& 1$ I I OP'fl&NAL,IUIRRI Allot OMITS L ORNL E REAM ~ 3l'15 <<,00\

S MIN 3 llOLES raa-<03

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+"

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I IR ~ CSCL SLC IET. 2I8993 0 I R E. ( T 10 N 1)R 4(a R IR-CSCL ('06- SLC OOE

'4 I (NTNIC ETE SCIM\l(R CMR s0(4121 C Ql MlllRIIL 14(KIRI( (f Ns1 llssNIR UNs(ATIIN TRS(N MAY I I OLOCK C 3 NOTES'SO All'E(.T AN@It R(AM CR SIRAICRT EtAM CAU&RATIONS.

INIE flNM CASUS CLE rKAT Ns ZR3533 S RE (44 Rs.1&$ 0 ro ~ (,010 STCEL SIIHP Ek Ns ARO IRAI Ils SARAN Ol NIRfA(E UN(CA(CO ~o

~ 4 I/If( SOVIHWEST RESEARCH INST(IUI QS SH CHARACTtR'5 3/I( IWNIMUM Ikl&HT ~ rsrl rosrrl r ~ lllos rolrrirr wN 'r r rroo Qo AsssR (Ass& RADN f(RSH 10 CON(044 s/OosN 4 NMA(sot IIA'ISIRIA(CS RASH ~

((AOOTIRIAT Pl N(OKAN(t IRIN 5<<RT. PROCt0444 TIPS 540'4 Rll ~, I L QS lftfEfls INNER RADIUS D(RUHR ANO RREAR SHARP EOCES ~ I orr r I OSMENSNIHL ARC IH RICHES

~ lI os r rr r RAM

'll C D-n073 II8

LINDBERG/COOK HEAT TREATING COMPANY CORPORATION p.o. Oox paaao ~ Ttovrrort. T ax As yrot o ~ ltor anaaot CERTIFICATION OF HEAT TREATMENT DATE:

SOUTHWEST RESEATKZ ZNSTZTUT P 0 DRAWER 28510 CERTIFICATION NO

~ SAN ANTONZO r TEXAS 78284 ATTN JZH SILVERS OTHER ORDER NOS.:

wt >>tttlv alivv oixr ne Txstt oltt>>sto writ olvoi ne Tollowvvo>>txl lit>>lie>>n twe xt rexf NUMBER OF PARTS:

PART NUMBERS:

993 6 X 8 X 15 JOB 14141 DRAWN 12 0 SPM. ttQ rtlttttDED ospCY sar STRESS ttSUStrED We further rettily that heat treatment ite>>crlbeil aT>>ive i>> true anil airrert anil that ti m peratures and test resuhs were ohtaineil with ctanitar<l apprnveil mi thi>>t>>.

Suhscritwit amt sworn to beiore me this Lssetsscstarcooss stmAT vteEATtsea cosepAsev

~I521 Itsy ill , 19~

Notary Public in anil inr the nunty of Marti ate iit Texa>>

PAms GAMBLE My Commission E'xpires 4 PLANT SUPERZNTENDENT E-17

Biyhap machine. 5 Teel Ce. Inc.

-1 3-gUALITY CONTROL INSPECTION REPORT Contract No.: Item P/H - 0 HSH Acc Rej Acc Ref Acc ReS 16 31 17 32 18 33 19 20 35 21 36 22 37 23 24 39 10 25 40 26 41 12 27 42 13 2S 14 29 44 15 30 45 Tolerances on Dimensions Number and Types of Defects Found:

(unless otherwise specified)

Fractions B 0.

.X Corrective Action Taken:

Pt Be

.XX LCQ

.XXX Number of Samples LOT: ACCEPTEO Number ACCEPTEO REJECTED ~

Number REJECTFD Signed Date I

nag. g~

E-19

Pebruary 8, 1982 MEMORANDUM TO ~ Pro)ect Pile 17-6787-721 (St. Lucia Inner Radius Block)

PROM:

Manager, Melding Research and Development

SUBJECT:

Post Veld Heat Treatment of Inner Radius UT Calibration Block IR-CSCL-66-SLC, Draving No. ~073-118 The above block received a post veld heat treatment at 1150'P, -25'or a period of 4-1/2 hours. This is a verification that the block received the post veld heat treatment in accordance wiht Article IV,Section V, paragraph T-434.1.3 of the ASME Boiler and Pressure Vessel Code.

