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{{#Wiki_filter:}} | {{#Wiki_filter:A ULE ASONIC EXAMI!aTION rW ' | ||
SUBJECT CF WEEDS IN PIPE adams EASTERN SERVICE DEPARTMENT I pn f ,"n* ho P.B. 83-1 REV. 4PAGE 10F | |||
( a**y,Q,*,*g4a"'o PREPARED 8Y/DATE f. f- , , 3 /h/8 "S PEA 01 BCTI'KM A'KHIC POWER STATION /(,[8 * - | |||
APPROVED BY/DATE (( , | |||
OA APPROVED BY/DATE jh p/ 3 Attachment 1 I)ocket no 50 277 May 23, 1933 l Exhibit 1 - | |||
I STATEMENT OF INIDOED USE l | |||
THIS DOQJMENT CDNTAI!6 INEOiWiPION PREPARED BY 'INE GENERAL ELECIRIC ODMPANY FOR' WE PHIIADELPHIA ELECTRIC CIEPANY NO IS INTE20ED POR USE BY WE EMPIDYEES OF B0frH COMPANIES. IT IS SUBMITTED 'IO THE PHIIADELPHIA ELBCIRIC COMPAW UPON 'INE CONDITION 'IHi IT WILL BE USED IN 'IHE (DtOUCT OF PHIIADELPHIA ELECTRIC CDMPANY INTERNAL TEDINICAL WRi MO WILL N3r IE RELEASED BY 'IHE PHILADELPHIA ELECIRIC CDMPAW 'IO COMPE'rI'IORS OF 'IEE l GENERAL ELECIRIC CIEPANY, WILL N7f BE DISEIBUTED EOR GENERAL IMXJSTRY MO WILL PM BE USED DIRECTIX OR ItOIRECILY IN AN UNFAIR CJMPETTITIVE MANNER 'IO 'IME INTERESTS OF EE GENERAL ELECTRIC COMPANY. | |||
I i PROCEDURE GAPGES OIA?GES 'IO 'IHIS PROCEDURE WIII, BE MACE IN N WTIE GENERAL F | |||
* ECIRIC QUALITY ASSURA.C MANUAL, AND APPROVED BY PECo DGINEERI!G. | |||
PEID APPROVAL PEED Ergineering Approval ( | |||
D& . ate C 4/ch3 EVIEWED BY7 bd, , | |||
APR 7 1983 PHILA. ELECTRIC CO. | |||
INSa.'.'i; a * 'CPECTION | |||
( | |||
8306020303 830323 PDR ADOCK 05000277 P PDR G EN ER AL h ELECTRIC | |||
aro No P.B. 83-1 Revision No 4 Page: 1A of 20 f 'Ev'."." ens - | |||
: ;q, I (, | |||
. .m. . .. | |||
gy pg i | |||
i i | |||
l PAGE REVISION IWIE CCM4ENTS | |||
* 1 4 03/14/83 Opver Page | |||
* 1A 4 03/14/83 List of Effective Pages i | |||
2 0 12/01/82 3 2 01/03/83 | |||
* 4 3 03/14/83 5 0 12/01/83 s 6 0 12/01/82 7 3 02/04/83 | |||
'( 8 1 12/03/82 9 3 02/04/83 10 1 12/03/82 11 3 0.2/04/83 12 1 12/03/82 13 0 12/01/82 14 2 01/03/83 15 2 01/03/93 ., | |||
16 2 01/03/83 17 2 01/03/83 . | |||
18 2 01/03/83 19 2 01/03/83 20 2 01/03/83 | |||
( . | |||
GEN ER AL h ELECTRIC | |||
*' Procedure No. P.B. 83-1 | |||
- 1 Revision No. 0 | |||
**""" Page 2 of 20 mwisiiis | |||
( l% | |||
::=.=== | |||
1.0 SCOPE 1.1 The ultrasonic pulse echo contact method examination described herein is applicable to full penetration circumferential and longt tudinal welds in piping systems. | |||
1.2 The appitcable material thickness range is from 0.200 to 2.50 inches. | |||
1.3 This procedure covers angle beam shear wave ultrasonic examination of piping welds and a straight beam longitudinal wave examination of piping base material through which the angle beam passes. | |||
2.0 APPLICABLE DOCUMENTS 2.1 Codes and Standards. The following documents form a part of this specification to the extent specified herein. | |||
: a. American Society of Mechanical Engineers (ASME) Bailer and Pressure Vessel Code | |||
( | |||
(1) Section Y. Nondestructive Examination, Article 5,1974 Edition, Sumer 1975 Addenda (2) Section XI, Inservice Inspection of Nuclear Power Plant Components,1974 Edition, Sumer 1975 Addenda | |||
: b. American Society for Wondestructive Testing (ASNT) | |||
(1) Recomended Practice for Nondestructive Testing Personnel Qualification and Certification, SNT-TC-1A, Ultrasonic Testing Method - 1975 Edition | |||
==3.0 DESCRIPTION== | |||
3.1 The objective of the methods given herein is the location and recording of indications within the counter bore area, the heat affected zone, the fusion zone and the base material within two thicknesses (2T) of the weld. The examination shall be perfonned | |||
- from the outside surface of the piping system. | |||
4.0 REQUIREMENTS 4.1 Personnel 4.1.1 All personnel performing ultrasonic examinations shall be | |||
( certified to at least Level I in accordance with SNT-TC-1 A, Ultrasonic Testing. Level I personnel shall perform the examination under the direction of personnel certifled to Level II or III. | |||
GEN ER AL $ ELECTRIC | |||
Procedure No. P.B.03-1 ag of 20 senwicek | |||
#83 n | |||
TifM*.E" | |||
~ | |||
4.1.2 All personnel reviewing the results of the ultrasonic examinations shall be certified to at least Level II in accordance with SNT-TC-1 A, Ultrasonic Testing. | |||
4.1.3 When actual samples containing IGSCC are available at the jobsite, all inspection teams shall be trained on these samples prior to their perfoming any actual examinations. | |||
The purpose of this training is to allow the inspection teams to become familiar with the appearance and behavior of IGSCC indications in welded samples and to demonstrate their proficiency to the satisfaction to the person (s) responsible for evaluating the results of the examinations. The duration of the training shall be at the discretion of the responsible individual ( s) . | |||
4.2 Equipment 4.2.1 Pulse echo ultrasonic equipment shall be used with contact search units. The ultrasonic instrument shall be equipped with a d3 calibrated gain or attenuation control. | |||
t 4.2.2 Angle beam shear wave examination shall be perfomed using single element trasmit/ receive or cual element pitch-catch ceramic type search units having a nominal frequency fran 1.0 to 2.25 MHz. Other frequencies may be used to obtain adequate penetration or resolution. | |||
4.2.2.1 The size and configuration of search units should conform to the chart below. If piping geometry (weld crown width, mismatch, etc.) preclude the use of the recorvnended search unit (s), alternative | |||
,eerch units may be used. The use of any dternative search unit (s) shall be documented as 3, ell as the reason the alternative was necessary. | |||
Pipe Outer Diameter 7I n.) wa ll Thickness (In.) Search Unit Less Than 4.500 Less Than .750 1/4 Dia. or 1/4 sq. Single 1/4 x 3/8 | |||
* Dual Greater Than .750 1/4 x 3/4 | |||
* Dual Over 4.500 Through 12.750 Less Than .750 1/2 Dia. or 1/2 Sq. Single 3/8 x 3/4 | |||
* Dual 1/4 x 3/8 | |||
* Dual Greater Than .750 3/8 x 3/4 | |||
* Dual k 1/4 x 3/8 | |||
* Dual 1/2 Dia. or 1/2 Sq. Single l GEN ER AL h ELECTRIC | |||
I Proceduro No. P.B. 83-1 sawics Revision tb. 3 Page 4 of 20 | |||
< %~ , | |||
(- ::=:== | |||
Pipe Outer Diameter (In.) Wall hickness (In.) Search Unit a | |||
Over 12.750 thru 20.000 Iess han .750 1/2 Dia. or 1/2 Sq. Single 3/8 x 3/4 | |||
* Dual 1/4 x 3/8 | |||
* Dual Greater han .750 3/8 x 3/4 | |||
* Dual 1/4 x 3/8 | |||
* Dual 1/2 Dia. or 1/2 Sq. Single Over 20.000 Iass h an .750 1/2 Dia. or 1/2 Sq. Single 3/8 x 3/4 | |||
* Dual 1/4 x 3/8 | |||
* Dual Greater than .750 3/8 x 3/4 | |||
* Dual 1/4 x 3/8 | |||
* Dual 1/2 Dia. or 1/2 Sq. Single Search units must be qualified on a cracked sample prior to use on piping welds. | |||
i This qualification may take place on site, if a cracked sample is available, or at a location designated by the plant owner. If an alternative search unit is required due to pipirg gecmetry, etc., qualification of the alternative shall be per the direction of the plant owner. | |||
On piping 12.750" OD ard larger, consideration should be given to qualifying the largest size search unit passible to minimize radiation exposure. | |||
Care in selection of the focal length of dual element search units should be exercise:1. he focal point should fall as close as possible to the pipe ID to precltde crossing cuer beyond the focal point. When an examination requires a 1 1/2 vee path calibration focused dual element search units should not be used. | |||
4.2.3 Wedges shall be used to produce shear mve team angles of 45 degrees, + 3 deg. - 3 deg., as determined using the IIW-2 ultrasonic calibration block. Se distance I frcrn the index point of the wedge to the front erd of the vedge should be short enough to permit 1/2 node examination of the near side of the weld root fusion zone without placing the transducer on Se weld reinforcement. Where a 1/2 node examination cannot be | |||
* performed, wedges producing shear wave beam angles up to 70* + 3* may be used or a DAC may be constructed to allow for 1-1/2 vee path examination. . | |||
4.2.4 Couplants. Glycerine, ultra gel - II or Hercules powder 7H and demineralized water shall be used. Alternate couplants require approval by BWRSD Materials Engireering. | |||
