ML19274E501

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Automated Ultrasonic Examination Procedures for Reactor Vessel Nozzle Welds
ML19274E501
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 11/03/1978
From:
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML19274E499 List:
References
80A0470, 80A470, NUDOCS 7903290018
Download: ML19274E501 (33)
v • d • e


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PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 1

0F 33 AUTOMATED ULTRASONIC EXAMINATION PROCEDURES FOR REACTOR VESSEL N0ZZLE WELDS I.i

.k LONG ISLAND LIGHTING COMPANY SHOREHAll NUCLEAR POWER STATION i

2 I-30 '26 Prep'd by DATE NES A

I' 3 -73 Project M DATE REV. NO.

DATE NES 2

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/*78 Mgr IS Level lil DATE O

2-I-78 NES jm

/-y/-7Q IST Progligr Level lli DATE

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!'3/~78 NES QA Mgr.

DATE LiLCO N.

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'DATE DATE 7 9 0 3 2 9.0 0 lf n

4, flUCLEAR Et1ERGY SERVICES, INC.

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PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE VELDS

- PAGE 2 0F 33 s

, RECORD OF REVISIONS Prep'd Rev.

Reason By App'd By No.

Date Description LILCO Comments, CFA 567 f NES LILCO 1

11-78 Revise:

5.6 & 5.6.1-5.6.5

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Table 1 13-314A thru K to 13-314A thru H, J, K and (t!2A thrt K) to (N2A thru H, J, K).

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Add:

2.3(2) manual No.80A1035 2.'3 (3) manual No. 85A096 7.5.3 (1) the word " check"

7. 5.4 (2) the word " check" 7.5. 5 (1) the word " check" 8.1.l(3) "In the 0

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straight beam...

calibration."

8. 2. l (3) " Verify that all poirits on the sweepline are within plus or minus 5% of the full equalizec response sweepline."
8. 2. 2 (1)

... and horizontal positions."

8.2.2(2)

...and the horizontal displacement is within the required plus or minus 5%."

9.1.1 "..., Appendix D, Table 2 Delete:

8.1.l(3)

... entire (0-8 horizontal divisions)."

e NUCLEAR ENERGY SERVICES, IrlC.

p' 1

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 3 0F 33 AUTOMATED ULTRASONIC EXAMINATION PROCEDURES FOR REACTOR VESSEL N0ZZLE WELDS

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1.0 SCOPE 1.1 Area of Examination

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w This document covers the automated ultrasonic examination procedures for the following Reactor Pressure Vessel (RPV) nozzle welds:

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(1)

Feedwater (N4) Nozzle to RPV Weld.

(2)

Recirculation inlet (N2) Nozzle to RPV Weld.

(3)

Recirculation Outlet (NI) Nozzle to RPV Weld.

(4)

Core Spray (NS) Nozzle to RPV Weld.

1.2 Type ;f Examination 1.2.1 Volumetric examination shall be performed using ultrasonic 0

pulse echo nomi'al 450 angle beam shear wave and 0 straight beam techniques.pplied to the outside surfaces of the Reactor Pressure Vessel Shell.

1.2.2 Examinations shall be pedormed using a semi-automatic nozzle scanning device in conjunction with fixed length water column transducer assemblies (sleds).

1.3 Time of Examination

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These procedures shall govern the preservice examination and re-examination of repaired areas of the RPV nozzle welds as required by the ASME Boiler and Pressure Vessel Code,Section XI.

1.4 Weld Configuration 1.4.1 The RPV to Feedwater and RPV to Core Spray nozzle welds have a nominal thickness of 5-7/8" (minimum of 5-3/8").

1.4.2 The RPV to Recirc. Inlet and Outlet nozzle welds have a nominal thickness of 6-7/8" (minimum of 6-3/8").

1.4.3 Typical RPV nozzle configurations and nominal weld thicknes".es are shown in Figures 1, 2, 3 and 4.

MJCLEAR ENEMCY SERVN"ESJNC.

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS

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PAGE 4 0F JJ

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1.5 Materials The RPV nozzles are constructed of low ca. bon steel. The RPV is cladded with 5/16" stainless steel cladding on the ID surfaces.

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2.0 REFERENCES

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2.1 Reference Documents

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The following documents form a part of this examination procedure:

(1) ASME Boiler and Pressure Vessel Code,Section XI, 1971 Edition and the Summer of 1972 Addenda.

(2) ASME Boiler and Pressure Vessel Code, Section til, 1971 Edition and the Summer of 1972 Addenda.

(3) ASNT Recommended Practice, SNT-TC-1A, Supplement C,

. Third Edition (1971).,

(4)

ConAm Procedure for Certifying inspection Personnel, CUTP-1, Rev. 4, September, 1975 (5)

ConAm Procedure for Ultrasonic Instrument Linearity Verification, 25-PS-002, Rev. 2, November, 1975 2.2 Applicable Drawings The following component drawings are part of this procedure:

(1)

CE Assembly Dwg. E-234-245 (2)

CE Assembly Dwg. E-234-470 2.3 Operational Manuals The following manuals shall be available to personnel performing examinations to this procedure:

(1)

Nuclear Reflectoscope, Data Acquisition and

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Control System, 854100-1, Operating and Maintenance Manual, No. TM-73-14N, Rev. O, November, 1973 (2)

BWR Nozzle and Pipe Scanner, Operating and Maintenance Manual No. 80A1035.

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NUCLEAR ENERGY SERVICE 1p+C

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 4 0F 33 1.5 Materials The RPV nozzles are constructed of low carbon steel.

The RPV is cladded with 5/16" stainless steel cladding on the ID surfaces.

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2.0 REFERENCES

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._).V 2.I Reference Documents

.< 7 1 The following documents form a part of this examination procedure:

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(1) ASME Boiler and Pressure Vessel Code,Section XI, 1971 Edition and the Summer of 1972 Addenda.