/ga E-21

( I I

I I

I I

MCTIOIV A.A SCALE Z/I g NOM TT I'/O see(pc CUT TO ION R I/Z Ill(R.

.OEM'~

SCALE Z/I TYPICAL 3 PLACCS of coot (p des% NCML P(KKIVC CIA(DINO 1$

I I

II.AA I

I I

DIR'ECTION I ~

I t

OPTIONAL ION(PI AMVC OMITS L d MIN ORI(L t 3 IIOLESe REAM .Ve IS 3 OOS rm-cQa

+-

OIRKC;TION 4.IES

'SO QS QV OIR E.C.T ION O3Z~ Z HIIIRNL TOR( IPII Cf ANV IAWNAR Pde(A(eSN VWOI HAY Alftl1 AN(IK d(AH OR eeIRAICPT d(AM VLIORATIONS,

. UICC (NAI SASOO CLC.VKAI Re. CIOSSS QS j

S a( ul ~ .IASO STC(L SCRAP ($ R. AAO NIAT Nt SPOON ON Wl(A(E PIHCATCO Ij(gR I)R I

tSO IR- (SCL SLC HT. 218993

~t w

~e e I,OI 0 I/I(g I

I (RTIAG EVE I DLOCK IR-C'5CL-(46 SLC ALHASTIR CARR P SO(A(Ply SOUTNWCST C 3 ECStAKCN (NSIIIUI C

IN cNARACTtR'S 3/IC MINIMUM NXIONT Aeeeee eewwe lelelel w Iewlw (wee ewe Qe) eeee4 (ceo RAPU RUIN Io cohi(RR e/oveN C IN(hdel I(AI IAIIMls flssN, Qs (uo ovlplAv pl K((woAN(c (Alee s RE IRD(toodt Nps soo't plv I. dna 4 II f(TK(C(ee I INNER RADIUS l Plhlhld ANO IVRKAK SHARP tOOC'S, we ~ ~

I OeHINSIONS ARK Ni UKNKS el ~ 0 (IC6 RAM ""'I/

NOTES' ~e ~ ew e ~e C 0 1073 II6

LINDB ERG/COOK HEAT TREATING COMPANY CORPORATION P,O. 0OX 14040 ~ KOL/STO//<<TfXAS 75051 ~ Sta/4114401 CERTIFICATION OF HEAT TREATMENT DATE:

SOUTHWEST RESEMK2f ZNSTZTOT~

P 0 DEQRER 28510 CERTIFICATION NO

~ SIT ANTONZOr TEXAS '78284 r PZTH iTZM SZLVERS OTHER ORDER NOS.:

wt <<e<<ts<<ct<<lv<<n<<LL ne LLL<<5 ntsD<<L<<o wt<<t 0<</ran ne <<0<<Lowi<<<<o <<e>>f L<<l<<r<<<<r<<<<t NUMBER OF PARTS:

PART NUMBERS'93 6 X 8 X 15 JOB 14141 PREHEAT OUENCHED DRAWN 290 s<<TERLAL SPB:. NQ 815IZ C /5'9 O <<P STRESS REVS/ED 'f

~ ~

HARDNESS TEST We (urther rerti(y that heat trestmeot <<le>>er(he<><<L<<e i>> true En<<i <<L<<rrrrt anil that trm 15 perature>> and test results were <<<<h(a(ne<<I with stander<<l appnwe<<1 m<< th<<<<<<(s.

Suhserihrd an<<<<<<worn to br(ore me this nsseDnxs<<4/coost seKAT Ts>>DATtKO COseNKT

~2E <<lay ii(. .

19'otary Puh(ie (n anil h<<r the ounty of Harri ate ot Tcxa<<<<

Ny Commission Eipires 4 E-17

Qi>hap machine O'eel Ca. Inc.