4.3 Calibration Blocks | |||
(' 4.3.1 Field Examinations: The primary calibration blocks shall be those provided by the plant owner ard shall meet the requirenents of ASME tion XI. | |||
GENERAL ELECTRIC | |||
Procedure No. P.B. 83-1 Rcvisten No. O amos Page 5 of 20 | |||
( lU S ayE=g;llll' 4.3.2 An !!W-2 ultrasonic calibration bicck shall be used during calibration to establish angle beam index ootnt and beam angle as required in paragraphs 4.4.6.1 and 4.4.6.2. | |||
4.4 Equipment Calibration 4.4.1 Calibration shall include the complete ultrasonic examination system. Any change in search units, test shoes, (wedges), | |||
couplants, cables or ultrasonic instruments shall be cause for recalibration. | |||
4.4.2 The calibration data shall be recorded and plotted for each calibration on the Calibration Data Sheet (Figure 1). These sheets shall be numbered in sequence with the Examination Data Sheets (Figure 2). | |||
4.4.3 Instrument Calibration 4.4.3.1 Laboratory: At the beginning of each period of continuous use, (or every three months, whichever is less), the ultrasonic instrument shall be checked for amplitude linearity and amplitude control linearity per Paragraphs 4.4.4 and 4.4.5, respectively. | |||
4.4.3.2 Field: After any transport of the instruments in any comercial carrier, the instruments shall be checked per Paragraphs 4.4.4 and 4.4.5, respectively. These checks shall also be repeated once each week for the duration of the field examination. | |||
4.4.4 Amplitude Linearity Check An angle beam search unit shall be positioned on a block and signals obtained from two reflectors. The search unit position shall be adjusted to give an exact 2-to-1 ratio of amplitudes between the two. The gain control (sensitivity) shall be adjusted and the larger signal brought to 80 percent of full screen height (FSH), adjust position if necessary, maintaining the 2:1 signal ratio. Without moving the search unit, the gain control shall be adjusted to successively set the larger signal from 100 percent to 20 percent FSH in 10 percent increments.The smaller indication shall be read at each setting. The signal amplitude must be 50 percent of the larger amplitude within five percent of FSH. Instruments | |||
( that do not meet this requirement shall not be used. The data shall be recorded on the calibration data sheet provided. | |||
GEN ER AL $ ELECTRIC | |||
Procedure No. P.B. 83-1 r | |||
wp ' Revision No. O sammes Page 6 of 20 | |||
( < '6E | |||
=.= = | |||
4.4.5 Amplitude Control Linearity Check. The angle beam search unit shall be positioned on a calibration block and a peaked signal amplitude obtained fra a hole. The indication shall be brought as near as possible to 80 percent FSH with the dB control. If necessary, the final adjustment to 80 percent FSH is made with the variable gain control. Using only the dB control, the dB changes indicate ( below shall be made and the resulting amplitude compared with the allowable anplitude limits. The resultant signal must fall within the amplitude limits as specified below. Instruments that do not meet these limits shall not be used. The procedure shall be repeated for the 40 percent and 20 percent FSH amplitudes and the data recorded on the calibration data sheet. | |||
Initial Amplitude dB Control Amplitude Limits Set of % FSH Change % FSH 80 -6 32 to 48 80 -12 16 to 24 40 +6 64 to 96 20 +12 64 to 96 4.4.6 Beam Angle Determination 4.4.6.1 Determination of Angle Beam Index. The angle beam search unit is positioned on the 11W-2 calibration block so the beam is directed toward the four-inch radius surface. Move the search unit parallel to the sides of the calibration block until a maximum echo is obtained from the reflecting radius. The beam index point is now above the center line of the radius. Place a mark on the side of the angle beam wedge to identify the index point. | |||
4.4.6.2 Determination of Beam Angle. Place the angle beam search unit on the IIW-2 calibration block and obtain a peak signal amplitude from the two-inch diameter hole. Read the refracted beam angle from the side of the calibration block using the angle which corresponds with the beam index point and record it on the Calibration Data Sheet. | |||
4.4.7 Sweep Range Calibration The calibration block shall be used to calibrate the ultrasonic instrument search unit combination for sweep range over the metal path to be used. | |||
( | |||
GENER AL h ELECTRIC | |||
~ | |||
"" Procedure No. P.B. 83-1 | |||
/Masis, ag of b ( | |||
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'"7.'E.'.*MTO 4.4.8 Recalibration, Sweep Only If any indication of the DAC curve has noved on the sweep line more than five percent of the sweep division reading, correct the sweep l range calibration and note the correction en the Calibration Data l Sheet. If recordable reflectors are noted on the examination data sheets, those data sheets shall be voided and &stroyed. A new calibration shall be na& ard recorded, aM the voided examination areas shall te re-examined. | |||
4.4.9 Recalibration, Amplitude Only If the amplitude cn the DAC curve has changed by nere than 20 percent of its amplitude when a check is made on the calibration standard, all data sheets since the last positive calibration check shall be marked void and destroyed. A new calibration shall be mde and recorded and the vaided examination areas shall be re-examined. | |||
4.4.10 Verification of 2X Scannino Sensitivity The dB switches required to obtain the scanning sensitivity shall be detemined using the calibration standards. A reflected signal frcm one of the side-drilled calibration holes shall be detected and the amplitude adjusted to a level between 30 percent ard 40 percent of Full Screen Height. Using the dB switches, increase the signal amplitude to twice the sensitivity level amplitude ard record the setting change required. This dB change shall be used to obtain the | |||
* minimum scanning sensitivity. | |||
4.4.11 Scanning Rate The manual scanning rate for angle team scanning shall be sufficiently sicw to allow careful observation of the ultrasonic instrument screen and shall not exceed six inches per second of search unit novement. | |||
l 4.4.12 Calibration shall te performed at the beginning of each series of examinations on the calibration block applicable to the systen(s) being examined. A calibration verification shall be made at the end t | |||
of each series of examinations ard at intervals not exceeding four tours daring the examinations. | |||
4.4.13 A curve representing 20 percent of the DAC level shall be marked on | |||
- the display screen durirg calibration to aid in the determination of | |||
( indication amplitude. | |||
GEN ER AL h ELECTRIC | |||
Procedure No. P.B. 83-1 | |||
- Revision No. 1 Page 8 of 20 sannosh | |||
$$iiN n. | |||
-"v t'::=' | |||
4.5. Surface Preparation 4.5.1 The base material scanning surface shall be free of weld spatter and any other condition that would interfere with free novement of the search unit or impair coupling of ultrasonic vibrations to and from the material being examined. Unacceptable surface conditions shall be reported to the customer. | |||
4.5.2 Surface preparation and cleaning operations are not within the scope of this procedure. | |||
5.0 CALIBRATION AND EXAMINATION 5.1 0 Degree Base Material Sensitivity Calibration 5.1.1 Position the search unit on the applicable Plant Owner's calibration standard and obtain a back reflection. Adjust the peak signal amplitude to 75 or 80 percent of the Full Screen Height and mark the position on the display screen. This point represents primary reference level for the base material examination. Record this calibration data on the Calibration i Data Sheet. | |||
5.2 0 Degree Base Material Examination 5.2.1 Scan the volume of base material through which the angle beam examination will be performed to detect reflectors that could interfere with the performance or the results of the angle beam examination. This examination is not intended to be used for acceptance or rejection of piping welds. | |||
