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POWER AUTHORITY OF THE STATE OF NEW YORK,

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QUALITY ASSURANCENONDESTRUCTIVE EXAMINATION

PROCEDURE -

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TITLE *ULSTASONIC EXAMINATION PROCEDURE FORTHE DETECTION OF INTERGRANULAR STRESS 9,4_7CORROSION CRACKING (IGSCC)

APPLICABILITY REVISION :

NUCLEAR POWER PLANTS 1

DATEAPPROVAL ,,-

NDE - LEVEL III

CONCURRENCE DATEh/ $ --_ - --_

3/25/82- -

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.- VICE PREdlDENT - QUALITY ASSURANCEl

SUPERCEDESREV. O, 2/10/82

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POWER AUTH2RITY CF THE STATE CF NEW YORK 9'NDEP:

QUALITY ASSURANCE 3n5/82DAT E:" NONDESTRUCTIVE EX AMIN ATION 1

> REVISION:PROCEDURE

ULTRASONIC EXAMINATION PROCEDURE EVR THE DETECTIONOF INTERGRANULAR STRESS CORRGSION CRACKING (IGSCC)

1.0 PURPOSE

This procedure delineates the technique whereby ultrasonic examination bymanual pulse / echo techniques may be performed on stainless steel pipingfor intergranular stress corrosion cracking (IGSCC).

2.0 APPLICABILITY

2.1 Area of Examinations

This document covers the ultrasonic examination procedures ofstainless steel piping for intergranular stress corrosion cracking(IGSCC) . IGSCC is typically detected in the area between the weldheat affected zone and a point 1/2 inch outward.

2.2 Type of Examination

i 2.2.1 Volumetric examination shall be performed using ultrasonicpulse echo nominal 45* angle beam shear wave and O'longitudinal straight beam techniques applied to the outsidesurfaces of the piping.

2.2.2 The examination shall be performed using manual search units(transducers).

2.3 Time of Examination

This procedure shall govern the examin.". tion and re-examin.stion ofrepaired areas of the pipe as required by the Nuclear Regulatory.Cbmmission.

2.4 Weld Configuration

2.4.1 The typical weld configurations and areas of IGSCC coveredby this procedure are shown Figures 1 and 2.

2 2.4.2 Nominal weld thicknesres range from 0.120" to 1.125".

2.5 Materials

The piping is constructed for austenitic stainless steel.,

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YGRK NDEP' 9*4-7- g POWER AUTHORITY OF THE STATE OF NEWQUALITY ASSURANCE*

# ' . 1/ 2 5 , a ._.,

'' " NONDESTRUCTIVE E X AMIN ATION

nE VISION: 1PROCEDURE

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2.6 Examination Intent;

This procedure is intended to cover the piping ID surface adjacentto welds. We are interested in the detection of cracks whichoriginate at the ID surface. The outside surf ace of each weld willbe examined by the liquid penetrant method.

3.0 REFE RENCES

The following documents form a part of this examination procedure

3.1 ASME Doiler and Pressure Vessel Code, Section XI, 1974 Edition,

Appendix III and supplements of the 1975 Winter Addenda.

3.2 Electric Power Research Institute ( EP RI ) , Project Report 092 (1/79)

" Workshop on In-Service Inspection of Stainless Steel Piping inNuclear Systen.s."

3.3 Electric Power Research Institute ( EP RI ) , " Seminar on

Countermeasures for DWR Pipe Cracking." Jan 22, 23, 24, 1980Session #8.

i 3.4 Electric Power Research Institute ( EP RI ) , Special Report - Project892, Aug. 1979 EPRI NP-ll53.

3.6 ASNT Recommended Practice, SNT-TC-1A, 1975 Edition.

3.7 PASNY Procedure for " Ultrasonic Instrument Linearity Procedure", as

modified by paragraph 5.11.2 of this procedure.