EQUALITY COHTROL IHSPECTIOH REPORT Contract Ho.: 0 Item P/H - d / C(l, Acc Rej Acc Ref Acc Ref 16 31 17 32 18 33 19 34 20 35 21 36 22 37 23 24 39 25 40 26 41 12 27 . 42 28 43 14 29 15 30 Tolerances on Dimensions Humber and Types of Defects Found:

(unless othe ise specified)

..'.-,z R O~

.X 8~

Corrective Action Taken:

Po

.XX Lco

.XXX Humber of Samples LOT: ACCEPTED Number ACCEPTED REJECTED ~

Humber REJECTED Signed Date I 7

E-19

Pebruary 8, 1982 MEMORANDUM TO: Pro)ect Pile 17-6787-721 (Bc. L cla l ac Baddaa Black)

FROM:

Manager, Welding Research and Developnent

SUBJECT:

Post Weld Heat Treatnent of Inner Radius UT Calibration Block IR-CSCL-66-SLC, Drawing No. D-4073-118 The above block received a post weld heat treatment at 1150'F, -25'or a period of 4-1/2 hours. This is a verification that the block received the post weld heat treatttent in accordance wiht Article IV,Section V, paragraph T-434.1.3 of the ASME Boiler and Pressure Vessel Code.

/ga E-21

APPENDIX E ULTRASONIC CALIBRATION BLOCK DRAWINGS AND CERTIFICATIONS

APPENDIX E ULTRASONIC CALIBRATION BLOCK DRAWINGS AND CERTIFICATIONS Table of Contents D rawin No. Title ~Pa e

• UT-1 Upper Shell Block E-1

• UT-2 Lower and Intermediate Shell Block E-2 I

• UT-4 Bottom Head and Outlet Nozzle Safe End Block E-3

• UT-5 Inlet Nozzle Safe End Block E-4

• UT-6 3-1/2" Thick Primary Piping Block Assembly

• UT-8 Vessel Flange and Ligament Block E-6

• UT-9 Inlet Nozzle Block E-7

• UT-10 Outlet Nozzle Block E-8 5-CSCL-40-SLC Block Standard E-9 IR-CSCL-66-SLC Inlet and Outlet Nozzle Inner Radius E-15

• FPL Furnished Blocks (Certifications On Site)

SCRlOT LINC TVP

$ GROOYC

~ASS 00 NOV USC ~ TTP DOTN SIOCS r-+-a I I I I I I 1 I I

1

-I I

I/I III I I I I GROOVC TVLL RADIUS P RALN 'CND NOT t OG R SICIL STAIOO Tlt IOCCONihG evelwIVV ACT Ql 1111 + UN 1ViV CVAAACTCAS

~ 'I CNIIIATIOV 110 UT I C001 VI M COO I CO%COACT Nl. T lilt TellwLTOIATMINT T VR'L eelle ep TAOCC TNICQNCSS N

~ O)0 OIA R 4 0TTP OTTP WCIGNC Ii)ll G IIOI Oh OASC UCTAL UNC Sg CrROOVC ICCO tICP TVP CAISTIND CLAD

)

~ SCR10C VNC COCATCO ON N01.%$ ANO CDGC OC GROOVCS Og f OCI'WCe C TIIT? ~ I ~ 1 OOT I ncr COUDUSIVel TNCINtCPViG

/~

l

I eeAX R TTP~

AIL J ROUND A 1 ACR 0 TTP ~ CIO GROOVC ttt1 TTP 504110 SOUIHWI55 OC Sf ATCN IN5IIIUII

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n gl

~P HI tlat& ~ ~ tH ~ ~ ~ ~ IM ~ I 0- 683 I C'33 s

FULL RADIP5 fACH ENO TTP DRILL f. (.57$ 0) Dlh TAP I-0 UNC t8 x I MAX DffP SCRlbf LINf LOCATED EOCE Or CRODTES ON f Or HolfS g A A I

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~LOS DO NOT USE 87@ALT TYP. 80TH SIDES tl '-*

DRILL g (.tSOO) DIA A 3 DEEP 6 HOLES REF

.IIO

>>OQ NOTES:

I. DEMRR o BREAK SHARP EDCES WITH APPROX Qg RADIUS DR CHAtfrfR

2. THE CAITBRATION BLOCK MATERIAL SHALL bf CttfFLETELT EXAtllNED WITH A STRAICHT BEAtl SEARCH UNIT. AREAS WHICH CONTAIN LAMINAR INOICATIOH5 EXCEEDINC OAClf REFLfCIIOR AT THf INDICATION THE'ftlhlNINC tOSITIDN SNAII Of EXCIUDED Fhotf TNF Ofhtf PATH5 NEEDED 70 AfhCN THf VARIOUS CALISRATION HOLES.