5.3 Angle Beam (45 Degree) Sensitivity and DAC Calibration 5.3.1 Position the search unit on the appitcable Plant Owner's calibration standard and obtain the first point on the DAC curve using a sound sath no less than 3/8 of the full skip distance.* Adjust tw peak signal amplitude to 75 or 80 percent of the full screen height and mark its position and amplitude on the display screen. Without changing the gain level, obtain the peak signal amplitude for the next two metal paths of the sound beam. Mark their position and amplitudes on the display screen. Signal responses for metal paths less than 3/8 of the full skip distance may ba obtained by determining the 2/8 node response (off scale) to determine the shape of the DAC curve. Join the points with a smooth line, the length of which shall cover the examination range. This DAC line | |||
( | |||
GEN ER AL $ ELECTRIC | |||
k Procedure No. P.B. 83-1 Revision No. 3 om ,, | |||
Page 9 of 20 | |||
( <w; | |||
- ( | |||
"$2NCLW when adjusted for acoustic sIuivalency, represents the primary reference level (IX Sensitivity) for the angle beam examination. Record this calibration data on the Calibration | |||
* Data Sheet. This calibration shall be perforned using reflectors parallel ard transverse to the weld seam as applicable to the examinations to be perforned. | |||
* Vee path ard skip distance are considered sluivalent terns. | |||
5.3.1.1 The 1/2 ncdal and, if required, the 1-1/2 ncdal point locations for the pipe to be examined shall be determined off the calibration standard notches or corners. Their locaticn(s) shall te rrarked on the screen and on the calibration sheet. Their location shall be narked on the screen ard on the calibration sheet. | |||
5.3.2 Acoustic Euuivalency 5.3.2.1 The calibration block shall be checked as follows for use in cmparisons with the plant pipirs for acoustic i equivalency: | |||
a) With the instnment at the primary instruirent gain established in 5.3.1, set instrument for pitcV catch operation. | |||
b) Attach two 45 degree single elenent search units to the instrument T/R jacks. | |||
c) Couple the transnitting search unit to the calibration standard. | |||
d) Manipulate the receiving search unit on the cali-bration stardard to obtain a traxinun (% FSH) CRP indication frcan the received signal. | |||
e) Record tha dB change required to brirq the artplitude of the signal to approxinately 80% ESH. | |||
5.4 Angle Beam Exa:rdnation 5.4.1 Establishing Prifrary Reference level 5.4.1.1 The primary reference level shall be adjusted to provide aroustic equivalency between plant piping and the calibration stardard as follows: | |||
a) Perform the operations outlined in 5.3.2.1 (a) ard (b) | |||
GENER AL h ELECTRIC | |||
-A Procedure No. P.B. 83-1 | |||
. r w f1 | |||
' Revision No. I Page 10 of 20 assmas t-( lO | |||
-m.= | |||
b) Set the instrument gain to the level established in 5.3.2.1 (e). In three equally spaced (120 degree) locations on the pipe weld perform the operations outlined in 5.3.2.1 (c) and (d). | |||
c) Detemine average dB increase or decrease necessary to attain approximately 80 percent FSH. | |||
Record this dB difference on the ultrasonic examination data fom and increase or decrease the instrument gain established in paragraph 5.3.1 by this amount. | |||
d) These steps (a)-(c) must be perfomed for each weld examined. Care must be exercised to insure that the instrument is returned to primary instrument gain prior to perfoming these steps. | |||
5.4.2 Scanning Sensitivity Level The scanning shall be perfomed at a gain setting equal to or greater than twice the primary reference level . At the scanning level, the operator should be able to distinguish reflectors from the I.D. root geometry, increasing the gain beyond 2X may be required to accomplish this. | |||
5.4.3 Recording Sensitivity Level Indications shall be recorded at the primary reference level (1x). | |||
l 5.4.4 Scanning for Reflectors Oriented Parallel to the Weld The search unit shall be placed on the contcct surface with the beam aimed about 90 degrees to the weld and manipulated laterally and longitudinally so that the ultrasonic beam passes through 2T minimum of base material from the edge of the weld. In addition, the search unit shall be angulated 0 degrees (perpendicu-lar to the weld) through 45 degrees to the right and lef t of the nomal (perpendicular to the weld) scan. | |||
See Figure 4. This examination shall be perfomed from both sides of the weld dere component geometry l | |||
pemits. | |||
( | |||
l l GENER AL h ELECTRIC | |||
Proceduro No. P.B. f.3-1 samnce Revision No. 3 ! | |||
Page 11 of 20 l k% | |||
' " ' > ( | |||
5.4.5 Scannino for Reflectors Oriented Transverse to the ) | |||
'"M %'.'0 00"l" Weld l On Irepared or sufficiently smooth surfaces the angle l bean unit shall be aimed parallel to the longitudinal centerline of the weld with the search unit contacting the weld surface. The search unit shall be mcred along the weld so that the sound beam passes through all the wald metal ard weld HAZ on both sides of the weld where practical. Scanning shall be cbne in two directions 180 degrees to each other. In addition, the search unit shall be angulated frcm 0 degrees (parallel to the weld through 45 degrees, ained at the weld) on both sides of the weld for parallel scanning. | |||
(See Figure 4). | |||
5.4.6 Specific Area of Interest Angle beam irdications of intergranular stress corrosion cracking (if present) will be evident at the 4/8 node or 1/2 " Vee path" netal path distance. | |||
6.0 DATA REDRDItG 6.1 0 Decree Base Material Indications 6.1.1 Record on tM data sheet all areas of base material which exhibit a total loss of back reflection. In aCition, record all areas where intermediate reflector (s) with signal amplitudes eugal to or greater than the renaining back reflection appear. If rurerous overlapping irdications of lesser amplitudes exist sich in the opinion of the Level II might prevent a meaningful sheer wave examination they shall be cbcurented. | |||
6.2 Anole Beam Indications 6.2.1 All angle team indications in the HA2 or base naterial in excess of 20 parcent of the primary referenm level DAC shall be recorded on the Examination Data SMets, Figure 2. | |||
Irdications observed on the CRT, which eninate at the root (I.D. sarface) and travel along the sweep toward the O.D. shall be investigated regardless of amplituck. Irdications irdica-tive of IGSOC shall be recorded. | |||
6.3 Reference Positions for Physical Measurements 6.3.1 Wo shall be the wald's centerline and shall be used for reasuring transducer novecents perperdicular to the weld. See Figure 3. | |||
( 6.4 Selectino the Incation of In Reference Point (if not previously trarked) | |||
GENER AL h ELECTRIC | |||
Procedure No. P.B. 83-1 Revision No. 1 mamash Page 12 of 20 | |||
( l%T | |||
,w .= | |||
6.4.1 Piping Within Containment On horizontal pipe. Lo reference shall be an axial line or point at the pipe top dead center. On vertical pipe, lo reference shall be an axial line or point on the pipe circumference farthest fra the reactor pressure vessel. | |||
6.4.2 Piping Outside Containment On horizontal pipe, to reference shall be an axial line or point at the pipe top dead center. When possible, on vertical pipe, the LO reference shall be selected by drawing an imaginary line down fra the outermost radius of the next highest elevation elbow. | |||
When no elbows are in sight, the LO reference shall be an imaginary line on the pipe 180 degrees from the neares': wall or obstruction. | |||
6.4.3 Pipe welds with indications my be stamped with low t | |||
stress Y stamp. The V stamp shall be placed on the circumferential weld centerline. The top of the Y shall be LO (for circumferential welds) and shall point in the direction from which measurements are made. For longitudinal piping welds, lo shall be the pipe circumferential weld centerline. | |||
6.5 Method of Recording Examination Data 6.5.1 Figure 3 sketches the relationship between transducer 1 weld center movements (positions W , | |||
(Wo), weld reference point Loi4(, y)a,nd location and length of indications (L1 and L2 ). This attachment also contains a sample copy of an Examination Data Sheet. Hypothetical information l based on the above sketch has been recorded on it. | |||
