ML20084M483

Rev 1 to Procedure 80A7616, Ultrasonic Exam Procedure for Reactor Vessel Feedwater Nozzle Inner Radius

ML20084M483
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/28/1983
From:	Alling M NUCLEAR ENERGY SERVICES, INC.
To:
Shared Package
ML19268B543	List: ML20084M458 ML20084M468 ML20084M483
References
80A7616, NUDOCS 8306020184
Download: ML20084M483 (33)

Text

ENCLOSURE 2 M DdCUMENT NO. ROA7A1 A REV. 1 NUCLEAR ENERGY SERVICES, INC. PAGE I np 21 ULTRASONIC EXAMINATION PROCEDURE

! FOR REACTOR VESSEL FEEDWATER  !

NOZZLE INNER RADIUS l

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a L-Project Application Prepared By Date 5545-200 M.F. Alling 1/77/R1 APPROVALS TITLE / DEPT. SIGN AT U R E _

DATE Level III _

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- g DOCUMENT NO. 80A7616

" " PAGE 2 OF 21 NUCLEAR ENERGY SERVICES. INC.

REV. PAGE NO.

DATE NO.

DESCRIPTION APPROV AL 1 2/25/83 4 Para. 2.1 changing code year to "1974 t#d Stmner 75" Para. 2.2 reworded Para. 2.8 added new para.

4-5 Para. 3.1 reworded second and fourth sen-tence.

i Para. 1.2 addad new sentence. '

Para. 4.0 rewordad 2nd and 3rd linan. .

. 6' Pava. 5.2.5 rewordad 6-7 Para. 5.3 add new para. and renumbered 8 Para 6.1.11 added new para.

Para 6.2.5 reworded 9 Para. 8.1.1 revised Para 8.1.(2).(5) reworded 11 Para 8.2.5 add new cara, and renumbered Para. 8.3.l(A) (1) reworded 12 Para. 9.l(1). (3) reworded Para. 9.2.1 delete " Note... level".

14 Para.10.1.2 chance " 25% to 20%"

l Para. 10.1.1 add new cara and renumber =d Para. 10.2.1 revised 19 Parn . 11.1 revi sed 16-lS Figure (1),(3),(4) revised

?n_.2] Figure 5 delete and add new Fig. 5&6 Refer to CRA No. 3165

DOCUMENT NO. 80A7616 PAGE 3 op 21 NUCLEAR ENERGY SERVICES, INC.  ;

ULTRASONIC EXAMINATION PROCEDURE FOR REACTOR VESSEL FEEDWATER NOZZLE INNER RADIUS

1. SCOPE 1.1 AREA OF EXAMINATION l This document covers the ultrasonic examination procedure and application requirements for the examination of the feedwater nozzle inner radius area.

i 1.2 TYPE OF EXAMINATION

1. Volumetric examination, from the shell, shall be performed using ultrasonic  !

I pulse echo nominal 70 angle beam shear wave techniques applied to the [

t OD surfaces of the shell adjacent to the nozzles at the proper tangential (skew) angle.

2. Volumetric examination, from the barrel, shall be performed using

' compound angle beam shear wave techniques (two angles simultaneously) applied to the OD surface of each nozzle barrel to be examined.

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3. The examination sball be performed manually using contact search units (transducers) and/or scan fixtures.

4. The examination scan movement approach shall' proceed no further than l the beginning of the radius blend of each nozzle while on the vessel shell or nozzle barrel.

1.3 NOZZLE INNER RADIUS CONFIGURATION i

Typical nozzle inner radius area configuration is shown in Figure 1.

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DOCUMENT NO. 80A7616 PAGE OF 21 NUCLEAR ENERGY SERVICES. INC. ,,

l' 4

1.4 MATERIALS The reactor shell and nozzles are constructed of carbon steel with stainless steel cladding on the ID surface.

2. REFERENCES

1. .Section V, including Article 5, " Ultrasonic Examination," 1974 Edition, up to and including the Summer of 1975 Addenda.

2. ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition through the Summer 1975 Addenda, invoking the provisions of IWA-2240.

I SNT-TC-1 A, Testing Personnel and  !

3. " Nondestructive Qualifications Certification," 1975 Edition.