3.8 USNFC Bulletin 79-17 (7/26/79).

3.9 PASNY Procedure for Nondestructive Examination PersonnelQualification and Certification NDEP 1.1.

3.10 ASME - Section III Appendix IX %dh

5.0 G ENE RAL*

5.1 Personnel Requirements

5.1.1 All personnel performing the nondestructive examinations in~ accordance with this procedure shall be qualified and.

certified to at least Level I in accordance with SNT-TC-1Aand NDEP 1.1 Procedure for Qualification and Certification ofNondestructive Examination Personnel.

*The examination procedures described in this document comply withSection XI, Appendix III of the ASME Boiler and Pressure Vessel Code,1974 Edition, including the winter, 1975 Addenda except where examinationc ove ra ge is limited by part geometry or access.

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POWER AUTHORITY OF THE STATE OF NEW YORK 9.4-7NDEP.

' OUALITY ASSURANCE 3f3,u""'" NONDESTRUCTIVE EX AMIN ATION 1 i

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REVISION: 1

PROCEDURE il

NOTE: At least one member of each examination crew shallhave a minimum qualification of Level II. A Level II or IIIindividual shall be responsible for witnessing the finalinterpretation on all ultrasonic examinations. He shall beresponsible for the recording and acceptance of required dataon ultrasonic examination reports.

I 5.2 Equipment

5 . 2 .1 Pulse-echo ultrasonic equipment (Krautkramer USM2, Sonic MK1,Sperry Type UM, UJ or equivalent) shall be used. The ultra-

[sonic instrument shall be equipped with a fine gain and/orattentuation control calibrated in units no larger than 2dB.'

5.2.2 Search Units

5.2.2.1 Straight beam examination shall be performed using aceramic, lithium sulfate, or barium titanate 5.0 MHZnominal frequency to provide greater resolution andto minimize beam spread.

15.2.2.2 Angle beam examination shall be performed using a

lead metaniobate 1.5 MNZ 45' (+.5 degrees ) angle

beam single or dual element search unit as stated

ibelow. The effective size of the single element

units shall be .25" or .5". The effective area ofthe dual element units shall be 1/4" x 1/2" or 3/8"x 3/4 " .

5.2.2.3 Exit Point: A standard IIV block will be usedbefore examinations are performed each day to verifyor correct the exit point on the transducer shoe,

5.2.2.4 Beam Angles After the exit point has beendetermined, the beam angle shall be checked with the

IIW block to confirm that the transducer meets thej

angle ranges specified in 5.2.2.2.

5.2.2.5 Wedge Rework: Any transducer wedge not providing_

the angle tolerances specified in 5.2.2.2 shall be-

reworked and the measurements specified in 5.2.2.3~

and 5.2.2.4 repeated until the unit complies withthe tolerances.

5.2.2.6 Shear Wave: A 45 degree beam shall be used.

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PCWER AUTHERITY CF THE STATE GF NEW YORK g,4_7p.

OUALITY ASSUR ANCE3!:b/8:"# E : -" NONDESTRUCTIVE EX AMIN ATION 1REVISION'

PROCEDURE

5.2.2.7 At the discretion of the Level III, transducers ofdifferent size, shape, and frequency may be used aspermitted by Section III, Appendix IX. Thesechanges shall be documented on the data sheets.

5.2.2.8 When variables such as weld preparation, weld crownwidth, or physical interference preclude 1/2 Vee !

path examination of the weld root, and when thesevariables are such that the distance from the soundbeam exit point on the search unit to the weld(root) centerline is, greater than 0.93t, the beam jpath shall be increased at least 1 Vee path.Alternately, the interference may be eliminated by:

1. Reducing the dimension of the wedge edge-to-beamexit pointt

2. Reducing search unit size;3. Increasing beam angle.

5.2.2.9 Cable Type and length shall be recorded on the <j)calibration data sheet.

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5.3 Miniature Angle Beam Calibration Standard

5.3.1 As per Figure #4.

5.4 Thermometer

5.4.1 Calibrated for +5% of reading; calibrated every 3 months max.,

5.5 Wedges - 45' Shear and Longitudinal,1/4" and 1/2"

5.5.1 Lucite-type for single element transducer.

5.6 Surface Preparation:

The examination surface shall be free of dirt, loose scale,machining or grinding particles, weld spatter, or other looseforeign matter. The surface finish shall be sufficiently smooth tomaintain acoustical bond minimize surface noise. A mill finish may

be adequate for testing.