6.5.2 Search unit positions W1 and W2 shall be recorded only when the wall thickness of the pipe exceeds one | |||
- inch. Signals caused by geometric changes such as weld crown, mismatch, fitup ID preparations, etc., | |||
shall require recording of %, W , the peak signal amplitude, and the length of the indication in inches or degrees azimuth. | |||
. 6.5.3 The following " transducer positions" and " data to be | |||
( recorded "information shall be recorded on the Examination Data Sheets for indications which exceed 20 percent DAC at the primary reference level (1x). | |||
GENER AL $ ELECTRIC | |||
Procedure No. P.B. 83-1 sannes Revision 0 Pag? 13 of 20 l c ~> | |||
-ne = | |||
Transducer Positions Data to be Recorded (a) W1 - Distance between the (1) Distance from referenced search unit index point and centerline (WO I* | |||
the weld centerline (Wo) when the signal amplitude (2) Indicated metal path to decreases to 20 percent DAC when moving towards reflector distance (MP)). | |||
the weld from Wm . (1) Distance from reference centerline (WO I* | |||
(b) W, - Distance between the search unit index point and (2) Indicated metal path to the weld centerline (Wo) reflector distance (MPs ). | |||
when the signal amplitude is at maximum. (3) Signal aplitude in 1 DAC at Primary Reference Level . | |||
(c) W2 - Distance between the (1) Distance from reference search unit index point and centerline (WO I' | |||
, the weld centerline (Wo) when the signal amplitude decreases to 20 percent DAC (2) Indic:ted metal path of when moving away from the reflector distance (MP2 )* | |||
weld and Wm - | |||
6.5.3.1 The transducer positions L 1 and L2 , correspond to the 20 percent DAC length end points of an indication. | |||
The end points of the indication at 50 percent DAC shall also be noted on the d>ta sheet. | |||
6.5.4 When indications other than geometric have been identified within the fusion zone, the heat affected zone or the base material, the transducer's positions should be recorded as follows: 1) The transducer's movement for each data point is perpendicular to the 7ength dimension. 2) The data shall be l obtained at 1/4-inch intervals along the length of the reflector for indications less than 2 inches in length. | |||
In addition, the maximiss amplitude points shall be checked at 1/4-inch intervals. 3) For indications greater than 2 inches in length, the data shall be taken at 1-inch intervals. 4) The l continuity of indications between intervals shall be l | |||
confirmed. | |||
i( | |||
GEN ER AL h ELECTRIC | |||
Procedure No. P.B. 83-1 : | |||
Revision No. 2 l | |||
- Page 14 of 20 sewnsk | |||
( | |||
di!EI | |||
** y o g 7.0 REVIEW OF DATA 7.1 The recorded data shall be reviewed by an individual certified to at least Level II to determine if additional examination and/or evaluation is required. | |||
7.2 Evaluation of Indications Disposition and evaluation of indications shall be as specified in the contr;ct. | |||
7.2.1 Geometric plots of all recordable indications shall te made to show location of the indications with respect to tha weld root and weld heat affected zone (HAZ). | |||
7.2.2 To assist in preparation of geometric plots, the responsible individual shall assure that thickness measurements, where required, are available. | |||
7.2.3 Indications that appear to originate from a geometric condition shall be plotted to determine their origin. | |||
7.2.4 When geometric plotting appears to be inconclusive or plotted data appears to result in a condition that may not be correct, such as a reflector that appears to emanate from the far (opposite) side of the weld root, the Level III may elect to evaluate the indication based on signal behavior. Some characteristics of IGSCC signal behavior are: | |||
A) IGSCC indications will originate at or near the sweep position corresponding to the component ID. | |||
B) IGSCC indications will walk (travel on the CRT) from ID toward OD. | |||
C) When the search unit is angulated (per Figure 4) whfie the indication is peaked, a geometric indication will decrease l | |||
in amplitude rapidly with a variation in incident angle. | |||
t An indication caused by IGSCC tends to decrease in | |||
^ | |||
amplitude slowly and become more broad based as the search unit is angulated. | |||
D) At times, an indication will separate from an IGSCC indication, as the search unit is moved toward the indication, and walk toward the OD. This indication, when it appears, is indicative of a crack tip and is associated with indications of IGSCC. | |||
( | |||
GEN ER AL $ ELECTRIC | |||
Procedure No. P.B. 83-1 | |||
[k Revision No. 2 Page 15 of 20 | |||
_ J L_ | |||
c . | |||
='.:, | |||
These characteristics of IGSCC indications should be checked at or near the middle of the indication. If the i indication is short (less than 3 times the width of the search unit) it will be necessary to move the search unit to an end of the indication before angulation is performed (Step C). | |||
7.2.5 Indications determined not to be from geometric reflectors shall be evaluated as follows: | |||
7.2.5.1 0 degree base material indications shall be evaluated to ensure that no interference to the angle beam examination exists. | |||
l 7.2.5.2 Indications which appear to be from IGSCC shall be i reported to the Plant Owner within 24 hours of evaluation. The Owner shall supply disposition of the indication. | |||
7.2.5.3 Indications shall be reported to the Owner for disposition if the amplitude exceeds the reference level, and discontinuities have lengths dich exceed: | |||
(1) 1/4 inch fra t up to 3/4 inch, inclusive (2) 1/3t for t from 3/4 inch to 2-1/4 inch, inclusive (3) 3/4 inch for t over 2-1/4 inch where t is the thickness of the weld being examined; if a weld joins two members having different thicknesses at the weld, t is the thinner of these two thicknesses. | |||
L GEN ER AL $ ELECTRIC | |||
Procedura K). P.B. 83-1 Revision PC. 2 sammes Page 16 of 20 avaness | |||
( 'w, PIPE ITP CALIBRATION DATA SREEr Tab",,'g* | |||
SITE | |||
~ | |||
l lPreoperational l l I.S.I. | |||
SYST94 CALIBRATION BID 3 9 m i w iiRB 10. REV. CALIBRATION SHEEP i DAE CDUPIANT IIW-2 BID 3 $ | |||
EXAKINER ASNT EVEL DATA TAKER ASNT IEVIL DEIR'J EN! KDEL PC. DEIRMNr SERIAL $ | |||
CAB E .. . CAB 2 TfIE CAB 2 I22 CHI TRA?EDUOR DATA SEDE TYPE STRAIGfr APGLE BEAM BEAM SEDE AIG2 SERIAL 10. | |||
IDENTITY LODE PRS 20DCf SIZE (DUPLANr REFI2CKR ORIENTED (PARALLEL & 'DWFJUGE) TO WELD SFJM (Cross Out Ore) | |||
DAC CURVE CAL STD TD(P 90 D6IRMNT SETTDGS: | |||
80 l Start Finish Urcalibrated Gain 70 Coarse S g Fine Swwp 60 Coarse Range Fine Range 50 S a nning Gain Attenuation (in) 40 Evaluating Gain Attenuation (in) 30 - | |||
Pilter Position Rep Rate 20 Dacping Reject 10 Acoustic apiivalency (Para. 5.3.2) | |||
( 0 1 2 3 4 5 6 7 8 9 10 0 1 2 3 4 5 GENER AL $ ELECTRIC | |||
. : 4 | |||
-fi - - | |||
Proc. P.B. 83-1 mmm.. Rev. 2 | |||
"""% Page 17 of 20 f- <w2 m:=::* l Bole Depth . Gain Max "W" D or MF SCH Initial Calibration Time j "T" Inches 91X Acp. Irrh Inch or FE Periodic Checks: Iast 1X Time Value Data Sheet 1/4 1/2 IX 3/4 1X 24I.0 1X lbtch 240.0 1X Final Check: | |||
lbtch Calltration in Dept.(D) [ or Metal Path (!@) O Applitude Idnearity Check Control Linearity (Made Daily) (Made Daily) 100% FSH USH 50 WSH tFSH 80tFSH -64 (32-48) 90% | |||
40% " | |||
80%FSH -12 4 (16-24) 80% | |||
30% * | |||
* 40lFSH +6& (64-96) 70s " | |||
20 % " | |||
" 20%FSH +12db (64-96) i r | |||
Mt (hecks on llW-2 spip. Data-Straight Beam For Linearity Checks Block on './8" SEE for Field Calib. | |||
Checks @ Ma Anp. for Both Near/ Par c | |||
llW-2 Position in 4 Screen Beight Tranadacer Data: 1/8"SDB Near Far Serial')D. Max. | |||
Beam Argle Ano. t t Size Freq. Metal Shoe No. Cable No. Path 4 % | |||
Check Made By: | |||
k nevie.es by | |||
- St@ 'IC Le/el | |||
! G EN ER AL $ ELECTRIC | |||
Procedure No. P.B. 83-1 | |||
* ' ' Revision No. 2 samnes Page 18 cf 20 | |||
#I I I 1 Xh* | |||
( ' | |||
("a ULTRASONIC EXAMINATION DATA FORM Exam Form Cal. Form No. | |||
Site O Preoperational O l.s.i.oaio System Weld No. Weld Type _ _ . . . | |||