4. 80A9068 NES " Procedure for Qualification and Certification of Nondestructive Examination, Personnel"(Latest Revision).

5. 80A9053 NES " Procedure for Ultrasonic Instrument Linearity Verification" (Latest Revision).

~

6. NUREG-0619; BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking.

7. 80A9060 NES " Inservice Inspection Field Change Procedure"(Latest Revision). i

8. 80A9021 NES ISI Operations QA Manual (Latest Revision). .

3. PERSONNEL AND MATERIAL REQUIREMENTS

1. Personnel shall be certified in accordance with references 2, 3 and 4. At least

. .one member of an ultrasonic examination team shall have a minimum qualification of Level II. In addition to the certification referenced above, each h person performing inner radius examinations shall receive an additional 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />

< FORM s NES 205 2/80

DOCUMENT NO. 80A7616 mur -

11 NUCLEAR ENERGY SERVICES. INC.

of training annually. This training shall be documented and retained in the k individual's certification reco'rds. A copy of the examiner's certification summary and'a current eye test as . required by SNT-TC-1 A and Section XI, shall be submitted to the Plant Owner, or his Agent, prior to starting examinations.

2. The ultrasonic couplant shall be Ultragel and be certified to contain less than 1%

i sulfur and halogens by weight. The couplant shall be supplied in clean containers of sufficient quantity for performance of the examination. Vaseline or 1 equivalent may be utilized to couple the transducers to the wedges.

3. The search unit cable may be Microdot or BNC of any convenient length or combination of lengths. Record actual usage on the Calibration Data Sheet.

4. PROCEDURE COMPLIANCE The examination procedure described in this document complies with Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition, Summer 1975 Addenda, invoking the provisions of IWA-2240, except where examination coverage is limited by part  !

geometry or access. Such limitations shall be identified and described on the data sheets.

l 1

5. EXAMINATION REQUIREMENTS 1

5.1 EXAMINATION FREQUENCY

1. The nominal examination frequency shall be 1.0 MHz for all examinations

performed from the shell. For examinations performed from the nozzle l barrel, 2.25 MHz shall be used.

1

2. Other pulse frequencies may be used if such variables as material attenuation, grain structure, etc., necessitate their use to achieve penetration or resolution. This information shall be recorded on the data sheets.

FORM # NES 205 2/80 - -

DOCUMENT NO. 80kf616 mr 11 NUCLEAR ENERGY SERVICES, INC.

l i

5.2 EXAMINATION ANGLES AND COVERAGE

1. The intent of this procedure is to provide maximum examination coverage.

Each nozzle inner radius shall be scanned with minimum 25% overlap of the transducer width (diameter) for each scan pass.

2. The rate of search unit movement shall not exceed 3" per second.

3. Each shell side examination (Zone 1) shall be performed, where part geometry and access permits, using 70 angle beam shear wave techniques.

They shall be applied in two directions, CW and CCW, tangential to the inside radius of each nozzle from the OD surfaces of the shell. The scanning approach shall proceed only to the beginning of the OD radius blend of each nozzle, as proceeding onto the blend will cause lift-off and also distort beam angle entry for this area of examination.

4. Each ba,rrel side' examination (Zone 2) shall be performed, where part geometry and access permits, using compound angle beam shear wave  :

techniques. They sha!! be applied in two directions, CW and CCW, 360 around the nozzle barrel OD surface. The scanning shall proceed no further than the beginning of OD radius blend, as proceeding onto the blend will cause lift-off and distort the entry angle for this examination.

5. Other angles may be used if required for aid in evaluation at the discretion 1 of the Level III examiner.

3.3 BEAM SPREAD MEASUREMENTS .

l 1

Beam spread measurements for the vertical plane of each angle beam search unit  !

l shall be made using a locating strip as followsi

1. Position search unit for maximum response from the 1/4 T hole. Set the amplitude response at 80% FSH and mark the location on a locating strip.

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DOCUMENT NO. 80A7616 HE!_%m NUCLEAR ENERGY SERVICES, INC. PAGE 7 OF 21  !

2. Increase instrument sensitivity 2X(6dB) over reference sensitivity and h move 'the search unit toward the hole until signal amplitude is equal to the j DAC curve drawn on the screen. Mark the strip where it crosses the scribe line over the 1/4 T hole.