(2)

ASME Boiler and Pressure Vessel Code, Section Ill, 1971 Edition and the Summer of 1972 Addenda.

(3) ASNT Recommended Practice, SNT-TC-1A, Supplement C, Third Edition (1971).

(4)

ConAm Procedure for Certifying Inspection Personnel, CUTP-1, Rev. 4, September, 1975 (5)

ConAm Procedure for Ultrasonic Instrument Linearity Verification, 25-PS-002, Rev. 2, November, 1975 2.2 Applicable Drawings The following component drawings are part of this procedure:

(1)

CE Assembly Dwg. E-234-245 (2)

CE Assembly Dwg. E-234-470 2.3 operational Manuals The following manuals shall be available to personnel performing examinations to this procedure:

(1)

Nuclear Reflectoscope, Data Acquisition and

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Control System, 854100-1, operating and Maintenance Manual, No. TM-73-14N, Rev. O, November, 1973 (2)

BWR Nozzle and Pipe Scanner, Operating and liaintenance Manual No. 80A1035.

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NUCLEAR ENERGY SERVICES DdC

s PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 5 0F 33 (3)

Data Analysis System, instruction Manual No. 85A096.

2$i 3.0 PROCEDURE CERTIFICATION The examination procedures described in this document comply with Section XI of the ASME Boiler and Pressure Vessel Code, 1971 Edition including Summer 1972 Addenda, except where examination coverage is limited by part geometry or access.

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4.0 PERSONNEL CERTIFICATION

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'4.1 Personnel Certification Requirements

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4.1.1 Each person performing ultrasonic examination governed by this procedure shall be certified in accordance with the References 2.1 (1), 2.1 (3) and 2.1 (4).

4.1.2 An examination crew shall consist of three or.more members']

as needed. At least one member of each crew shall have a minimum qualification of Level ll in accordance with the

____above referenced documents.

The remaining member (s) shall _., _ _

consist of one with a minimum qualification of Level I and a mechanical / electronic technician.

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4.2 Personnel Records 4.2.1 Records of personnel qualification shall be maintained by Examination Contractor.

4.2.2 A copy of the examiner's certification summary and a current eye test as required by SNT-TC-1A shall be filed with each permanent examination record, with a copy submitted to the plant owner or his agent, prior to performing examination per this procedure.

50 EXAMINATION REQUIREMENTS

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51 Examination Frequency 5.1.1 The nominal examination frequency shall be 2.25 MHz for all straight beam and angle beam examinations.

5.1.2 During preservice examination, other pulse frequencies shall be used only if such variables as material attenu-ation, grain structure, etc., necessitate their use to achieve penetration or resolution. This information shall be recorded on the data sheets.

  • Later NUCLEAR ENERGY SERVCESINC

1 PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 6 0F 33 52 Examination Angles and Coverage _

5.2.1 The intent of this procedure is to provide maximum examina-tion coverage to ensure weld integrity.

Each weld shall be scanned with minimum 25% overlap of the transducer width -

(diameter) for each scan pass.

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u 5.2.2 The rate of search unit movement shall not exceed six (6) inches per second.

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5.2 3 Each weld and the required volume (WRV) of metal for one-half

wall thickness (1/2T) on each side of the weld shall be ultrasonically examined using 450 shear wave angle beam techniques applied in one direction perpendicular to the weld axis and in two directions parallel with the weld axis, on both sides of the weld, except where restricted by part geometry or access.

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,a 5.2.4 Straight beam techniques shall be applied to the required examination volume (WRV) and to all parent material thru which angle beams will pass during angle beam examination of the WRV.

Indications outside the WRV may be evaluated in accordance with Section 10.1.1 of this procedure.

5.2.5 Other angles may be'used if required for aid in evaluation of reflectors or to accommodate geometric restrictions and limited access.

All information shall be recorded on the data sheets.

5.2.6 Where examination surface, geometry or other conditions (weld, contour, access, etc.) do not permit a meaningful ultrasonic examination to be performed, the examiner shall record the area of non-examination and the particular interfering condition in the space provided on the Weld Scan Data Sheet.

In addition, he shall make a sketch of the weld and adjacent conditions on the reverse side of the Weld Scan Data Sheet (Figure 7).

5.2.7 All examination welds shall'be enterid in' lie ~~s' pace Frovided -

on the Weld Scan Data Sheet.

if there are no recordable indical~ ~

tions, it shall be so noted in the appropriate column.

5.2.8 Coverage for the welds specified in Table 1 is shown in Figures I through 4.

Scanner coordinate settings and setup configura-tions are shown in Table 2.

5.3 Liquid Couplant s

5.3.1 The ultrasonic couplant shall be demineralized water or a mixture of ~ demineralized water and a suitable wetting agent such as Kodak Photo-Flo solution or other and shall be recorded on the Weld Scan Data Sheet.

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0 NUCLEAR ENERGY SERVICES. INC,

PROCEDURE NO.

80A0470,

SUBJECT:

AUTO N0ZZLE WELD 5"~

PAGE 7 0F 33 5.3 2 The couplant shall be supplied in clean containers of suf-ficient quantity to perform the examination.

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5.3 3 The couplant shall be pumped from the container to the trans-ducer fixtures through flexiole tubing.

5.4 Surface Preparation

.-q i. I All examination surfaces should be clean and free of dirt, weld spatter, etc., or any other condition which would interfere with the examination by impairing proper transmission of the sound beam, or by preventing free movement of the search unit along the examination surface.

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5.5 Weld identification Each weld shall be located and identified per the appropriate weld map located in the Program Plan Book.

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5.6 _

5.6.1 Reference points have been marked on RPV nostle to vessel welds in*

accordance with Stone and Webster Specification SH1-397 to provide' identification and location of no::le to vessel welds.