Examiner ASNT Level . _ _ ._ | |||
Data Taker _. | |||
ASNT Level _ | |||
Scarch Angie U.T. Ps ocedure Rev. __ | |||
Scan Sens: X2 Other Evaluation Sens: X1 ._. | |||
Couplant Comp.Te mp. | |||
EXAMINATIONS: Performed Indication Yes No Angle beam for reflectors parallel to weld Yes No _ | |||
1. | |||
: 2. Angle beam for reflectors transverse to weld (dockwise and counter clockwise) | |||
Benchmark or Referenced "O" Locat;on: | |||
L, = Wo" AVER AGE ACOUSTIC.DIFFERENCEjdb) Pero. 5.4.1.1 : | |||
Inches %DAC Metal Path From Wj W, W2 1X Amp. Exami-L= Ref. Inches Inches Inches W, W g W, W2 n t;on Scanning Mode & Rema ks i | |||
( Reviewed by: ASNT TC-1A Level O si O tii DOESO DOES NOTO lAEET CODE 1 | |||
GENERAL h ELECTRIC | |||
T U | |||
* eu e - | |||
P0.g3 19 of 20 . | |||
. Rev. 2 - | |||
N * .. | |||
t . | |||
1 ., | |||
* -(V) STA&1P - e . | |||
T .. | |||
~ | |||
- TC.* DEAO CT.NTER s t, FCA CRCb'MFERENT.AL WZLDS , | |||
y, . ,, y, l. | |||
/ | |||
to t, | |||
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g _ | |||
g e c- ' | |||
c. | |||
. _.L -t.s ej sj , ( m - | |||
i s | |||
- . -W. FCR - | |||
LCNG WELO | |||
. . _ . i . | |||
g g | |||
\ | |||
t, q | |||
x , , | |||
Wa Tu W W, FCR C$tCU:.:FE.*CfMAL WP D XYZ , | |||
- . | |||
* 5 . | |||
- . m. .. . . . . . , | |||
( . . | |||
I ' | |||
Ezas . Sca.ni: | |||
W ZDAC }'eral 7ath _ | |||
ya* s Ec=s: | |||
p::=5.as ~ | |||
. v.y 1 y yo Inc 1e.s | |||
~ | |||
2 | |||
,.s --hEs ;, I_ch.sas t m | |||
3.6 25 2.7 3.5 ' 4.8 3 22 2.0 . l 2.7 2.6 ' 3.4 L.A.7 3 2.6 3.5 15 22.3 l 2.0 , | |||
i 20 l 1.7 3.4 4.6 3 . | |||
I 2.0 2.6 3.4 25.0 l . ._ | |||
. i . | |||
2.4 2.7 2.9 2 . | |||
1.4 2.7 20 p.3 2.1 | |||
* 2.9 35 , 2.4 2.8 3.3 , | |||
2* _ | |||
j 1c0 | |||
~ | |||
l 2.1 2.6 | |||
* 2.4 2.7 2.9 2 | |||
! 2.4 2.7 22 e t.5 w 2 . *- | |||
- I | |||
.~ | |||
(> | |||
TIC *JPT., 3 _ .__.. . _ . - . . | |||
. : . . . * ,f . | |||
p -e- m- - .- | |||
^ | |||
Procaeare 'No. P.B. 83-1 | |||
. . Rev. 2 | |||
+- . | |||
'. *t ,Page 20 of 20 SENER AL h ELECTRIC . | |||
( | |||
Page 20 of 20 , | |||
Tests ~ {&3' - | |||
Saw as - | |||
-. Test 2 Side Test 3 Side | |||
' WEL D . | |||
A A Test 2 Side , | |||
(( "} g'%'IN) | |||
. 45 w 45 | |||
( Tests 415 , | |||
} - | |||
45*y $4g* . | |||
. Test 3 Side W E'L D | |||
.Tes t 2, 31de u--1>) Oh | |||
'' ~q Q ,_ Q .( ) .. | |||
g e k . | |||
Figure 4. Scanning Pattern . | |||
G | |||
ttachment 1 I)ocket No. $0-277 Exhibit 2 . May 23, 1983 semca "m "weaiGt 51 1 I I IM PIPE UT CALIBRATION DATA SHEET | |||
'":lE'50T SITE %ntulorT OM - V N I T -w PrOOperational b l.S.I. | |||
SYSTEM T.\4.7. 50 c TIO w CALIBRATION BLOCK NO. 33 A PROCEDUp W A3-l REV. 4 CALIBRATION SHEET NO. 2- /cCO DATE 5 -A3 @0 PLANT Ut.-re.MEL IIW-2 BLOCK NO. 790339 EXAMINER I. D 6.cXt. R- ASNT LEVEL M DATA TAKER l . R ' C. L R 'I.R ASNT LEVEL h | |||
.I 3I INSTRUMENT MODEL NO. Somc MK. I INSTRUMENT SERI AL NO. DIO s7f /o& L m E i | |||
CABLE NO. C-I5 CABLE TYPE BNC le MC b CABLE LENGTH (o Y ISO ' | |||
TRANSDUCER DATA SHOE TYPE Lu c.1r e STRAIGHT BN ANGLE BEM SHOE NO. $\ | |||
SERI AL NO. YA B 7.7. 3 0 7 IDENTITY "/A CnA P4M A SilOE ANGLE (oO FREQUENCY N/A 1. 5 M4 s SIZE N/A 5 MODE $ N( N2-PARALLEL COUPLANT LX,TM Gn f L Of REFLECTORS ORIENTED TO WELD SEAM (Cross Out One) | |||
- T!'Z:CVE RC E CAI. STD TEMP A/'1016 -INSTRUMENT SETTINGS: | |||
DAC Curve Uncalibrated Gain % M/4 Coarse Sweep g N g g Fine Sweep g, g ( 7, g t) | |||
/' | |||
} | |||
Coarse Range 5 5 70 | |||
; Fine Range l 90 2 98 60 | |||
! Sc'an'ng Ga.n B[ 8O | |||
( ! Attentuation (in) g N/A Evaluating Gain 75 l 74 0 | |||
Attentuation lin) , t4/4 N/A 30 Filter Position H.T H 'I, l , 1 t 20 N. , | |||
Rep Rate 3K 3K 10 | |||
' 9 W MM l | |||
g 0 1 2 3 4 l\'% | |||
5 6 7 8 9 10 Reject Ac unic Emalency OFF p/A oFF i (Para. 5.3 2) 0 2 3 4 5 , , | |||
1 9 | |||
1 | |||
* 1 l -.... ., A . - ,, , ,, , 2 | |||
E | |||
~ | |||
, z _ ..,_ . | |||
e o . | |||
QD [411L I l ' o (f j0 I I | |||
- e D 2. | |||
Ev"meis i1 1 I I I M ULTR ASONIC EXAMI TlON DATA FORM Enem Form l - l C O l Cat. Form No. S ~ l 00 C) _ | |||
s,te Peract. Atte # E O Pr.cooretica.: pH i.s.i. oaie i /-T3 System UR Wold No. IO- C ~ 0 Weld Type Pr W T o aELBo u 1 faamenee 7 e DEdd ASNT Lewt M Data Toker ka M 'CL A A ASNT Lent E bO~ N / | |||
Search Anfe U.T. Proceevre Re. Y Scan Sens. X2 $8 d b Other 2WL E valuar en Seni x1 7SJ6 Couo ans lh' OA6 Cl - | |||
n h Coon Temp I30* | |||
E x AMIN ATIONS. | |||
Pe r f o'm ed and cas.on Yes No Yes No | |||
: 1. Angle beam for refiectors parallel to weld 2 Angie beam for reflectors transnrie to weld (docka.se and counter clockaisel Benchmark or Referenced "O' Locai,on Tbc | |||
, p t | |||
o | |||
. ID C-- wo - | |||
ik . f w ere_ D yG - dc yc r o CE AVER AGE ACQU$ Tic OlFFERENCK (e) Pero S 411 : | |||
Inches %DAC Metal Path From W, W W2 ix Am, Enam. | |||
L. Ref Inches inenes incees W, W, W, W2 at on Sc ,,n ,,9 y ,c , g p , _ , . , | |||
L hi l'/.O 0.9 1. 0 1. 3 /ev% +jbf8 ?.o ff 3. 7 d S. | |||
v | |||
& 'n 2.9D o. 9 c. 9 1.1 .2 59l M 2.9 3. Y u. s. 12 u o s rc3z L 3r75 3& "ci c,w - M. | |||
G% 34.0 /.0 I. 2 f. E 70% 2. Y 1. 7 39 U.S I"Lesce | |||
&% 41D l.I l.1 f. T Jc% 3.0 3, g 3.g g_ g | |||
~ | |||
1r h 4fo 41 | |||
+ | |||
: 1. 3 25% .15 v. 5 | |||
& % 52.5 f 1.35 15% 3.7 U. S. | |||
0 % 53.5 1. 3 25 % 3.;L U.S. | |||
4 0 % 5to 1. o , fe'i4 1,6 s ico% 32 y.o yy v.s sto r x-aransa se..e.,d by: ? d '/X% / | |||
* ASNT.TC.1 A Lewt 0 is 3 m octsO oots notO ucET cobE N d 7Ti k'lG d C O'- [MEJMY GENER alm FIFCTRir ! - | |||
N,' jky# - | |||
.a J | |||
==: .. p i , | |||
JEE' [ggici es,,,ics /{MI[ 1 Ev"wisiiir ULTRASONIC EXAMINATION DATA FORM Erem Form | |||
. Cal. Form No. | |||
s,,e PfuHsoroni int-2 o e, ,ei,on. e i.s.: o.te 5-7-33 System RHR SocTXo** Wend No. l0 ~ * | |||
* b Weld Tsno PZPE To ELemJ ASNT Level 22E Enam. nee f. DECA ER Data Tekee R. MCC t.4 TAI ASNT Levei .2t Search AnWe | |||
# U.T. Procedu,, PR-83-/ R,, +/ | |||
Scan Sens: X2 8f 28 Other E valuat.on Sens x1 75d8 Couplant Come Temp E X AMIN ATIONS: Per f ormed Ind cat.on Yes No Yes No | |||
: 1. Angle beam for refiectors parallel to weld 2 Ange beam for reflectors transverse to mid (cfockwise end counter clock veisel Benchmv h or Re ferenced ''O'' Locat.on NO L e TV wn e of %![LO AVER AGE ACOUSTIC D FFERENCK (db) Pero S 4 1 1 ! | |||
Inches %DAC Meter Path From Wj W, Wy IX Amp W eat.on Lo Ret inches incees Inches W, y W, W7 gg ,,n,39 y ,c , g g , ,,, | |||
'n 35.0 10 I. 3 1.15 90 % 3.I 3.9 4. 5 U. S. | |||
4 . | |||
% 6I.o fofo 2.1 13 U.S. o s + r v. c . v. _ | |||
@ i. o i. 3 i. 7 v. ~3 4 - | |||
Q % o c.9 1. s 19 iec% 3.4 q.c 5.1 as 4 | |||
&% 4.o | |||
+ | |||
: c. 9 1.1 1.5 100% 3.1 % 5.8 o.s. | |||
4 | |||
: 3. o i.1 1.1 a.s 100 % Y.3 4. 8 to D. s. | |||
@ % sto i. o /. 2 /. 5 75 % 3. 2 3. 3 Vo D.s. | |||
4 g% 44.o I. I /. 2 /6 30% 3. 2. 3.V V. 2. o.s. | |||
4 | |||
{ Ls W.o hviend by. | |||
1.15_ | |||
k l.% | |||
j.'N 4 It 1.75 Jo% 3. '1 ASNT.TC 1 A Level | |||
?.5 O is KV 0 5'. | |||
1 iii DOESO DOES Not0 isEET coot | |||
~I | |||
~ 'I O ' | |||
Y GENER AL M ELECTRIC s , / | |||
.a | |||
L Jc' gxst : | |||
,i . | |||
4 " | |||
h/[ e [ | |||
. ale"enein | |||
, ULTRASONIC EXAMINATION DATA F.ORM | |||
< w2 E sam Form Cel. Form No. _ | |||
s,te PEACHectroAs MTr 1 O preooeret,onsu & s.S I. 0 ate 5-7-13 sr, tem RHR SUCTroni west No. /0'O'S wem Tree MT ro nectJ E4m.n., T. DecNER AsNrte : 327 Date Take, A.MecLAIM ASNT Lent 5 Search Angie SO U T N xedw,, PR 93-/ n,,_ V . | |||
Scan Sens x2 RI J B Other E va'wat,on Seni 7f/A x1 Cowplans ComeTemp E X AMIN ATIONS. | |||
Per f ormed Ind. cat.on Yes No Yes No 1 Angle beam for reflectors para'let to weld | |||
: 2. Angle beam for reflectors transver6e to weld (dockeine end counter clockwisel _ | |||
Senchma,k or Referenced "O" Locat.on IO C. | |||
L, = TDC w, . 1 or wrto AVER A0[ ACOUSTIC oIFFERENCK f o) Pero S 411 : /If _ | |||
inchet %DAC Metal Path From Wy W, Wy IX Amo L. Ret inches locnes incties W, Wi Wm ation | |||
*2 $c,,n,ng y,c , g q ,,,, , , | |||
% 30_o I.'l .2OYo 3. 5 D. 5, 3MTT STG AML | |||
+ | |||
53.0 /. '/ 25 % 35 D.S SRU srGAL k | |||
h % 57.0 4 | |||
115 /3 5' 23 75% 3. 3 3. (, 5.1 0.5 g % 59.o as i.gs 2.s c,0% u u s. e o.s. | |||