QZ57EEL STAMP THE FOLLOWINC INFORtfhTION WITH $$ REF

>nc IYIN RICH CHAIMCTERS:I UT CAIIORAIION 010 VT COOf NO. tf-604;I t Rfrf FPL DWC E-THTt -Ifl-003 CONTRACT NO. 7H72 PC ITC-310)

THERtlhL TREATMENT 2 HRS BLOCK 7HICHNE55 $ cflies

'WEI6MT ICD w 2 I I.IFT ETE HfAI'REATtffHT TIKE SHALL BE TWO HOURS I I CAL BLOCK AT IISO'$ F OYER ANO ABOVE PRESENT HEAT ~ Ncaa>>N ~ e>>LI ~ o>>efl ~ ~ at>>

I ella tae ~ >>ael >>ac I OQL I

~

TAEATtlfHT. ROUCH CUT 70 5ltf T HEAT TAEATT AND ~ le>>we ITIC 64+ OOOTO LIO'f

~ eacf feel FINAL MACHIHf. +0 30 ~ I ~ f OTN>>ea>> ~

RESEARCH INSTITUTE a>>eccl SOUTHWEST THIS IS NOT A FAORICATION ORAWINC. t fell>> Oflll!TT JTTffclffCC TfITI>>T I>>O ICCTOCCITIC CCTTTTOk REPRODUCED FOR SITE USE OHLT. II>> a>>clef ~ ~ Ilal LVCIE Z

~ ttae Tl ~

T.O.O. OOTII ST BOTTOM HEAD (

Bw OUTLET NOZZLE SAFE END BLOCK TKctf al >>af N of>>lee>>l Nof>>co N co>>Teacf TKTI Nae>>N

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Lcl ~ c ~ oa oaf l c>>e oN>>. a>>e tell. TNO ~ o fae1.

h'h S OWCT

""'y< (o f Oal OE7

STEEL STQISP THE FOILOWINC INFDRIIATIOk WITH I~ PHN MICH CHARACTERS tIT ChtlbRATIPN STD UT-5 COPf HD. PI- IIZOT CONTRACT NO. 7IO72 THERIIAL TREATPIENT C Jrt ZHR5 IIIN BLOCH THINNESS 3$

WEICHT ID7 tbS Cl APPINC .070 6hOOVf DEPTH

.070 CROOVE DEPTH DRILL iIC (.IOTS) DIA L HOLES Ib+TT to It 11 III II 3+f.

I 11 HOTESI Il I. PEPORR E BRIAR SHARP EPCES MITH AFCROT I 11 HZ RAPIDS OR CRANER.

bf

2. THf ChtlhRATIOH IOHPlfrllY BLOCH ISATEAIAL SHALL EIAIIIHEP MTH A STRAICHI SEARCH DMT. AREA5 SIHJCH CONTAIN

¹II Fbtt RAPIDS EACH EHD LAIINAR IHPICAVIPNS ETCffPINC THE ~ rvr RftIAININ6 BACH RfflfCTIPN AT TOE I IHPIchrlO>> F05ITIPN sbhtt bf txCLDPED 2 4 IT FROII THE BEAII PATHS HEEDED TO RfACH THE YARIPIIS CALIBRATION HOlES ~

3. HEAT TREATIIEHT THSE )HALL BE TVP (2)

HOURS IIIN AT IISD 25 F OVER iWD ABOVE PRESENT HEAT TREATPIENT 5CAIBE LIHf LOCATEO ON $ OF HOLES g DRILI.

g (.57$ 0) DIA EOCE OF CROOVES TAII I-0 IINC-ZB 2 I" IIAX DEEP AEFt FFL DSPO 7/07 70 -002 ISSY Nt. 755-ZII) 2 I EYE BOLT I I CAL BLII Rac<<IKR Kata ~ wff~ ~ a<<I <<I tel T <<a<<t <<IICOIL