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5.6.2 The RPV nossle to vessel weld reference points start at the highes't

- 2 point on the weld centerline and continue in a clockwise direction.

l lb 5.6.3 The top dead center position of the scanner assembly shall be determined by a levelling device.

5.6.4 The radial position of the transducer assembly shall be determined by means of alignment marks on the transducer slide assecbly and on the radial arm.

5.6.5 The transducer radial and vertical starting positions are specified in Table 2.

6.0 EQUIPMENT REQUIREMENTS

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6.1 Examination Contractor's Eauipment The following test equipment or its equivalent shall be provided by the Examination Contractor (as a minimum) for examination of the RPV nozzle welds:

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PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 8 0F 3.3 (1)

Nuclear inspection System I, No. 850096 (2)

Nozzle Scanner Assembly No. 80D i,.

(3)

Sled Assembly, 5-Transducer, No. 80D g

(4)

Sled Assembly, 3-Transducer, No. 80D A

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(5)

Transducers,1/2" i 1", 2.25 MHi~for Sle'd~ ~ ~7

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Assemblies (6)- Couplant Supply Systen

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(7)

Camera (8)

Thermometer 6.2 Plant Owner's Equipment

.g' The Plant Owner or his Agent shall provide the following service facilities and equipment as required:

(1)

Scaffolding 2

(2)

Demineralized Water, Air and Electricity (3)

Temporary Lighting (4)

Crane or Lifting Devices (5)

Calibration Standard No. SNPS-6 (6)

Calibration Standard No. SNPS-7-1/4 (7)

Test Surface Preparation- (Cleaning and Finishing)

(8)

Drawings of Each Examination Area (9)

Post-Examination Cleanup of Test Area 7.0 CAllBRATION REQUIP.EMENTS 71 Calibration Data Packages Calibration Data Packages shall be numbered 470-1, 470-2, 470-3, etc.,

at the timo of calibration and shall be signed by the examiner (s) upon completion.

A Calibration Data Package shall consist of a Weld Scan Data Sheet (Figure 7), Calibration Data Sheet (s) (Figure 8), Calibra-

~ tion Check Sheet (Fig. 9), and Supplements A, B and/or C (Figures 10, 11, 12) as required.

  • Later 4

NUCLEAR EPsERGY SERVICES psC.

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 9 0F 33 7.2 Calibration Standards 7.2.1 The calibration standards designated in Section 6.2 (5)"and...._)

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(6) shall be used for basic Instrument i calibration and for establishing reference sensitivity levels for examination of the specified welds.

(See Figure 5).

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1 7.2.2 The Identity of the calibration standard used for performing calibration shall be recorded on each Weld Scan Data Sheet and Calibration Data Sheets.

7.2.3 Calibration procedures for the examination shall be performed using the 0.0. surfaces of the calibration standards.

7.2.4 The temperature of the calibration standard shall be within 25 F of the component temperature.

Calibration standard and component temperatures shall be recorded on the Weld Scan Date Sheet.

7.3 Re.

2nce Sensitivity Level g

g 7.3.1 The reference sensitivity level shall be the electronically l

equalized response obtained from the distance-amplitude curve Initially established on the calibration standard and shall be the sensitivity level used for evaluating and recording all Indicatinns. _

7.3.2 During actual weld scanning, the reference sensitivity leve,1 shall be increased a minimum of 2X (6dB).

7.4 Times of Calibration 7.4.1 Examination system calibration shall be performed prior to examination of the specified welds and shall include establishing of Distance Amplitude Curves, setting of depth gates, and the programming of Electronic Distance Amplitude Correction (EDAC)

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and Transponding Ultrasonic Calibrator (TUC) cards to establish

equalized amplitude response.

7.4.2 Instrument vertical linecrity checks for each of the receivers ~~ ~

used shall-be~ performed at the beginning.of each day of

_ examination in accordance with the applicable sections of the procedure referenced in paragraph 2.1 (5).

Data shall be recorded as required within the Check Sheet, Figure 9 7.4.3 Examination system calibration checks using the TUC shall be performed at least at the beginning and at the completion of each 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period of examination and/or at the change of examination personnel, and at the completion of 'the examinations of each similar series of welds.

Checks shall be made in accordance with Sections 8.1 and 8.2 of this procedure.

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-.___._...._.J NUCLEAR ENERGY SERVICES thC.

k, PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 10 0F 33 9

7.4.4 Performance of the search unit steds and coaxial cables shall be verified each time the sled and cables are removed f rom the examination area.

Shculd an examination scan overlap two'

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shif ts, these checks should not interrupt the scan but shall be performed as soon as possible after the scan is completed i

(Refer to paragraph 8.2.2).

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7.5 Calibration pesponse

/7.5.1 Calibration responra shall be checked at the Equalized Response. Level.

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7 5.2 Signal respc e obtained during calibration check shall be within plus or minus 20% of that established during basic system calibration.

7.5.3 If any point on the Equalized Response has decreased by more than 20% of its amplitude, the examiner shall:

(1) !! ark all Weld Scan Data Sheets " VOID" since

/b6 previous calibration check.

(2)

Recalibratc examination system.

(3)

Re-examine voided areas.

7.5.4 If any point on the Equalized Response has increased by more than 20% of its amplitude, the examiner shall:

(1)

Recalibrate examinatio.1 system.

(2)

Re-evaluate all indications recorded since the previous calibration check at the corrected equalized dh response 1cvel.

7.5.5 If any point on the Equalized Response has moved horizontally more than 5% of the sweep line from its original settings, the examiner shall:

(1) Mark all Weld Scan Data Sheets "V0lD" since previous calibration check which.have recorded indications.

lfi (2)

Recalibrate examination system.

(3)

Re-examine voided areas.

@ nucum aneacy seauru~c.

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PROCEDURE NO.