4 | |||
% (40 1.15 l. ))$ 2. 3 $0To 3. 3 3. b - S'. 8 0. $. | |||
4 64 0.o 13 i. v5 f. ss fooyo a.e 3.4 v.3 0. 5. | |||
YiA .4&lC/(G 0[i)N(C /A dV Cf /hhC VtCA3 ~ | |||
c ~ i. hMdM s'/3 0[.4C'U r'? k' /TW$tt b AlL DC/ WOs YL Reviewed by: / | |||
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ] | |||
Peach Bottos Unit #2 RHR Suction; Pipe to Elbow b* eld: 10-0-6 20" diameter Assume 64" circumference g | |||
N 2 | |||
Graphic Plot of the location and thru-wall depth of all ultrasonic indications, assumed to be ciacks. | |||
4} | |||
Y | |||
. 4.,- | |||
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t,sals ~ f/7/93 | |||
'd 1 Attachm:nt 1 Docket No. 50-277 Exhibi 3 May 23, 1983 , | |||
PROCEDURE FOR SIZING NON CEOMETRIC INDICATIONS 1.) Thickness readings and surface contours are taken on all welds at a minimum of three locations around the circumference. Additional thicknesses and contours are taken as required. See Figure 1. | |||
2.) Metal paths W1s W'W2 M are taken, where: | |||
W1 = Minimum metal path at 20% DAC. | |||
~ | |||
Wg = Metal path at maximum amplitude W2 = Maximum metal path at 20% DAC. | |||
3.) Cross sectional plots are constructed using the appropriate surface contours and thicknesees. | |||
4.) The shear wave refracted angle is determined from the calibration standard of the same material, diameter and thickness as the weld being examined. | |||
5.) The ultrasonic data is then applied to the cross sectional plots and the maximum thru wall depth of the indication is measured directly. | |||
This technique has proven to be the most conservative, ie, provides the deepest thru wall dimension of an indication. The crack tip method using the formula: d = (Wg - W1 ) cos 0 has been shown to provide depths 10 to 20 percent less than the method described herein. | |||
UDC 610.179.16: 620.194: 611.365.5.01J: 621.039.536.14 Attachment 1 Docket No. 50-277 Exhibit it May 23, 1983 | |||
, '. Effects Brought by Induction Heating Stress improvement 01-1S1) | |||
Measures on Ultrasonic Signals Reflected from intergranular Stress Corrosion Cracks (IGSCC) | |||
Saburo Sidbata's Iliroshi Yoneyama'l Shinji Tanaka'8 Moritaka Kishigami'l alTected zone on both sides of the welded joint, of | |||
!. Introtluction various depths and widths cut by EDM, as specified in | |||
.he research efforts directed in recent years toward Table 1. The other specimen was provided artificially | |||
.mnbating Stress Corrosion Cracking (SCC) have re- with IGSCC which was produced in multitude by the | |||
.ulted in the development of a number of materials technique known as " Creviced Pipe Test" in high | |||
:c>istant to SCC and of techniques to provide against temperature pure water 44)(Fig.1). The resulting IGSCC M*C. which have come to be practically applied to was distributed as shown in Fig.1. | |||
.r.:..e.ir boiling water reactor (BWR) plants"). Induction 2.2 Experimental apparatus fe.nmg Stress . improvement (IHSI)(W3) is one such The ultrasonic apparatus used for the experiment | |||
..nmque that is receiving particular attention both in i.u'an and in other countries, as an efTective counter- ,,,,,,,,,, | |||
O e.nure, against-SCC for BWR-whether in the con- NS 3 W N~ek | |||
. intetson stage or:already in operation. The aim of IHS! | |||
p t,iimprove.the state of residual stress due to welding, /*** | |||
through reduction.of' the. tensile component of the / c,.m.u . | |||
Suual stresslichte to occasion SCC-or further - | |||
wu.:h its conversion into compressive component. | |||
On the other hand,in view of the current practice of f ' S{-{ 7 ~ | |||
utilizing ultrasonic methods of flaw detection for in-service inspection of. equipment and piping in DWR c | |||
"~ " | |||
./ h[* ' ~ | |||
s plants. it is essential to know in advance whether the liiSI treatment applied to such components should | |||
.itfect in any way the ultrasonic' properties of the material . ., | |||
: s. : treated, and if so, what the effects would be. /,*;"_ | |||
The present study covers a comparison made of the r- - | |||
~ | |||
results of ultrasonic tests applied before and after IHSI ~/ | |||
treatment to specimen pipes carrying notches introduced ~ <=. | |||
hy Electric Discharge Machining (EDM) and artificially Fig. 1 SCC testing apparatus created Intergranular Stress Corrosion Cracking ilGSCC). A discussion is also given cocerning the deter-mination of defect size by ultrasonic testing. ' | |||
_..,s m.,,,,, , | |||
,,0 ,'_~i ,.> ~ ~ %v | |||
: 3. Experimental apparatus and test specisnens | |||
. _ - , _ , - - . _ m .- . - - ~ | |||
21 hpecimens used in experiment e=cu> >> | |||
~'u'.u '+"' M -3" The specimens used in the experiment were prepared | |||
' rom 12 inch Sch 100 type 304 stainless steel pipe each . . _ _ . . . _ - _m - | |||
.arrying a butt joint made by conventional automatic '#CC ' '1WC# | |||
viding. Two such specimens were produced, one of smth eine was provided with 12 notches in the heat- y,,. _ .-m._ ,, | |||
stet.6Hure liep; rtment. Itcscarch institute - , | |||
I " 'inWf mc TJ m m nirainin .3. Development Department. | |||
...i ,, | |||
. i . .cr liis nion Fig. 2 Produced SCC distribuuon S | |||
M M'*% N Ttbla f EDM netch c nfigurttians HAZ No. Al Anmuth ang!c t i A2 0 45 93 135 180 225 270 315 25 | |||
= 115 205 295 L tmmt 5 10 20 it'emmt 0.2(, 0.27 0.26 0.33 0.26 0.27 0.30 0.J2 0.26 0.27 O tmme 0.25 0.3 0.43 1.55 3.95 7.90 0.48 1.55 4 95 7.90 0.48 1.55 3.95 7.9 41 9 | |||
U | |||
-l ] | |||
i ^ | |||
j; q . . _ - _ . | |||
j , | |||
consisted of: | |||
3.4 Transducer positions for defect measurement and Search unit USIP ll method of ultrasonic testing Transducer .t5 shear wase angle. 2.25 MHz. | |||
The defect echo height, as well as the length and depth 12.7 mm diameter Couplant of the defect, were measured using the same transducer Glycerine positions. | |||
For deriving the Distance. A mplit ude Correction (1) Defect e.ho height (DAC) curve and for adjusting the working sensitivity level, the reference block i!!ustrated in Tie. J was cut out For the specimen provided with notches (Table 1), | |||
the echo height was measured with the transducer from the same material as the specimen. | |||
set at the position where it registered maximum | |||
: 3. Method of experiment echo heicht before IHSI. For the IGSCC specimen, 3.1 Preparation of examination surface the measurements were made along the pipe periph. | |||
The external surface of the pipe joint was fmished cry at mtervals of 10 mm (135 positions in all), in smooth so as not to affect the performance of ultrasonic view of the almost uniform distribution of the search. This was done by simple grinding in the case of IGSCC over the entire circumference on both sides of the joint. | |||
the specimen notched by EDMt in the case of the other specimen provided with IGSCC, the surface was ma-chined, for the reason that it presented a prominent (2) Length of defect The defect length was measured on both speu-g weld reinforcement. mens by the method prescribed in the ASME 3.2 Experimental procedure Loiler & Pressure Vessel Code Sec. V, using both the criteria of echo height exceeding 1/2 max. and The two specimens were subjected to ultrasonic search , | |||
exceeding 50% DAC. | |||
before and after lHSi treatment, as schematized in (3) Depth of defect Fig. 4. The pairs of search before and after IHSt were The defect depth was measured by the same made by the same examiner, to climinate any differences due to personal tendencies. method as above, supplemented with additional measurements by the Flaw Tip Echo Method 3.3 Discrimination .etween echoes from defects and illustrated in Fig. J. In this measurement the from root bead surface configuration transducer was located in the same position as for The echoes from the artificial defects (EDM notches. the echo height measurement (see (1) above). | |||
IGSCC) were discriminated from those retlectine back ' | |||