+ .OIO ~I acR

~ IIMaao

~ slcfaaea 2 trST tlsTS LIST seato +0 30 I f aoaawa<<

~ ~ ~

SOUTHNEST RESEARCH INSTITUTE 44CLTSS JSSSSSSCC S'IS'TSSS NO SSCIICSSMC OITTSIOS

~ III t.l.l. Ollll Ca1 lll41I~ 'Ilail ST LUCIE 2 tatltl ll <<af K KKaeOl IIIIIKIlf CtaIIICT TKN RaeIKI

~ ao oc<<I<<II<<aa aat Iat taatl ~ If ct IRIwtlfKKIK<< M I <<I<< ~ III 3 4 UT- 6 THICK PRINRY PIPIIIC IILOCK hbST

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Ltl ~ C1 W Oaf l Cea ~ IR Wa till<<R os Ws CMCal ~ ~ I RN SI YZ Q-683I OM IISVISIONS CTa Ct /rat ra

) og TE-IO QT vJ SC IA ) RIE Ip RQ STC CL ')TAMP TRt ICLLORINO AIORll))ION VIIIII Lrl) MPI RMI I

CA R AC T I 4)

OT CALIRRAllON )TDDI CO)I III M. AIIC, I COATRACT Rl 1H1t 1AIRMAL TRC AIMtNT C AA) MH WCIORT tllbO DACLTIO CI.ADO Hd vvAV v ~

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f]3791-1 li8 3666]I GR>>12]I69-SR 12~6 tEClflCATIONSS C.E,SPC'c. P3F12(C) 9/25/67 SA+33-65 Gr.3 Claaa 1, AS]IF, Sec.3 Claaa A Pbx. 80000 NMD Irlr OAKS ZI 4 MIGINrirrnil OSI(. Contour Q16+LP, JOD~i0858 CHEMICAL ANALYSIS AIELI NO. 1AM cv CI MD AI 5312 Slab 2 22 21 1.26 1,26 ll 016 016 18 20 5]I 52 5]I 5II P.ILV.r.P.Sta Blab 1 23 1428.

09 009 016 19'2 52 PHYSIC AL PROPERTIES MELT NO.

NA4 ISO.

rlISO III 1100 IINIAI III 1 100 II IIDND 2r 54 ~ IIIN I MrAcr5 DESCRIPTION 835 1 219 x 1Cf x 11 13/16" 601 823 30 Silo 610 8]IO r

'cata heate ot hc df]h a ~ Tna ~ an progTI ala coqlcd er C.E. Co 1650'tc:ql for, 1 -13/1 Qaop ate. Then tcrnpcqed

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'.oolcd 100'!.

alicvcd 109 P p

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APPENDIX F EXAMINATION AREA LIMITATIONS FOR THE ST. LUCIE PLANT, UNIT 2, REACTOR PRESSURE VESSEL

APPENDIX F EXAMINATION AREA LIMITATIONS FOR THE ST ~ LUCIE PLANT, UNIT 2, REACTOR PRESSURE VESSEL

l. Introduction Limitations to examination coverage were experienced during the mechanized PSI of the St. Lucie Plant, Unit 2, RPV and are generically identified in the Examination Summary Table of this Final Report. The purpose of this appendix is to further define and quantify the examination limitations as specified in U.S. Nuclear, Regulatory Guide 1.150 and as requested by FPL.

Two generic types of limitations were encountered most frequently during the PSI of the St. Lucie Plant, Unit 2, RPV welds and components:

(1) Interference from search unit wedge-to-component near surface interface noise, and (2) Component geometric interference with the scanning equipment and/or geometric shadowing of examination areas.

SwRI procedures implemented during the St. Lucie RPV exami-nations required full vee path calibration of the 45-degree shear wave scans to compensate for limitations encountered in the near surface and those due to geometric shadowing. Additionally, manual scans were con-ducted from the outside surface of the RPV (where accessible) to comple-ment the inside surface examination coverage. Nevertheless, those examination volumes which received other than 100 percent of the ASME Code-required coverage are identified herein. Generally, interface noise inhibited resolution capabilities at the. near surface for about 1/2 inch to 2 inches .of metal path for longitudinal wave examinations. It should be noted that electronic gating did not result in any examination limita-tions since the entire instrument screen presentation was monitored during the examinations, video taped, and reviewed independently following the examinations-

2. Descri tion of Limitations The attached tables and figures detail the examination limitations experienced during the St. Lucie Unit 2 RPV PSI. Specifically, the tables quantify the limitations in terms of percent of Code-required examination volume which was not effectively covered. The accompanying figures graphi-cally depict the location and extent of the limitations with respect to weld metal and associated base material.