3. Move the search unit away from the 1/4 T hole, through the maximum amplitude point, until the signal amplitude is again equal to the DAC curve drawn ori the screen. Again, mark the strip.

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4. Repeat steps 2 and 3 for 1/2 T, 3/4 T and 1-1/4 T holes, using small numbers "2", "3a and "5" respectively. , ,

5. Using suitable beam plot forms for appropriate thicknesses, transfer the measurements from the block to the paper. Connect points to determine spread and angle information. i h

6. Beam spread plots shall become part of the examination record.

5.4 DATUM POINTS 1

l Daturn Points for the vessel nozzle inner radius areas shall be located at the highest point on the vessel to nozzle weld at the weld centerline.

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6. EQUIPMENT REQUIREMENTS .

6.1 EXAMINATION CONTRACTOR'S EQUIPMENT The following test equipment or its equivalent shall be provided by the Examination Contractor (as a minimum) for the examination of the inner radius areas specified in this procedure.

FORM = NES 205 2/80 _ _ _

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DOCUMENT NO. 80A7616 NUCLEAR ENERGY SERVICES. INC.

1. Pulse-Echo ultrasonic instrument

2. Wedges: Std. 70 for shell side examinations

3. Wedges: predetermined compound angles for barrel side examinations ,

4. Wedge: Std. 45 for barrel calibration

5. Search units: 1.0 MHz,1" diameter for shell side examinations

6. Search units: 2.25 MHz,1/2" x 1" for barrel side examinations

7. Couplant

8. Miniature angle beam verification block

9. Camera 10 Thermometer

11. Any other equ:pment to aid in examination or evaluation. k 6.2 PLANT OWNER'S EQUIPMENT The Plant Owner, or his Agent, shall provide the following service facilities and equipment as required:

1. Scaffolding

2. Water, Air, and Electricity

3. Adequate Temporary Lighting I

4. Moving or Lifting Devices

5. ' Calibration Blocks (VY-6-IR and RV-1) 1

6. Radiation Monitoring Equipment l

7. Radiation Shielding Equipment

8. Vessel Layout Equipment and Supplies (as needed)

J 9. Test Surface Preparation (cleaning and finishing)

10. Post examination cleanup.

7. CALIBRATION REQUIREMENTS ,

l 7.1 CALIBRATION PACKAGES Calibration Data Packages shall be numbered 7616-1, 7616-2, 7616-3, etc.,and I j

shall be signed by the examiner (s) upon completion noting applicable NDE Certification Levels. All Data Sheet (s) shall be annotated as either "shell scan" or " barrel scan" for the individual examination being performed.

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DOCUMENT NO. 80A7616 mu 11 NUCLEAR ENERGY SERVICES, INC.

7.2 INITIAL SENSITIVITY LEVEL The initial sensitivity levels shall be the amplitude response from the ID notch within the calibration block.

8. EXAMINATION SYSTEM CALIBRATION 8.1 ANGLE BEAM CALIBRATION FOR EXAMINATIONS PERFORMED FROM THE

, SHELL '

Angle beam calibration, using a standard 700 wedge and the appropriate ,

calibration block, shall be performed as follows:

1. The instrument horizontal linear range, as displayed on the CRT, will be k calibrated in inches by use of a miniature angle beam verification block or IlW block.

2. To establish the vertical linear range, obtain a maximum response from the h opposite surface notch and adjust sensitivity controls to pro, vide a signal amplitude of 80% FSH and mark location and amplitude on the CRT. The response from the 1/4 T and 3/4 T holes shall also be marked on the CRT for reference.

3 This is the initial sensitivity level. Record all sensitivity control settings I

on the appropriate Calibration Data Sheet.

4. Upon completion of calibration ensure that all data and instrument settings are recorded on the Calibration Data Sheet. Sign sheet upon . completion, noting applicable NDE Certification Levels.

5. To establish scanning sensitivity, position the search unit at the 0 reference point of the nozzle. Using the sensitivity control, adjust the cladding interface signal response level to 20% FSH (this response shall not be less than the initial sensitivity level). All indications shall be evaluated and recorded at the scan sensitivity.