80A0470

SUBJECT:

AUTO NOZZLE WELDS PAGE 11 OF 33 8.0 EXAMINATION SYSTEM CALIBRATION

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8.1 Basic System Calibration for Angle and Straight Beam 8.1.1 Basic examination system calibration settings and parameters may be established at any time prior to the T

examination of reactor vessel welds.

Initial calibration shall consist of the following:

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v (1)

Adjust instrument screep range to correspond with the area to be covered during the examination. For initial calibration, the 1/4T hold indication from the calibration standard shall occur at the second horizontal screen position; the 1/2T and 3/4T indications shall occur respectively at the fourth and sixth horizontal screen positions.

For angle beam examination where detection is possible, the far surface notch shall occur at or near the 8th position.

(2)

Establish actual Distance Amplitude Curve for each angle and examination depth combination by plotting the signal response amplitudes from the 1/4T, 1/2T and 3/4T reference holes while the highest response hole indication is set at 80% of Full Screen Height (FSH) as shown in Figure 6.

(3)

Adjust depth gate positions to cover the examination range.

In the O straight beam channel, water path indications exist due to the 'anstruction of the search unit.

Normally the first water path indication occurs at or near CRT position zero (0).

This b

position of the water path indication will vary depending on examination thickness.

Normal examina-tion practice is to ronitor (set gates) from the trailing edge of the water path (entry echo) to the leading edge of the thickness back reflection. As this is not necessari'.y CRT positions 0-8, the precise setting is best left to the examiner (s) at the time of system calibration.

(4)

Connect TUC to proper channel and place one TUC pulse in each depth gate.

(5)

Program a TUC card to catch the Distance Amplitude Curve established in (2) above.

(6)

Program a LAC card to electronically equalize all TUC responses to the specified (80% FSH) amplitude over the entire depth range to be used during the examina-tion.

The sensitivity established here is the reference sensitivity.

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P PROCEDURE NO.

80A0470

SUBJECT:

AUTO NOZZLE WELDS PAGE 12 OF 33 (7)

Pecord all infomation required on the Calibration Data Sheet (s).

The ultrasonic examiner or examiners shall sign the completed Calibration Data Package Sheet (s) noting their applicable SNT-TC-1A levels.

t (8)

Assign each TUC card a sequential I.D.' number from the TUC Card Log and properly store each calibrated TUC Card and DAC Calibration Data Sheet for subsequent

.use.

U (9)

Repeat steps (1) thru (8) fdr each of the instrument

, receiver sections used.

,y (10)

Adjust amplitude recording gate levels to trigger at the specified limits (40% to 80%) if examinations are to be performed immediately.

_8.2 System Calibration Check 8.2.1 Calibration checks of the examination system as required by Section 7.4.3 shall be perfomed as follows:

(1)

If not already running, equipment shall be allowed a minimum of 15 minutes warm-up.

(2)

Refer to the proper Calibration Data Sheets for required instrument settings.

(3)

Use appropriate TUC cards and DAC settings and perfom a check of the examination instrumentation system including sensitivity level, depth gate function and position, and digital print system.

Verify that the amplitude response is within plus or minus 20% of the Equalized Response obtained during initial calibration. Verify that all points on the sweepline are within plus or minus 5% of the b full equalized response sweep line.

(4)

If the response is beyond the allcwed tolerance, refer to Section 7.5.

8.2.2 Performance checks of search units and cables as required by Section 7.4.4 shall be performed as follows:

(1)

Reposition search unit on the Calibration Standard at each test hole and observe maximum signal response amplitudes and horizontal positions.

(2)

Verify that all amplitudes fall within 20% of the Equalized Response level and the horizontal displace-I ment is within the required plus or minus 5%.

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e NUCLEAR ENERGY SEREES INC.

PPDCECURE NO.

80A0470

SUBJECT:

AUTO NOZZLE WELDS PAGE 13 OF 33 (3)

If the response from any hole is beyond the allowed tolerance refer to Section 7.5.

8.2.3 Record time, date and type of calibration check (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, shift change, etc.) on the Calibration Check Sheet and attach a tape printout showing high and low amplitude response.

Figure 9 is an example of the Calibration Check Sheet to be used with this procedure.

8.3 Angle Beam Sensitivity Correction For Planar Re'flectors At Or Near The Far Surface.

8.3.1 With instrument at Equalized Sensitivity setting, position search unit to obtain maximum amplitude from far surface notch.

8.3.2 Note amplitude from notch, when detectable, on DAC plot graph on appropriate Calibration Data Sheet.

'8.3.3 This amplitude response may be used to facilitate subsequent evaluation of print cut data.

9.0 EXAMINATION PROCEDURES 9.1 Examination of Reactor Nozzle Welds 9.1.1 Refer to Figures 1 thru 4 and to Program Plan, Appendix D, for j@g scan coverage and scan sequence information.

9.1.2 Calibrate examination equipment as required by paragraph 8.1 or if more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> have elapsed since initial calibration, perform calibration check as required by paragraph 8.2.

Scanning is to be performed at two times (2X) ' the Equalized Response sensitivity (6dB higher).

9.1.3 Position scanner at reference points specified in 5.6.4 and 5.6.5 and begin automated examination sequence.

9.1.4 Us'ing rubber stamp, log Plant Name, Calibration Data no. (Data Package No.), Scan No., Orientation (perpendicular or parallel),

and Magnetic and Paper Data Tape No. on the printer tape, sign and date the printer tape.

Print out coordinates at the beginning and end of each scan.

9.1.5 Continue scanning sequences until all welds requiring the samc calibration have been examined.

Examinations shall not be considered complete unitl all recordable indications have be7n evaluated.

4 NUCLEAR ENERGY SERMCEilNC,

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PROCEDURE NO.