from the root bead surface by wave pattern identifica. 4. Experimental results and discussion tion. or else by touching with a finger the root bend 4.1 Effects brought by IllSI on echo height surface of specimen at the zone of wave impingement, The echo heights obtained from corresponding measure-which produced a change in echo height in tne case of root bead surface retlection. ments before and after IHSI are correlated in Fig. 6, where the diagonal line represents unchanged echo M | |||
b- .c 'Y DMW_= % t.r M . UT h 1 | |||
/ \ / | |||
.tcaoae v. | |||
. . - .%: .6woeaca O | |||
{ .e ,. | |||
= F g v "- Pe ) | |||
Fig. 3 | |||
..a s em cscc .r | |||
. M% | |||
\ or H | |||
*-=a h | |||
Reference bicek for ultrasonic examination Fig. 4 Experimental procedur7 2 | |||
r | |||
o 1, s., t 5 No. 4 October 1983 | |||
~ | |||
, . . ."ight between the two measurements. Extremely little machining of specimen surface applied to remove the gunge due to IHSI is noted for the measurements on asperities on the examir.ation surface. The standard mnhanically applied notch. An equal performance has deviation shown by the plots are, as shown in Table 2, not been obtained for the IGSCC specimen, despite the 1.2 dB for the mechanically notched and 2.7 dB for the l , IGSCC specimen. The poorer stability of measurements g | |||
: i. ~ | |||
~ | |||
obtained on the IGSCC specimen can be attributed to l l . . | |||
the complex configuration of the cracks, which fork into many brar.ches, as evidenced in the photomicrograph of e, _ b a sectioned specimen shown in Fig. 9 as compared with the neat notches that are obtained by EDM. | |||
Even the value of 2.7 dB standard deviation obtained k on the IGSCC specimen, however, is already within the i | |||
range of scattering normally obtained on similar meas-urements by ultrasonic testing, considering that the | |||
- estimated reliability of flaw detection by ultrasonic testing is said to ensure reproducibility only within | |||
* d2.7 dB standard deviation when counting solely the i | |||
r differences in tendency shown between persons, and if all factors are included, the standard deviation will further increase to 6.7 dBm. The values in Tab /c 2 | |||
< - nt,-a ,u.. . given under the column designated i represent the | |||
- mean differences between the measurements before and i m , | |||
,f after IHSI, i.e. the shift in measured values produced 7 .,$ by the IHSI. A very slight shift is discernible for the case of IGSCC specimen. Corbly et al(8). have reported | |||
[ 7'- - - '- | |||
b'' that the height of defect echo can vary with stress WC applied to the region of crack, and that cracks with tig. 5 Sche natic illustration of the Tip Echo Method for closed gap tend to transmit ultrasonic waves, resulting SCC sizing I | |||
ca* csce | |||
* ~ | |||
? ? | |||
: ..G: | |||
a : a< n : 4 s r...<> ,..3 Fig. 6 Echo height Table 2 Seatistical daea , | |||
EDM notch SCC n e i n e i Echo Height (dB) 12 1.17 0.63 135 2.70 , | |||
1.68 li2 n m . 12 0.39 0.32 44 3.59 - 0.86 Flaw length _ | |||
""*' 50!; DAC 11 1.39 0.23 47 5.20 - 0.76 t/2 mas. 12 0.81 - 0.07 51 0.57 0.15 | |||
'*d*[ 50!; D AC 11 0.15 0.03 37 0.72 0.06 n.14 Tip echo 10 0 49 0.19 23 0.5 R 8 %te t er Numnct et wrnr'ie r: Standard deu.mn | |||
~ | |||
- Mcan error li, Pre IHSI-Pmt IHsl p ,,) | |||
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es. . in- * | |||
. sn cac ~' | |||
.in . . | |||
s,. . so , oAc | |||
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I ... | |||
gs. | |||
. 6 | |||
. cu ' J" ?* C'cc | |||
+ , , | |||
to. | |||
a,. | |||
5- . *,/ | |||
rn | |||
'f-v. | |||
u . u ev es ao u aa su e ** * = N p., m < > | |||
r,. mt ) | |||
Fig. 7 Flaw length e- | |||
. i/2.ea. | |||
., . sosorc | |||
* 7- | |||
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6 - . sn eac 6 - | |||
,y,,,, | |||
15 - | |||
15 E | |||
* 3 t4 - | |||
[1 ' .., | |||
3 . | |||
. 3. * *** | |||
* cSec | |||
, ,.. ,,s,., | |||
. g. - | |||
,- y ><-:t 3 | |||
i . . | |||
/ *, ** | |||
sde s | |||
h o a e 3 . 3 . : e a : | |||
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; Fig. 8 Flaw height - | |||
l | |||
{ in lowering of the echo height. This would indicate the Now, if IHS! had brought any physical change to a possibility of echo height being influenced by IHS! defect, both length and depth should have increased, or treatment, since the intensity of residual stress is modified else both decreased: The fact that the data given in by this treatment"1--amounting at times to conversion Table 1 indicate inverse directions of change for these from tensile to compressive stress around a crack. | |||
two dimensions would deny the existence of any con. | |||
The foregoing results of the present experiment, how-sistent causal relation between IHS! and ultrasonic data, ever, would indicate that such influence of IHSI treat-and the scattering of the measured values should more ment on the ultrasonic property of the material, if any, reasonably be attributed to normal measurement errors. | |||
should be negligibly small, from the fact that extremely 4.3 Dimensioning of defect depth small change of echo height was registered for the in what precedes we have found that IHS! treatment specimen with EDh1 notch, and that for both speci-produces no significant shift on the ultrasonic properties mens the values obtained for i have been found to be of the material. Some considerations are presented very small compared to the corresponding values of a. | |||
; below on the relative merits of different methods of 4.2 Effects brought by IHS1 on defect dimensioning defect dimensioning. | |||
Plots similar to those of Fig. 6 are presented in figs. 7 | |||
; The data in Table J include those obtained from and 3 respectively for flaw length and depth, to compare Flaw Tip Echo Alethod, as well as from the AShtE the nicasurements obtained before and after IHSI. As technique: Compared with the actual measurements in the case of echo height, an appreciably higher scatter-ing of plots is observed for the specimen with IGSCC, made by microscopic observation, appreciably undefr 3 as compared with that of EDh1 notch. But again, the estimated values are noted for the results obtained wid' the ASNfE technique (both by 1/2 max. and 50% DAC relation of very small I compared with a is indicated in criteria), whereas the Flaw Tip Echo hiethod is seen to Tsjh/c .'. where the negatisc values of I signify a shift ~ | |||
give values nearer the direct visual measurements by el crack dimension to the larger side, and rice tersa. | |||
microscopy on sectioned specimens. An exampic of the 4 | |||
, 'vd 15 N3. 4 October 1982 | |||
.This 3 Camparison d flaw h:ight measurement | |||
*f.,.,;. , . - ;, | |||
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by UT cnd deseructiva assay (unitt mm) .O . ., je N: ,/ | |||
~t . ,, ' '' * ' ')j EDM (post IHSil SCC (post lHSI) * | |||
[e s .. ..l .(., . *. , j;p-w ual 50'; l/2 Tip Actual 50*; il2 Tip - | |||
~ | |||
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''aM 4.95 3.i 1.6 3.2 J.So I.8 2.2 3.8 - | |||
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otomicrographs obtained on sectioned sample for ,, g . _- (,' ,1 7 i tal crack measurement is presented in Fig. 9, which .'.;f .1 ,, M M*g. t | |||
:als a crack configuration very similar to those 3,Q '';,(0, | |||
* terved in IGSCC detected in BWR plants. b ~ .' ' | |||
Jt: | |||
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:rasonic measurements were applied to two speci. . J,] , v 5 d | |||
ers of welded joint artificially provided with defects t ,___ 9 . .'' 9" m:,fi means of EDM and IGSCC, these measurements N. - W | |||
* r . ".7* | |||
.M 7$r.'h eing performed on the same position before and after - | |||
k- wr ;- .U | |||
.151, with a view to determining the existence of any 7' N A < %. 5 QD.* '.<j s.nsistent shift in ultrasonic properties due to the IHSI -b 'M g Y- | |||
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.eatment. The results obtained from this experiment - | |||
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., -'c,'5 i [\ f i;'c . /n sovided that: | |||
il) in respect of echo height, the effect of IHSI is j .. i | |||
\[.'. ~g | |||
> J$- | |||
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negligible, and the deviations of measurement are . | |||
.., p . s . | |||
g.k-}9%.l'"~M | |||
:;;3,. | |||
