ML20070M781

Ultrasonic Exam Procedure for Detection of Intergranular Stress Corrosion Cracking (Igscc)

ML20070M781
Person / Time
Site:	FitzPatrick
Issue date:	03/25/1982
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20070M761	List: ML20070M759 ML20070M771 ML20070M781
References
RTR-NUREG-0313, RTR-NUREG-313 9.4-7, NUDOCS 8301250331
Download: ML20070M781 (13)

Text

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.- 1 POWER AUTHORITY OF THE STATE OF NEW YORK ,

l QUALITY ASSURANCE NONDESTRUCTIVE EXAMINATION PROCEDURE -

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TITLE ULSTASONIC EXAMINATION PROCEDURE FOR THE DETECTION OF INTERGRANULAR STRESS 9,4_7 CORROSION CRACKING (IGSCC)

APPLICABILITY REVISION :

NUCLEAR POWER PLANTS 1 APPROVAL ,,- DATE NDE - LEVEL III CONCURRENCE DATE h/ $ --_ - -- -

3/25/82 l .- VICE PREdlDENT - QUALITY ASSURANCE SUPERCEDES REV. O, 2/10/82 l

l D DO O O 03 3 l - P PDR

POWER AUTH2RITY CF THE STATE CF NEW YORK NDEP:

9' QUALITY ASSURANCE 3n5/82

" DAT E:

NONDESTRUCTIVE EX AMIN ATION 1

> REVISION:

PROCEDURE ULTRASONIC EXAMINATION PROCEDURE EVR THE DETECTION OF INTERGRANULAR STRESS CORRGSION CRACKING (IGSCC) 1.0 PURPOSE This procedure delineates the technique whereby ultrasonic examination by manual pulse / echo techniques may be performed on stainless steel piping for intergranular stress corrosion cracking (IGSCC).

2.0 APPLICABILITY 2.1 Area of Examinations This document covers the ultrasonic examination procedures of stainless steel piping for intergranular stress corrosion cracking (IGSCC) . IGSCC is typically detected in the area between the weld heat affected zone and a point 1/2 inch outward.

2.2 Type of Examination i 2.2.1 Volumetric examination shall be performed using ultrasonic pulse echo nominal 45* angle beam shear wave and O' longitudinal straight beam techniques applied to the outside surfaces 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 of repaired 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 covered by 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.

Page 1 of 12

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

• QUALITY ASSURANCE

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

NONDESTRUCTIVE E X AMIN ATION nE VISION: 1 -

PROCEDURE

2.6 Examination Intent This procedure is intended to cover the piping ID surface adjacent to welds. We are interested in the detection of cracks which originate at the ID surface. The outside surf ace of each weld will be 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 in Nuclear Systen.s."

3.3 Electric Power Research Institute ( EP RI ) , " Seminar on Countermeasures for DWR Pipe Cracking." Jan 22, 23, 24, 1980 Session #8.

i 3.4 Electric Power Research Institute ( EP RI ) , Special Report - Project 892, 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 Personnel Qualification 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

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accordance with this procedure shall be qualified and certified to at least Level I in accordance with SNT-TC-1A and NDEP 1.1 Procedure for Qualification and Certification of Nondestructive Examination Personnel.

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

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POWER AUTHORITY OF THE STATE OF NEW YORK NDEP.

9.4-7 OUALITY ASSURANCE 3f3,u NONDESTRUCTIVE EX AMIN ATION

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1 i REVISION: 1 PROCEDURE i l

NOTE: At least one member of each examination crew shall have a minimum qualification of Level II. A Level II or III individual shall be responsible for witnessing the final interpretation on all ultrasonic examinations. He shall be responsible for the recording and acceptance of required data on 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-

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

5.2.2 Search Units 5.2.2.1 Straight beam examination shall be performed using a ceramic, lithium sulfate, or barium titanate 5.0 MHZ nominal frequency to provide greater resolution and to minimize beam spread.

1 5.2.2.2 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 i

below. The effective size of the single element units shall be .25" or .5". The effective area of the 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 used before examinations are performed each day to verify or correct the exit point on the transducer shoe, 5.2.2.4 Beam Angles After the exit point has been determined, the beam angle shall be checked with the IIW block to confirm that the transducer meets the j

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

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reworked and the measurements specified in 5.2.2.3 and 5.2.2.4 repeated until the unit complies with the tolerances.

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

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s PCWER AUTHERITY CF THE STATE GF NEW YORK p. g,4_7 OUALITY ASSUR ANCE 3!:b/8:

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" NONDESTRUCTIVE EX AMIN ATION 1 REVISION' PROCEDURE 5.2.2.7 At the discretion of the Level III, transducers of different size, shape, and frequency may be used as permitted by Section III, Appendix IX. These changes shall be documented on the data sheets.