80A0470

SUBJECT:

AUTO NOZZLE WELDS PAGE 14 OF 33 10.0 EVALUATICN CRITERIA 10.1 Recording of Indications 10.1.1 For straight beam examinations of the base metal outside the WRV for laminations, all areas giving indications equal to or greater than the remaining back reflection shall be recorded on the

. appropriate data sheet.

Each recorded area shall be identified as to distance from surface, length and position relative to the veld datum point. When a 0 indication 'is encountered in the base material, the back surface signal from the component shall be adjusted to 80% FSH, prior to recording the indication extent.

t 10.1.2 For examinations of the WRV, all indications showing a signal amplitude response equal to or greater than 50% of the Equalized Response shall be recorded on the appropriate data sheet at the time of weld examination.

Planar indications at or near the far surface shall be compared directly with the amplitude obtained frca the notch.

(1)

Indications from examinations of the reactor vessel nozzle welds shall be recorded by channel, in inches (as determined from depth gate no.) from the examina-tion surface and in degrees and inches relative to the datum point.

(2)

Recorded data shall be taken on each parallel scan pass at increments not to exceed that permitted by the 25%

overlap of transducer element diameter (width).

(3)

The end points of recorded indications shall be determined by 50% DAC amplitude points.

10.1.3 Indications from all nozzle welds shall be reported in degrees CW or CCW from datum points when looking at the outside of the vessel, and in inches inboard (toward center of nozzle) or outboard (away from center of nozzle) of the weld centerline.

10.2 Evaluation of Indications 10.2.1 Evaluation of all indiciations shall be made at the Equalized Response level and in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, IS-300.

All evaluations shall be performed by a Level II or Level III examiner.

10.2.2 Results of this evaluation shall be reported to the Plant Owner or his Agent in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, IS-600.

Disposition of evaluation results shall be made in accordance with the Owner's Plant Procedures.

  • huCLEAR ENERGY SERVICES 1hC.

t PROCEDURE NO.

80A0470

SUBJECT:

AUTO NOZZLE WELDS PAGE 15 OF 33 11.0 EXAMINATION RECORDS 11.1 Certification of Records The examiner shall complete and sign all data sheets immediately upon the completion of each weld examination.

The data sheets cay be reviewed by the authorized Code Inspector.

11.2 Filing of Records

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The examiner shall be responsible for submitting to the Plant 0.mer or his Agent a completely documented set of examination records including certification of personnel qualifications with a current eye test report in accordance with SNT-TC-1A.

11.3 Procedure Corrections and Additions 11.3.1 All procedure corrections and/or additions required during the preservice examinations shall be made in accordance with requirements of NES QA Program Plan #NES 80A0448.

11.3.2 The examiner will contact the LILCO represen.ative on site to initiate all such changes.

All changes shall be documented in the record of revisions sections of this procedure.

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NUCLEAR ENERGY SERinCES thC,

PROCEDURE NO.

80A0470

SUBJECT:

AUTO tJ0ZZLE WELDS PAGE 16 0F 33 LEGEND 5-7/8" 5/16" Claddi ng

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_L Perpendicular to Weld Parallel to Weld

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O Base Material WRV Weld and Required Volume 0*

45 1 10.5" l

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00 WRV 3"

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5-1/2"R 34"D

/

1 2.-

~ ~

- *: _.__.a.~;

~

~

~

s s

Figure 1 - Ultrasonic Examination of Feedwater Nozzle to RPV Weld Sa nucamaestacvssavictunc

,i JAG

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 17 0F 33 5-7/8" 5/16" Cladding LEGEND i Perpendicular to Weld N

j Parallel to Weld O Base Material

.0 WRV Veld and Required Volume

'~

45*.L 10.5" i

//

00 WRV 3"

/

450 =

h

[/

1.5" //////,'

// / / / /

d 5-1/8" R 32" 0 J

/

..__.n,_

. -. =.

...,n_.._,._

Figure 2 - Ultrasonic Examination of Core Spray Nozzle to RPV Weld

u%

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS-PAGE 18 0F 33,

~

LEGEND 6-7/8" 5/16" cladding 1 Perpendicular to Weld

\\

_/

_ Parallel to Weld

  • O Base Material

-A WRV Weld and Required Volume

-O a

~

5.L 12"

.f

/

'~5 0 WRV -

3.5" 45

=

I

//

/

~

0" l/////

~

ll////

4-1/8" R 28-11/16" D

)

/

j

-w__

Figure 3 - Ultrasonic Examination of Recirculation inlet Nozzle to RPV Weld 4

o A PeuCLEA4EhERGYSERytCEiIN

~

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 19 0F 33 LEGEND

~

1PerpendiculartoWeld

= Parallel to Weld 6-7/8"

- 5/16"

  • O, Base Material 77 2ZWRV Weld and Required Volume 0
  • u 45.L

-0 WRV ---

12" 45

=

3 5"

((((f 1.5"

'//////

7" R 59-1/4" D Figure 4 - Ultrasonic Examiniation of Recirculation Outlet Nozzle to RPV Weld.

wetua essacy scavices >=c.

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 20 0F 33-f' Examination Surface

, 1 j.

O o

- 1/4T

~

T' O

O

- 1/2T o

o

- 3/4T

'Claddingi hp G

is is n

' lI 18 ll ll Il

!! If

,i Calibration Holes (6)

Standard Block Hole Hole Notch No.

Thickness 1/4T 1/2T 3/4T Diam.

Depth Depth SNPS-6 5-5/32" 1.54" 3.08" 4.62" 0.25" 3.00" 0.123" SNPS-7-1/4 7.25" 1.81" 3.62" 5.44" 0.312" 3.00" 0.145" Figure 5 - Ultrasonic Calibration Standards for RPV Nozzle Welds G

' NUCLEAR ENERGY SERVICES, INC.