FORM E NES 205 2/80 ._J

DOCUMENT NO. 80A7616 PAGE 10 op 21 NUCLEAR ENERGY SERVICES. INC.

8.2 ANGLE BEAM CALIBRATION FOR EXAMINATIONS PERFORMED FROM THE NOZZLE BARREL Angle beam calibration, using a standard 45 wedge and the appropriate calibration block, shall be performed as follows:

1. Horizontal linear range shall be established in inches of metal path as follows:

A. Obtain a maximized indication from the long radius reflection surface of the " Miniature Angle Beam Verification Block" (2" metal path).

~

B. Using the material calibration control and the delay control, align this signal at CRT position 2.

C. Increase tiie instrument gain until secondary echos occur.

D. Align the secondary echos shall be aligned at CRT positions 5 and 8.

'E. The CRT is now calibrated in inches of metal path (each major division equaling 1 inch). Make no further adjustments to the sweep range or delay controls.

2. Using the nozzle barrel calibration block, obtain a maximum response from the opposite surface notch. Adjust sensitivity controls to provide a signal amplitude of.100% FSH and mark location and amplitude on the CRT.

3. This is the initial sensitivity level. Record all sensitivity control settings on the appropriate Calibration Data Sheet.

4. Upon completion of calibration ensure that all data and instrument settings are recorded on the Calibration Data Sheet. Sign sheet upon completion, noting applicable NDE Certification Levels.

. FORM 8 NE@ PM5 arg6) __ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _

T my DOCUMENT NO. 80A7616 PAGE 11 OF 21 NUCLEAR ENERGY SERVICES, INC.

5. Remove the transducer from the standard 45 wedge and attach it to the k appropriate barrel examination wedge, CW or CCW.

6. To establish scanning sensitivity, add 20 dB to the initial sensitivity. All indications shall be evaluated and recorded at the scan sensitivity.

8.3 CALIBRATION CHECKS

/ 1. A system calibration check shall verify the DAC curve and the sweep range calibration at the start and finish of each examination, with any change in examinatien personnel, transducers, cables, shoes, batteries, couplants and at least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during an examination. Calibration checks shall be performed at the initial sensitivity level. Signal response obtained during calibration check shall be within plus 20% of that established during basic .

system calibration.

A. If any point on the DAC curve has changed by more than 20% of its amplitude, the Examiner shall:

1. Void all nozzle inner radius scan data sheets since the previous l calibration or calibration check.

i I

2. Recalibrate examination system.

l l 3. Reexamine voided areas. I l

B. If any point on the DAC curve has moved horizontally more than 5%

of the sweep line from its original settings, the Examiner shall:

1. Correct the sweep calibration and note correction (s) on the Calibration Data Sheet.

j 2. Void any recorded indication data taken since the previous calibration, or calibration check, and reexamine the applicable area using the corrected sweep.

I FORM e NEM62 PMg ,

DOCUMENT NO. 80A7616 PAGE 12 OF 21 NUCLEAR ENERGY SERVICES, INC.

3. The temperature of the calibration block shall be within 250F of the i component temperature. Calibration block and component temperatures shall be recorded on the Calibration Data Sheet.

4. The identity of the calibration block used for performing calibration shall be recorded on each Calibration Data Sheet. l l

9. EXAMINATION PROCEDURES  !

l 9.1 SCAN LAYOUT (360 AROUND EACH NOZZLE) FOR SHELL SIDE EXAMINATIONS

1. Using a suitable marker the ultrasonic examiner shall mark, in 10 increments, skew lines are necessary to aid in maintaining a tangential

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alignment with the nozzle inner radius area.

2. There should be as many divisions as necessary to visually aid the l

ultrasonic exami'n er to maintain a 25% overlap.

3. Refer to Figure 3 for scan path distances and tangential (skew) angles. .

9.2 ANGLE BEAM EXAMINATION OF THE NOZZLE INNER RADIUS AREAS l

1. Scanning Sensitivity for Examinations Performed from the Shell A. Select the proper tangential (skew) angle for the nozzle to be i examined.