/

2.1 RPV Lower Head Welds No limitations were experienced during examination of the Lower Head Dollar Plate Weld 101-151.

shows the limitations to the shell side examination and depicts the cover-age obtained from the seal surface examination. Also shown is the tapered surface where transverse examination was prohibited.

2.3 RPV Lon itudinal Shell Welds The examinations of the Lower Shell Vertical Welds 101-142A, B, and C were limited due to near surface interface noise. Those volumes shadowed by the interface noise were effectively examined with the 45-degree full vee path scans, except for a small area of interference from the core barrel anti-rotation lugs in the case of Welds 101-142B and C. Figure 9 shows the limitation of the 45"degree vee path examina-tion. The examination of Weld 101-142C was also limited due to inter-ference of the surveillance capsules. This volume was effectively examined by the 45-degree full vee path beam. The 0- and 60-degree beam limitations are shown on Figure 10. Transverse examinations were not

'imited by the lugs or capsules.

Examination of the Middle Shell Vertical Welds 101-124A, B, and C were limited by near surface interface noise in the case of'0- and 60-degree beams, however the 45-degree full vee path scans obtained full coverage. The 60-degree examination of Weld 101-124C was further limited by interference from the surveillance capsules as shown on Figure 10.

Examination of the Upper Shell Vertical Welds 101-122A and C were limited by interference from the inlet nozzle inner radius blend and the outlet nozzle integral extension as shown on Figure ll. The examina-tions were, however, complemented by the nozzle-to-shell weld examina-tions. Figure 12 shows 45-degree full vee path coverage of the volumes not effectively examined by 0 and 60 degrees due to near surface interface noise.

2.4 Nozzle-to-Shell Weld Examinations The inlet and outlet nozzle-to-shell welds were examined from the shell side and from the nozzle bore. The nozzle bore examinations were limited due to near surface interface noise, however, surface wave examinations were performed on the nozzle inner radius sections. The shell side transverse examinations of the outlet nozzleswere limited due to interference from the nozzle integral extensions. Limitations to the inlet nozzle examinations are shown on Figure 13 and limitations to the outlet nozzle examinations are shown on Figure 14.

3. Conclusions Limitations to effective coverage of ASME Code-required examination volumes were experienced during the St. Lucie Unit 2 RPV preservice exam-inations and are identified in the figures and table provided in this appendix- The limitations were minimized 'to the maximum extent possible.

Future equipment and technique development may further reduce limitations to inservice examinations.

F-3

TABLE 1. RPV EXAMINATION LIMITATIONS (Cont'd)

Exam Percent of Volume Figure Weld No. ~An le Not Effectivel Examined Ne.

101-142B pO ~

24 9 5 9 45'0'5'T 12 9 0 N/A 60'T 12 N/A Combined Coverage* 0 N/A 101-142C pO 24 N/A 45'p0 6 9 12 9 and 10 45'T 0 N/A 60 T 12 N/A Combined Coverage* 0 N/A 101-124A pO 24 N/A 45'0 0 N/A 12 N/A 45 T 0 N/A 60'T 12 N/A Combined Coverage* 0 N/A 101-124B pO ~

24 N/A 0 N/A 45'0'5'T 12 N/A 0 N/A 60'T 12 N/A Combined Coverage+ 0 N/A 101-124C pO 24 N/A 0 N/A 45'0'5'T 12 N/A 1 10 60'T 12 N/A Combined Coverage* 0 N/A 101-122A pO 19 11 and 12 1 11 and 12 45'0'5'T 18 ll and 12 12 0

60'T 17 12 Combined Coverage* 0 N/A

• Combined Coverage indicates the percent of Code~equired volume not effectively covered by at least one calibrated beam.