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 21 0F 33 DAC Equalized

/

i Initial DAC 1

2 3

{

2 Curve e

n n

n 3

f yg 4T I

I l

3 f

3/4T t

I l

i I

J+

6 9

\\

1 i

2

-Q g

(

r h

2 Straight Beam Search l

l

[

j Unit Positions 0

2 4

6 8

Typical DAC Curve 4 r,3 2 r,1 i

i n

t t DAC Equalized m

f

~

~

N gg 2

initial DAC

\\

g __

ST 3

' Curve NN_

I i

[l l

4

\\

'l I

X h

h i

Angle Beam Search Unit il

?,

.g Positions

,1 h

ll p

i II l

1 I

I O

2 k

6 8'

Typical DAC Curve Step 1 - Adjust sweep controis so that 1/4T, 1/2T and 3/4T holes are located respectively on the 2nd, 4th and 6th horizontal screen positions.

Step 2 - Adjust sensitivity to provide 80% FSH indication from hole giving maximum response.

Mark position on screen.

Step 3 - Position search unit for maximum response from remaining holes.

Mark position on screen.

Step 4 - Plot DAC by connecting points marked on screen with line extended to cover entire examination range.

~

~

~

Step 5-Useelectronicdistanceamplitudecorrectiontoequalizeamplitude

~'

response at the specified level.

Step 6 - Record all sweep and sensitivity control settings on respective data sheets.

Step 7 - Position search unit for maximum response from far surface notch and "X" mark screen and data sheet to indicate amplitude.

Figure 6 - Reference Sensitivity and DAC o

Calibration Procedures for

/p#*

NUCl. EAR ENERGY SERVICES, INC.

Ultrasonic Examination or wesos.

' ' PAGE 22 0F 33

' Plant / Unit AUTOMATED EX.01INATION

~

~

E*! YU WELD SCAN DATA SHEET Cal. Data Pkg Sheet of TRANSDUCER IDENTIFICATION NUCLEAR REFLECTOSCOPE Proc. No.

Rev

~

Size:

Model No.

I Frequency:

MHz Assy No.

85D096 Cal Block No.

Manufacturer:

Exam Surface TRANSDUCER FIXTURE Part No. (Style) :

Assy No.:

Block Temp.

  • F
'H.#

Serial No. Angle / Mode Refr'd Angles:

Comp. Temp.

'F 2

T.U.C. CARD ID UO.'S CABLE /COUPLANT CH. 1 Cable Type:

3 4

CH.2&3 Cable Length:

5 CH.4&S Couplant:

SCAN AREA RECORDABLE INDICATION

~

WELD / SCAN NO.

1-

=~

CO:O'INTS/ REASON FOR (Indicate both)

Yes No INCOMPLETE SCAN (s)

/

M W d We d Examiners 1 ADDITIONAL SHEETS (Check Box)

Level Date Continuation Supplements 2

Level Date Cal. Data Sheet Beam Plot Reviewer Date O

NuCLUM E%ga0V SERV'CES :.%C.

g

PAGE 23 0F 33 Plant / Unit AUTOMATED EXAMINATION Cal. Data Pkg CALIBRATION DATA SHEET Sheet of Comp /Syst Proc. No Rev Cal Block No.

T.U.C.

Card ID No.:

SCOPE CONTROLS Pulses:

Channel / Angle:

Trigger + -

Freq: A B C Sweep Delay C

F Pulse Perioc C F

Sweep Range C

M F

Pulse Delay C

F Mode:

Attenuation C

F' Pulser requency:

mz Receiver Prim. Ref. Sens*. :

dB D.A.C. CARDS Unit "

Pulse Length:

24 CDCDCDCD CJ 23 CJ C J CJ Ca CD CD Reject:

22 ta a OCJC3 Closed 21 CJ CD C 3 Frequency:

MHZ 20 ca c 3 ca c3 c3 CJ Switched 19 CJCDCDtaCJ CJ Pulser Gain (

):

t3 18 C 3 CD C J C 3 CJ CD Open Unit Gain (

):

17 CDC3C-]C3CJCJ 16 E3CDCJCDCJC3 Damping:

15 C J t J C--] c 3 C_]

14 CJCJCJCJCJCJ Gate Start 0 F

13 CJ CD c2 CD C J CJ G

12 CJ CJ CJ CJ CD Var.I C

F A

11 CD CD CJ CJ C-] CQ T

Fixed Gate Mos.:

10 CD CJ CD t ' CJ CJ Gate E

9 C J CD Q C-] CJ Clad Gate: C F

Settings S

8 tJc3 7

c3CJcmcacac3 Var. 2 C

F 6'

CJ Ca CD CJ CJ CJ 5

CD CD CJ CD CJ Var. 3 C

F 4

CD CD CJ CJCJ Var. 4 C

F 3

CJ CJ CD 2

CD CD CJ CJ CJ CJ B.E. Gate: C F

1 CJ CJ CJ CJ O C---)_

PRE-DAC r-1 O CJ G CO C J Screen Gated:

Div.

to CD ca C3 C3 a CD CO CJ CJ CJ CD CO 1 Gate:

Screen Div.

C-]CD CJ CJ CJ l Screen Div:

in.

dB 1 2 4 8 10 20 Gate Start Depth:

in.

Equalized Sensitivity:

dB Exam Sen.;itivity :

dB Examiners:

DEPTH MdL.

ATTO icos DAC N IDENT in.

4 dB l

t 1 2 l 3 6 & l 5 5

1.

Level ~Date 4

l I

i ec 7ol g

l l

2.

1 t i

I I

Level _Date ec l

50 p

4 l 4 4 l Reviewer:

4 C,.

1

+

l

+

+

3 C, l

1 i t i i i Date i

2 c,

, i g i j 1C

., ;,. I i....i.

i.a....I g,.