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

path examination of the weld root, and when these variables are such that the distance from the sound beam exit point on the search unit to the weld (root) centerline is, greater than 0.93t, the beam j path shall be increased at least 1 Vee path.

Alternately, the interference may be eliminated by:

1. Reducing the dimension of the wedge edge-to-beam exit 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.

I 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 loose foreign matter. The surface finish shall be sufficiently smooth to maintain 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 as water, oil, glycerin, grease, or llamikleer shall be applied to the examination surf ece. Each batch of materials used on stainless steels or nickel base alloys shall have been tested for residual Page 4 of 12

o YORK NDEP:

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• 7 gsj@ POWER AUTHORITY OF THE STATE OF NEW QUALITY ASSURANCE 3/25/s2

" **TE: -

NONDESTRUCTIVE E X AMIN ATI ON 1 REVISION:

PROCEDURE

2. Observe signal shape, behavior, and search unit distance from the weld centerline. This will yield information as to the nature of the indication. Make notes of your observations 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.

4) Plot the "W max", "Wi ", and "W2 " dimensions on the applicable side of the weld.

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

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

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

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

8.3 Evaluationm of Indications 8.3.1 Indications where plots confirm that they are caused by geometry shall be marked as such.

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

. reported to the examination supervisor who will notify the Plant Owner within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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

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PSWER AUTHORITY CF THE STATE OF NEW YORK NDEP'

"* M OUALITY ASSURANCE 3 / 2 5 /n

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NONDESTRUCTIVE E X AMIN ATI ON 1 REVISION:

PROCEDURE l 9.0 EXAMINATION RECORDS 9.1 Certification of Records The Examiner shall complete and sign all data 1 sheets immediately upon the completion of each weld examination. The data sheets may be reviewed by the Authorized Code Inspector.

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

A. Contract Number D. Examination Personnel C. Instrument D. Method of Test E. Couplant F. Calibration Sheets G. Weld Identification and Iocation 11 . Type, Size, and Frequency of Search Unit I. Ultrasonic Wave Mode J. Calibration Block Number K. Chart of Results L. Procedure M. Date(s ) of Examination N. Examination Surface O. Layout of Weld Seams 9.3 Reports 9.3.1 A detailed ,1trasonic examination report she.ll be prepared using Indication Data Sheet and any additional sketches or photographs 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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1 ATTACHMENT.NO 6 I

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. - w JAFWrp fj ti 3.6 (cont'd) 4.6 (can't)

4. Except as specified in 3.6.C.3 above, the reactor coolant water shall not exceed the following limits with steam-ing rates greater than or equal to 100,000 lb/hr and during reactor shut-downs.

Conductivity 5 unho/cn Chloride ion 0.5 ppm

5. If Specification 3.6.C cannot be met, the reactor shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. Coolant Leakage 4.6.D Coolant Leakage

1. Anytime irradiated fuel is in the Reactor coolant leakage rate inside the reactor vessel and the reactor coolant primary containment shall be established temperature is above 2120F, the reactor once/ day utilizing the Equipnent and Floor coolant leakage into the primary con- Drain Sump Monitoring Systems.

tainmbnt shall be limited to:

a. 5 gpm unidentified leakage

b. 9 gpm increase in unidentified leakage within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

(This limitation shall apply only after a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at oper-ating pressure.) ,

c. The total reactor coolant leakage into the primary containment shall not exceed 25 gpm.

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2. With any reactor coolant system leakage greater than any one of the limits speci-fied in a. or c. above, the leakage rate -

shall be reduced to within the limits 141

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3.6 (cont'd) 4.5 (cont'd) within 4 hcurs or the reactor shall be in at least the hot standby condition within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '

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3. If the increase in unidentified leakage as speci fied in 3.6.D.1.b is exceeded, the fl.

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source of the leakage shall be identified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the reactor shall be in at least tot standby condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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4. The following reactor coolant system Icakage detection systems shall be

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operable during reactor power I operation:

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

b. Drywell Continuous Atmosphere (particulate) Radioactivity Monitoring System, and

c. Drywell Continuous Atmosphere .

(gaseous) Radioactivity Monitoring System. l l

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

5. With only two of the leakage i detection systems operable (3.6.D.4), operation may l

continue for up to 30 days provided grab samples of the drywell atmosphere are obtained 3. Drywell Continuous Atmosphere arol analyzed at least once per Dadioactivity Monitoring System 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous instrumentation shall be funct-or particulate monitoring system fonally tested and calibrated as is inoperable; otherwise, be speci fied in Table 4.6-2.

in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold nhutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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- Amendennt No. 142 i i

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