F-5

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L'o'->il nREA t.lan'te old 0 QLAQ

- hKKA LIMITED ST. LUCIE UNIT 2 MERIDIONhl WHLDS 101-154h THRU F (TYPICAL)

CROSS SECTION VIEW FROM TOP OF VESSEL TYPE EXAH PARALLEL FIGURE 1

ToP oP VE'SSfl ul'VERY air oF Er8~ aRFA QI~I co<wits OPPER U<>l oF FL<gu<NM'T IMTERFEREAkE lo~ cnmroc ENO9 AREAL iSSn c users CAd6R UWI7 oF ~tJMZ Fisc s'riRt IVKRFERMC 3900 ST. 1.UCII: llNIT 2 gl ws so'rz~n-svzzsz

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CROSS SECTION VIEW ELEVATION

= -4~'mdksVEEsE TYPE EXAM - TRANSVERSE

, G'/ OE6XE85'oue 1" FIGURE 2

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l50 I lO A I O>> 0'10'7O 300'.

330'60'ss St.so CS 1o <so.to' te. < o'CC1f <lt S t1111 AVSII gn t<'>>S.S'to t As<P lot<ST< ~ O LvC (C Ca.)

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EVE<

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QESSEL wcwb LOWER HEAD LOV/ER SHELL ST. LUCIE UNIT 2 CIRCUMFERENTIAL WELD 201-141 EXAM TYPE PARALLEL CROSS SECTION VIEW FIGURE 4

TOP OF VE55CL I

AREAS OF NO EXAMINATION DUE TO SURVEILLANCE SPECD1EN CAPSULES 0'20'ISTANCE IS

'6.22' l039'QUAL I80'"to'56.57f0JQ'T.

TO FULL EXAMINATION VOLUME LUCIE UNIT 2 CIRCUMFERENTIAL MELD - 101<<171 EXAM TYPE PARALLEL PLAN VIEW FIGURE 5

25778 cooAT'5

): 78 l3 ~amma g t5 7 LimnÃrleTPY'<ow5 ST LUCIE UNIT 2 CIRCUMFERENTIAL WELD 101-171 E)QQ1 TYPE TRANSVERSE AREAS OF LIMITATIONS (TYPICAL)

FIGURE 6

pl lilt MELO

//// 6O'INlTPsTSOS>~

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MIDDLE SHI SL ST. LUCIE UNIT 2 CIRCUMFERENTIAL MELD 106-121 EXAM TYPE PARALLEL CROSS SECTION UIEM FIGURE 7

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gp'>i(i r'ararrraas gP )It I C

ST. LUCIE UNIT 2 LOWER SHELLrVERTICAl. WELDS 101 llt28 & C No o E.zhm LIMITATIONS DUE TO LUGS E)UQ1 TYPE PARALLEL K3 HD CO'yAHI (TOP VIEW SECTION) tJ0 45 EgA%

po FIGURE 9

fttl 0 8

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o'.s'lQl l (yQ 10,1~ 1~ QQ g. 7o ST. LUCIE UNIT 2 VERTICAI WELDS 101-12liC & 101 142C EXAM TYPE - PARALLEL AREAS OF LIMITATIONS DUE TO SURVEILLANCE SPECIMEN CAPSULES FIGURE 10

~TOP OF gh5SKL 1'i.s s'r Pc t.z,u 4TLAT MOZZ.Lf QcEaD liAoS

~ aal a,iwsib pr iS I l&N.s) J1 (IIL s )

5414L Scar tll narn os Ll41TATioPS ST. LUCIE VNIT 2 VERTIChL MELD 101-122A PLhN VIEW FIGURE ll

TDP 0F VESSEL v v

$ ghd L'$

~ v gga4 9$ V Il

$ goal W

Ib M'

l) 4 QJJ= 0 LwiT~T$od ST. LUCIE UNIT 2 H- = QO L<e>Th>>os VERTICAL WHLDS 101-122A, 101-1228 and 101-122C CROSS SECTION VEXW FIGURE 12

.j 1[

hREh hF SURFACE.

VfhVE E.VAN g]-/5 Rl FROM BORE ST. LUCIE UNIT 2 INLET NOZZLE g-45'FFPO81 cBORE AREAS OF LIMITATIONS FIGURE 13

ARFA OP'gg~t-gyp wee Eynz g-45 T COPlPVTER SCA/VS g-/5 Rl FROPI BORE ST. LUCIE UNIT 2

[9-w~ /EO+ BozE OUTLET NOZZLES

-hREhS Oti LIHITATIONS rrGURE 14