O 1 2 3 4 5 6 7 a 9 to -

O 4:

P.uCLEAst EPsE%V OERVCES t%

RE 8 A

A A

?

'A BRA I

PAGE 24 0F 33 AUTOMATED EXAMINATION CALIBRATION CHECK SHEET Cal. Data Pkg Comp./Syst.

Sheet of Proc. No.

Rev Cal Block No.

Exam Surface Block Temp.

  • P Comp. Temp.

'F INSTR. LINFRITY RESPONSE INSTR. LINEARITY RESPONSE INSTR. LINEARITY RESPONSE Amplitude Amplitude Amplitude High Low High Low High Low High Low High Low High Iow 1

5 1

5 1

5 2

6 2

6 2

6 3

7 3

7 3

7 4

8 4

8 4

8 AMPL. CONTROL LINEARITY AMPL. CONTROL LINEARITY AMPL. CO:iTROL LINEARITY Init.

Adb Result Limits Init.

Adb Result Limits Init.

Adb Result Limits 80

-6 32-48%

80

-6 32-48%

80

-6 32-48%

80

-12 16-24%

80

-12 16-24%

80

-12 16-24%

40

+6 64-96%

40

+6 64-96%

40

+6 64-96%

20

+12 64-96%

20

+12 64-96%

20

+12 64-96%

CHANNEL 1 CHANNEL 2 & 3 CHANNEL 4 & 5 TYPE OF CALIBRATION DATE TI?'E BY

1. VERTICAL LINEARITY
2. AMPL. CONTROL LINEARITY i
3. BASIC SYSTEM CALIBRATION DATE TIME BY DATE TIME BY 4.INTERM. TUC CHECKS 5.INTERM. UNIT / CABLE CHECKS Examiners 1 Level Date 2

Level Date Reviewer Date

' NUCLEAR ENERGY SERvrCES INC.

FIGURF 9 - U0 ED E PATf05 C LIBRATION

/

PAGE 25 0F 33 O Datum SUPPLEMENT A INDICATION REPORT SHEET xo STRAIGHT BEAM k-Procedure No.

N, Subject N.

Weld No.

\\,

Page of

\\

Attached to Cal Data Pkg No.

Y

. co-t J

Notes:

r-Yi-i d 1

-Y (1) X-axis increments not to exceed 2

allowable scan increments.

(2) End points shall be:(a) 50% of DAC i

I (6db) for WRV Straight Beam exam, k

'(b) equal to Remaining Back Re-

.I i o }

flection (RBR) for base raterial 77 lamination exam.

l,QD (3) This column for WRV Straight Beam exam only.

Yi (4) This column for base materiallam-Y ination exam only.

2 P.AX ('))

(4,)

ENDPOI:;T I'E-(i)

CATION SIDE OF D

X

% DAC PSR Y Q MAX II' UU{g D

NO.

WELD (in T/8s)

(in deg)

.(idB)

% FSH

% DAC y

y i

COMMENTS EXAMINERS 1.

Date Level 2.

Date Level REVIEWER Date 4

  • PeuCLEAR ENERGYSERvCES M FI ure 10 Su lement A Strai ht Beam Indication

PAGE 26' 0F 33 0

D Datum SUPPLEMENT B INDICATION REPORT SHEET J. ANGLE BEK4 x

Procedure No.

N Subject Weld No.

Page of

\\

Attached to Cal.

Data Pkg No.

y)_

Notes:

l (1) X-axis increments not to exceed allowable scan increments i

l (2) End points shall be 50% of DAC o

"y f, I

{

(6db)

N 7 o (3) Data must be recorded from both pg i

t sides.

If indication cannot be II found from the opposite side, so y'

state.

Y l

g l INBOARD (i)

OUTEGR D (o)

CALC.

MAXIMUM I!DICATION INDI-SIDE ENDPOINT *)

ENDPOINT (2)

L f

X(t)

MAX D 0 MAX Y C: MAX CATION OF (p NO.

WELD' (deg)

% DAC (T/8s)

(in)

D1 Y

(in)

D2 2

Y (in) in.

%T i

I COMMENTS EXAMINERS 1.

Date Level 2.

Date Level REVIEWER Date G

mnea vec, seavees. u.c.

I

~

'PAGE 27 0F 33 SUPPLEMENT C INDICATION REPORT SHEET

= ANGLE BEAM Procedure No.

s(g Subject 0 Datus e

o Weld No.

Page of L

i Attached to Cal.

Data Pkg No.

X 2

  • ~

X*

'N o

. Notes:

(1) Y-axis increments not to exceed

(*.

, N, allowable scan increments w

i (2) End points shall be 50% of DAC

. s b

(6db) y '

D (3) Data must be recorded from both

'g sides.

If indication cannot be

\\

\\

found from the opposite side, so

-[

I state P.'XI:UJM INDICATION INBOARD (i)

OUTBOiR D (c)

CALC.

I IDE ENDFOINTil)

ENDPOIIM1)

L Y(8)

MAX D @ MAX X @ MA>

CATION OF (3)

NO.

WELD.

(in)

% DAC (T/8s)

(in)

D1 XI (deg),

D3 X9(deg) in.

%T COMMENTS EXAMINERS 1.

_ Date Level 2.

Date Level REVIEWER Date O

P NUCLEAA E N E RGY SERVICEitPgC, q

PROCEDURE NO.

80A0470

SUBJECT:

AUTO N0ZZLE WELDS PAGE 28 0F 33 TABLE 1 WELD IDENTIFICATION

/

Weld No.

Descriotion Reference Block Reference Figures Notes 4-316A Feedwater (N4A, B, C, SNPS-6 1, 5 Thru.D D) Nozzle to RPV Welds ll-316A Core Spray (NSA, B) 2, 5 o

and B Nozzle to RPV Welds 13-314A Recirculation inlet SNPS-7-1/4 3, 5 Thru H, (N2A thru H, J, K)

'I J, K Nozzle to.RPV Welds 5-314A Recirculation Outlet

[

4, 5 and B (NIA, B) Nozzle to RPV Welds O

O j~.