B. Position the search unit at the 0 reference pcint of the nozzle, then using the sensitivity control, adjust the cladding interface signal response level to 20% FSH for cl$d nozzles.

l C. Record this sensitivity and the nozzle identification in the comments e section of the Calibration Data Sheet.

i l l

FORM e NE$ 8@@ 8/b@

DOCUMENT NO. 80A7616 mar PAGE 13 OF 21 NUCLEAR ENERGY SERVICES, INC.

D. During scanning adjust sensitivity as required to maintain a nominal 20% cladding interface response level signal for 360 around nozzle.

Record changes in sensitivity and corresponding nozzle reference datum.

E. All indications shall be recorded at the scanning sensitivity.

2. Scanning Sensitivity for Examinations' Performed from the Barrel A. Using the initial sensitivity established in paragraph 8.2, add 20 dB.

This is the scanning sensitivity. All indications shall be recorded at the scanning sensitivity.

B. Record this sensitivity and the nozzle identification in the comment ,

section of the Calibration Data Sheet.

1

3. Scanning Procedures A. With the transducer at the proper tangential (skew) angle (CW or CCW), scan the inner radius area 360 around the nozzle following the layout lines and scan paths limits.

, B. Transducer movement shall not proceed onto the OD radius blend of I l the nozzle. The radius blend does not permit proper angle entry of  !

the sound.

C. Repeat the foregoing paragraphs for the o'pposite tangential (skew) angle to complete the scanning requirements of two directions for each Nozzle Inner Radius area.

D. All information shall be recorded on the appropriate Data Sheet (s) and the Data Sheet (s) shall be annotated as follows: Shell Scan for examinations performed from the shell, or Barrel Scan for examinations performed from the barrel.

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DOCUMENT NO. 80A7616 11 = NUCLEAR ENERGY SERVICES, INC.

10. EVALUATION CRITERIA 10.1 RECORDING OF INDICATIONS NOTE: All signals to be recorded must have metal path movement. Metal path movement of a signal is when the indication " walks" across the screen in a continuous sweep. For nozzles with cladding, the signal must be above the

" clad roll."

1. All indications, during shell side examinations (Zone 1), within the zone specified for the nozzle inner radius area being examined showing a signal amplitude response 150% FSH (at the scan sensitivity) shall be recorded on the appropriate examination data sheet at the time of examination.

l 2. All indications, during ' irrel side examinations (Zone 2), within the zone specified for the nozzle inner radius area being examined showing a signal amplitude response 120% FSH (at the scan sensitivity) shall be recorded on k the apprppriate examination data sheet at the time of examination.

3. In addition to the requirements of 1 and 2, the examiner shall record all indications considered relevant for further evaluation.

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4. All indications from.all barrel side and shell side examinations shall be .

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reported in inches and degrees CW or CCW from the datum point when  !

looking towards the vessel and in inches away from the shell (for barre!

side examinations) or away from the nozzle barrel (for shell side examinations) to the search unit exit point.

10.2 EVALUA TION OF INDICA TIONS

1. Evaluation of all indications shall be rnade at the scan sensitivity and in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Article IWA-3000. In addition, indications shall be evaluated, with respect to the notch responses obtained in the calibration blocks for informational purposes at the initial sensitivity.

FORM a NES 20s 2180

DOCUMENT NO, 8017616 NUCLEAR ENERGY SERVICES, INC.

2. The results of this evr'uation shall be reported to the Plant Owner, or his Agent, in accordance with the requirements of the referenced ASME Boiler and Pressure Vessel Code,Section XI, Article IWA-6000. All evaluations shall be performed by a LevelIII Examiner.

11. EXAMINATION RECORDS 11.1 CERTIFICATION OF RECORDS The Examiner (s) shall complete and sign the appropriate scan data sheet (s) immediately upon the completion of each nozzle inner radius area examination, noting applicable NDE certification levels.

11.2 FILING OF RECORDS

1. Records of personnel qualifications shall be maintained by the Examination Contractor.

2. The Examination Contractor shall be r sponsible for submitting to the Plant Owner, or his Agent, a completely documented set of examination records, including certification of personnel qualifications with a current ,

eye test report.