5.7 Couplant:

A suitable liquid, semi-liquid, or paste couplant medium such aswater, oil, glycerin, grease, or llamikleer shall be applied to theexamination surf ece. Each batch of materials used on stainlesssteels or nickel base alloys shall have been tested for residual

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YORK '' * * 7

gsj@ POWER AUTHORITY OF THE STATE OF NEW NDEP:QUALITY ASSURANCE

3/25/s2**TE: -' " NONDESTRUCTIVE E X AMIN ATI ON 1REVISION:PROCEDURE

2. Observe signal shape, behavior, and search unit distancefrom the weld centerline. This will yield information asto the nature of the indication. Make notes of yourobservations during the recording process.

8.2 Plotting of Indications

All recorded indications shall be plotted full scale on Figure 9 or

on graph paper in the following manndr:

1) Trace the O.D. contour from the contour gauge.

2) Plot the thicknesses.

3) Connect the thickness points to reevonstruct the I.D. contour.

and "W " dimensions on the"W ",4) Plot the "W max", i 2applicable side of the weld.

5) All the "W max" position use a protractor to lay out the actualpath to the indication origin by measuring along the metal path.i

6) For the forward measurements (W1) use an angle which is 3degrees less than the "W max" angle, this allows a reasonableamount for beam spread. Plot the metal path to termination.

7) For the background measurements (W2) use an angle which is 3degrees greater than the "W max" angle. Plot the metal path totermination.

8) Connect the 3 metal path termination points to reconstruct theshape of the reflector.

8.3 Evaluationm of Indications

8.3.1 Indications where plots confirm that they are caused bygeometry shall be marked as such.

|0.3.2 Indications where plots confirm that they are cracks shall be

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reported to the examination supervisor who will notify the.

Plant Owner within 24 hours.

8.3.3 Indications where plots yield inconclusive information shallbe reported to the examination supervisor for disposition.

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PSWER AUTHORITY CF THE STATE OF NEW YORK "* MNDEP'

OUALITY ASSURANCE^I'.'

3 / 2 5 /n ''"NONDESTRUCTIVE E X AMIN ATI ON 1REVISION:

PROCEDURE |

9.0 EXAMINATION RECORDS

9.1 Certification of Records

The Examiner shall complete and sign all data 1 sheets immediatelyupon the completion of each weld examination. The data sheets maybe reviewed by the Authorized Code Inspector.

9.2 Record of Examination Results: A copy of the examination data shallbe provided the Authority with the following information:

A. Contract NumberD. Examination PersonnelC. InstrumentD. Method of TestE. CouplantF. Calibration SheetsG. Weld Identification and Iocation11 . Type, Size, and Frequency of Search UnitI. Ultrasonic Wave ModeJ. Calibration Block Number

'K. Chart of ResultsL. ProcedureM. Date(s ) of ExaminationN. Examination SurfaceO. Layout of Weld Seams

9.3 Reports

9.3.1 A detailed ,1trasonic examination report she.ll be preparedusing Indication Data Sheet and any additional sketches orphotographs as may be applicable. If no reportable indica-tions are detected, it shall be so noted on report form.

All final Data Sheets shall be in black ink.