M NUCLEAR ENERGY SERVICES, INC.

~

PROCEDURE NO. 80A0470 SUBJECT Auto Nozzle Welds PAGE 29 0F 33 AUTOMATIC N0ZZLE EXAMINATION FOR SHOREHAM NUCLEAR POWER STATION

- KEY -

General - Nozzles to be scanned automatically Nozzle Weld ID Feedwater (N4) 4-316 Recirc - In (N2) 13-314A Recirc - Out (N1) 5-314B Core Spray (NS)11-316 Column 1 Nozzle Designation followed by Scan number Column 2 M - Medium size nozzle scanner L - Large size nozzle scanner Column 5 5 = 8002006 5 search unit sled 3 = 80D2012 3 search unit sled Orientation 5 Search Unit 3 Search Unit 2.

6 3

/2 9

/

h NUCLEAR ENERGY SERVICES, INC.

PROCEDURE NO.

80A0470 SUBJECT Auto Nozzle Welds PAGE 30 0F 33 Column 7 Datum Point "Y" datum is sled in the farthest position on nozzle scanner

. arm Zero, Zero (0, 0") is center of nozzle.

WELD 4

77)L

=

/

/

l h

~

UJELD

(&

-.\\.

gy

=

( c '. o-)

r-ROLELE CENTER OV Column 8 s 9 N O 2.7_LE inches Speed to be filled in on site - actual speed used (6 ax.)

seconds Column 11 Sample Rate - to be filled in on site Note - Center transducer in sled assemblies is reference transducer when ilmit of scan is attained, it is the center transducer that has reached limit on 5 unit sled, o transducer is reference On 3 unit sled, 45 transducer is reference 9

4

~ huCLEAR ENERGY SERvCES.INC

TABLE //2 PROCEDURE No. 80A0470 AUTOMATIC EXAMINATION SEQUENCE SUBJECT Auto Nozzle Welds NUCLEAR COMPONENTS PAGE 31 0F 33 t.

3.

4.

5, e $ L 7

6, 9,

10 II.

. a: E cs D 5

DATUM X AXIS Y AXIS INDEX SAMPLE MWp "t

p5 2.E$Q5 8 $ 8 G < (Degrees)

(Inches) (Degrees t

Deg rees, (Inches' (Inches)

/ SCAN NO.

@M$ME d$ dE5 X AXIS Y AXIS START SPEED LIMIT START SPEED LIMIT AXIS LIMIT RATE 314A-01 M

ll N/A 5,2 N/A 0

33 0

360 20 14.3 Y

.75" 314A-02 1

3.3 28 X

1.5 20 Y

,75" 314B-01 1I 5,2 28 X

1.5 3148-02 1

3,3 20 Y

75" 314C-01 11 5,2 28 X

1.5 314c-02 1

3,3 20 Y

75" 314D-01 11 5,2

~

28 X

15 3140-02 1

3,3 20 Y

75" 314E-01 11 5,2 28 X

!.5 314E-02 1

3,3 20 Y

75" 314F-01 1I 5,2 28 X

1.5 314F-02 1

3,3 20 Y

. '7 5 "

314G-01 11 5,2 28 X

1.5

-314c-02 1

3,3 20 Y

75"

-31411-01 ll 5,2 F

U 7

28 y

X 1.5 314ll-02 1

3,3 y

TABLE #2 PROCEDURE No.

80A0470 AUTOMATIC EXAMINATION SEQUENCE SUBJECT Auto tiozzle welds NUCLEAR COMPONENTS PAGE 32 0F 33 2.

3.

4.

5, o @

z 8.

9.

10 II.

aE cs E 5

DATUM X AXIS Y AXIS INDEX SAMPL E ep

  • ti p5 w

E$ 55 8$@G< (Degrees)

(Inches) [ Degrees

' Degrees; (Inches, (Inches) g @.E$ ME d$ d25 X AXIS Y AXIS START SPEED LIMIT START SPEED LIMIT.

AXIS LIMIT RATE

/ SCAN NO.

r 14.3 Y

75"

-314J-01 ft

!I N/A 5,2 ft/A 0

33 0

160 2n X

1.5

-314J-02 1

3,3 28 20 Y

75"

-314 K-01 11 5,3 I

-314K-02 1

3,3 28 X

1.5 i-316A-01 11 5,2 360 50.0 22 17 Y

75"

-316A-02

.L 3.3 360 50.0 29 X

1.4 4-3168-01 11 5,2 0

174.6 22 Y

75" 6-316B-02 11 5,2 360 226.4 22 Y

75"

-3168-03 1

3,3 0

174. 6 29 X

1.4

-316B-04 1

3,3 360 226.4 29 X

1.4

-316C-01 ll 5,2 360 50 22 Y

75" i-316C-02 1

3,3 360 50 29 X

1.4 i-316D-01 11 5,2 0

360 22 Y

75" a-316D-02 1

3,3 0

360 29 X

1.4 1-316A-01 11 5,2 0

360 21 16 Y

75" 1-316A-02 i

f f

1 3,3 0

360 28 16 X

l.4 i

L E

P T

M A

A R

l.

f S

T I

5 5

M 7

9 9

s X

I 7

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L l

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3 W

3 N

0 I

7 e

S 4

l I

Y X

Y X

0 z

F X

A z

0 A

0 o

0 8

N 1

)

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.t sT 6

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cI 2

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3

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D CJ E I

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aT hR cA 5

3 5

3 9,

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4 3

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P NE X

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o BM gA AAR eT TXA 6,

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CC sS I

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M O

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7

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2, 2,

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0

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A A

A 8

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C 4

4 4

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