11.3 PROCEDURE CORRECTIONS AND ADDITIONS All procedure corrections and/or additions required during the examinations may be initiated by either the Owner or the NES Site Supervisor. All such changes shall have the approval of the Plant Owner, or his Agent, and an NES Level III and the Authorized Inspector shall be notified of such changes and their approval obtained as required.

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l FORM # NES 205 2/80 u

, DOCUMENT NO. 80A7616 {

PAGE lb 0F 21 NUCLEAR ENERGY SERVICES, INC.

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ZOIE 1 l Barrel Side - kW ZOIE 2 1

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4 Shell Side FIGURE 1. PICTORIAL VIEW OF THE ULTRASONIC EXAMINATION OF THE N0ZZLE INNER RADIUS AREA FROM THE SHELL SIDE AND THE N0ZZLE SIDE (CUT-A-WAY VIEW).

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i DOCUMENT NO. 80A7616 NUCLEAR ENERGY SERVICES, INC.

PAGE II OF b Wedge Designation Identifies Examination Arca p-

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\ Sound Path I j' l \ Directed towards l N \ Inner Radius &

Around Barrel

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l FIGURE 2. TYPICAL WEDGE CONFIGURATION USED FOR INNER RADIUS EXAMINATION PERFORMED FROM THE BARREL.

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m DOCUMENT NO. 80A7616 10 21 PAGE OF NUCLEAR ENERGY SERVICES, INC.

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• For "B" dimension scan as far as geometry permits, i.e. radius blend

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1. t Maintain accurate Scanning approach 25% overlap 3600 \F ~F Transducer Scanning direction approach around each nozzle left and '

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Nozzle OD Radius FIGURE 3. ULTRASONIC EXAMINATION OF N0ZZLE INNER RADIUS AREAS FroRM c MF2ffggg.g)

DOCUMENT NO. 80A7616 NUCLEAR ENERGY SERVICES, INC.

LATER l

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I Calibration Block for Shell Side Examinations D

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Calibration Block for Barrel Side Examination FIGURE 4 ULTRASONIC EXAMINATION CALIBRATION BLOCKS WM # 6$5@ 8/4@

mr Document No. 80A7616 11 NUCLEAR ENERGY SERVICES, INC.

Project No. tJo zzle : Azimuth Date '

la Plant Skew Angle Cal Data Pkg.

Unit Wedge I.D.:

Cal. Block: Scanning dB: Reference db page 9n of 21 tiP - Metal Path g g, Lo - 0* Datum Wo - Nozzle Barrel Lm - Distance from Lo at max. response Wm - Distance from Wo at max. response ,

f L1 - Distance from Lo at 50% Endpoints W1 - Distance from Wo at 50% Endpoints Ji L2 - Distance from Io at 50% Endpoints W2 - Distance from Wo at 50% Endpoints ," ' d, I i

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W. NAX. INBOARD OUTBOARD L MAX. CCW CW p

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11 0 . D7sC W MP W1 MP W2 MP L MP L1 MP L2 MP REMARKS Note: All measurements are to be taken from transducer centerline EXAMINER Level Date Sketch:

EXAMINER Level Date REVIEWER Date FIGURE 5. k .

Document IIo. 60A7616 NUCLEAR ENERGY SERVICES. INC.

Project No. Nozzle: Date (Day /Mo./7 ear) L.

Plant Azimuth: Page 21 of 21 L.,

Unit Wedge I.D.:

Attached Cal. Data Sheet +

Cal. Block: Scanning dB:

W.

MP - Metal Path W:

Lo - 0* Datum Wo - Vessel Shell w,, _

Lm - Distance from Lo at max. response Wm - Distance from Wo at max. response - W, L1 - Distance from Lo at 50% Endpoints W1 - Distance from Wo at 50% Endpoints .A L2 - Distance from M at 50% Endpoints W2 - Distance from Wo at 50% Endpoints . h W. MAX. ItiBOARD

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OUTBOARD L MAX. CCW CW r

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IND. of NO. DAC W MP W1 MP W2 MP L MP L1 MP L2 MP REMARKS Note: All measurements are to be taken to transducer centerline.

Sketch:

Examiner Level Date Examiner Level Date Reviewer Date Reviewer Date Reviewer Date m une a. /N _ _

F ENCLOSURE 3 i

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