TO DE INSERTED:

ATTACHMENT (FIGURE) #1 THROUGII 9._-

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ATTACHMENT NO. 5

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RECIRCULATION SYSTEM

STRESS RULE INDEX

0-1.20 1.2'-1.50 1.51-2.00 > 2.018 3

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} 12-4::-s* : ::-) 12-c::-:: 12-106 12-8 1;-6e;2-2F

12-9 10-70 12-7622-23 '

28-27 12-13 12 '1o 28-30 12-14 1;-77n

26-49' 12-18o28-50 12-19-

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4-33 28-31 4-38 28-52 4-42 12-6122-6 \ 22-5 28-32 (1) 4-47 28-88 4-43 12-67-

U 22-63 '22-11 28-J6 (1) 4-10; 28-111* 4-97 1 -7:o 22-80 22-16 28-53 12-25 4-96 12-78

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o 22-21 28-85 | 12-83 12-158 22-52 28-89 1 12-SJ 12-200 22-68 29-90 (1) I 22-?) 12-26

$ 22 9 28-103 (1) 22-S':2-06 :8-;.: ; I'EC CN III

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*Carben kncwn for only one wrou-ht ec.epe n e n t of a we;' ? cant. Tapandir? on the carbon ecntent

of the other base raterial, the posit 10n in the ratr;x m y change. scast raterial as exempted)

(1) Pypass weldalet{

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LEGEND: xx-y

indiviacal weld numberynominal pipe diameter

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ATTACHMENT.NO 6

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3.6 (cont'd) 4.6 (can't)

4. Except as specified in 3.6.C.3 above,the reactor coolant water shall notexceed the following limits with steam-ing rates greater than or equal to100,000 lb/hr and during reactor shut-downs.

Conductivity 5 unho/cnChloride ion 0.5 ppm

5. If Specification 3.6.C cannot be met,the reactor shall be placed in a coldcondition within 24 hours.

D. Coolant Leakage 4.6.D Coolant Leakage

1. Anytime irradiated fuel is in the Reactor coolant leakage rate inside thereactor vessel and the reactor coolant primary containment shall be establishedtemperature is above 2120F, the reactor once/ day utilizing the Equipnent and Floorcoolant leakage into the primary con- Drain Sump Monitoring Systems.tainmbnt shall be limited to:

a. 5 gpm unidentified leakage

b. 9 gpm increase in unidentifiedleakage within any 24 hour period.(This limitation shall apply onlyafter a period of 24 hours at oper-ating pressure.)

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c. The total reactor coolant leakageinto the primary containment shallnot exceed 25 gpm.

|2. With any reactor coolant system leakage

greater than any one of the limits speci-fied in a. or c. above, the leakage rate -

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shall be reduced to within the limits

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3.6 (cont'd) 4.5 (cont'd)within 4 hcurs or the reactor shall bein at least the hot standby conditionwithin the following 12 hours and in cold

condition within the next 24 hours. i'

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f|.3. If the increase in unidentified leakage

}as speci fied in 3.6.D.1.b is exceeded, the 'source of the leakage shall be identified

within 4 hours or the reactor shall bein at least tot standby condition within

the next 12 hours and in cold conditionwithin the following 24 hours.

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4. The following reactor coolant systemIcakage detection systems shall be

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operable during reactor power I

operation:

a. Drywell Sump Monitoring System(equipment drain sump monitoringand floor drain sump monitorino),

b. Drywell Continuous Atmosphere(particulate) RadioactivityMonitoring System, and

c. Drywell Continuous Atmosphere.

(gaseous) Radioactivity MonitoringSystem. |

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3.6 (cont'd) JAFNPP 4.6 (cont'd)

5. With only two of the leakagei

detection systems operable(3.6.D.4), operation may |continue for up to 30 daysprovided grab samples of thedrywell atmosphere are obtained 3. Drywell Continuous Atmospherearol analyzed at least once per Dadioactivity Monitoring System24 hours when the required gaseous instrumentation shall be funct-or particulate monitoring system fonally tested and calibrated asis inoperable; otherwise, be speci fied in Table 4.6-2.in at least hot shutdown withinthe next 12 hours and in coldnhutdown within the next 24 hours.

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Amendennt No. 142 i-

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