attributable to normal measurement errors. | |||
(2) The results of defect dimensioning (crack length and depth), while varying to some extent with the . ,,,,,,,,,, | |||
h method of measurement, denied in all cases the esistence of any consistent causal relation between Fig. 9 Produced SCC and microstructure of sample l IHS! and ultrasonic data. | |||
l 131 For evaluating crack depth, the Fisw Tip Echo tion Heating. EPRI-NP-814-LD (Prepared by Ishi-Alethod was found to be effective, from comparison kawajima Harima Heavy Industries Co., Ltd.) 1981 i mth actual measurements made by microscopic (4) Nondestructive Evaluation Program: Progress l observation on sectioned cracks. in 1979, EPRI NP-1234-SR Special Report Dec. | |||
l , | |||
1979: T. Kawamoto: Production of Controlled REFERENCES IGSCC in large Diameter Pipe, PR 1488-7 l ali Proceedings: Seminar on Countermeasures for (5) Investigation of NDE Reliability and Fracture l | |||
hpe Cracking in BWRs EPRI WS 79174 Vol. I- Mechanics, Phase I Report NUREG/CR-1696 4 1980 1980 t2) T. Umemoto and S. Tanaka: Residual Stress (6) D. M. Corbly, P. F. Pacman and H. S. Pearson: | |||
Improvement by Means of Induction Heating IH1 The Accuracy and Precision of Ultrasonic Shear Engineering Review Vol.11 No. 4 Oct. 1978 Wave Flaw Measurements as a Function of Stress rp.11-20 on the Flaw, Mat. Eval. 28 1970 131 Residual Stress improvement by Means ofInduc. | |||
Attachment 1 ' Docket No. 50-277 Fi 6ure 1 lby 23, 1983 g | |||
Peach 30tto:2 Unit #2 RIIR Suction; ' Pipe to Elbow Weld: 10-0-6 k tig 20 | |||
. " diameter Assume 64" circutzference b | |||
Graphie Plot of the location and thru-wall depth of all ultrasonic indications, assumed to be ciacks. | |||
., Ps es s ' oe T=.T E | |||
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Attachm:nt 1 Docket No. 50-277 Figure 2 . May 23, 1983 | |||
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DOCKET NO. 50-277 ' | |||
ATTACEMENT II MAY 23, 1983 PHILADELPHIA El'ECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 12153841 4000 May 20, 1983 Docket No. 50-277 Mr. J. M. Allan, Acting Administrator Office of Inspection and Enforcement U.S. Nuclear Rogulatory Commission 631 Park Avenue King of Prusnia, PA 19046 | |||
==Subject:== | |||
License Event Report Narrative Description Dear Mr. Allant The following occurrence was reported to Mr. A. R. | |||
Blough of Region I, U.S. Nuclear Regulatory Commission, on May 6, 1983. | |||
I | |||
==Reference:== | |||
Docket No 50-277 Report Number: 2-83-11/IT-0 Report Dato May 20, 1983 Event Date: May 6, 1983 Facility: Peach Bottom Atomic Power Station BD 1, Dolta, PA 17314 Technical Specification | |||
==Reference:== | |||
Tochnical specif.ication 3.6,0, structural Integrity, f states that, "The structural integrity of the primary system l | |||
boundary shall be maintained at the lovel required by tho original acceptance standards throughout the life of the station. | |||
The reactor shall be maintained in a Cold Shutdown condition until each indication of a defect has been investigated and evaluated." | |||
L | |||
page ? | |||
Mr . J . M. All an Description of the Event: | |||
Analysis of ul trasonic tanting data confirms the presence of cracks in the 20" RHR shutdown cooling suction line. | |||
These cracke are located in the heat af fected zone of the pipe and elbow at weld 10-0-G. Attachmont T of this letter shows the location of this weld in tha RHR nhutdown cooling suction line. | |||
Attachment TI of this letter to a graphic plot of the location and depth of all ultranonic indications in wold 10-0-6. The pipa side of the weld is 0.4" thick and the elbow side of the weld Tn in 1.1" thick. The cracks are all circumferential in nature. | |||
the pipe side the longest single crack length is approximate 1v 48" 1.ong and the maximum thru-wall depth is 0.4" . In the elbow side of the weld the longest single crack is 18" long and the maximum thru-wall depth is 0. 5" . | |||
Conditions Prior to Occurrence: | |||
During the current Unit 3 refueling outage, while performing non-destructive examinations following Induction Heating Stress Improvement Treatment of Reactor Recirculation and RHR Suction Lines, as of May 6, 1983, indications had been found in the heat affected zone of 12 welds of the treated piping. | |||
Three of the weldsThese were in the 20" welds are non-isolatable section identified 10-0-5, 10-0-6ofand the RHR nuction lino. | |||
10-0-7. Of thene three welds, the 10-0-6 weld had the most nevere indicationss and also had the highegt stress rule index number (SRI-2.095). The remaining 9 welds that had been identified with indications on Unit 3 were 9 of the ten 12" (For vertical riser to elbow welds in the recirculation risers. | |||
further reference information on Unit 3 indications, see LER 3-R3-12/IT-0.) | |||
On May 3, 1983, Unit 2 had been shutdown for maintenance initated by a value packing leak in the drywell. During this | |||
. outage, in light of th9 indication findings in Unit 3, the The | |||
' decision was made to examine certain welds in Unit 2. | |||
nelection of the welds to be inspected was made by considering SRI numbers and by choosing a representative sample of welds in Unit 2 that were typical of the wolds found with indications in Unit 3. Three welds were chosen to be inspected. On the reci rcul ation system piping, the vertical riser to elbow weld with the hiqhest SRI number in each of the A and B loops was chosen to be inspected. In the nHR shutdown cooling suction line, weld 10-0-6 was chosen; as mentioned above, wold 10-0-6 in Unit 3 had the most severe indications and the highest SRT numbar | |||
n - _- ._ | |||
A Mr. J. M. Allan paga 3 of the three welds found with indications in this line. This program was discussed with the NRC ntaff in Region I. | |||
Cause of the Event: | |||
The analysis of the data shows a pattern typical of intergranular stress corrosion cracking. | |||
Anal vnis of occurrence: | |||
on Unit 2, weld 10-0-6 was the only wold of the throo welds inspected that was found with indications. These indications were confirmed as cracks. A fracture The mechanice crack growth annlysis was performed by the NSS vendor. | |||
eval uation was performed using the initial average crack depthn of 0.3" on the pipe side of the weld and 0.4" on the olhow sido of the weld. For the analysis, conservatively, the' crack was assumed to be a 360 degree circumferential crack. Analysos were norformed with and without considering the beneficial offectn of the weld residual stresses. The analyses also used a conservative applied stress value of 13KSt. The analyses showed that with the maximum crack growth rate for weld sensitized material, the stress in the pipe would not exceed code allowable if oporation continued up to six months. | |||
Augmented Surveillance Steps Taken: | |||
/ | |||
Unit 2 is presently scheduled to begin a refueling outage on October 14, 1993; this represents a period of operation of loss than 5 months. Additional measures have been taken to increase the surveil. lance on the piping in Unit 2. | |||
Ry I,icense Amendment Application dated May 3, 1.9 8 3 , | |||
Philadelphia Electric Company requested changes to the Technical specifications for Peach nottom Units 7 and 3 to meet the coolant | |||
" Technical 1,9ak age cri teri a identified in NOREG 0313, Revision I, Report on Material Sel ection and Proconsing Guidelines for DNP Coolant prosaura noundary Piping". | |||
On May 8, 1983, EPRI approved " Water Sensitive Tapo" was installed on 10 selected welds in Unit 7 to improve on early warning detection. Three riser to elbow welds in each recirculation loop, and four welds on the RHR shutdown coolinq suction line were selected for tape installation. Thin tape in calibrated to alarm on a very low amount of water leakage | |||
Page 4 Mr. J. M. All.an (approximately 2 dropn of water) an'i has been utilized in other Nuclear facilities for thin purpose. | |||
The resul.tn of the fracture mechanics anal.ysin were cent to the NRC staff in Bethesda. On May 9,1903,TheUnit 2 returned to Phil adelphi a servico af ter concultation with NRC 9taf f. | |||
Electric Comnany Operation and safety P.oview (O&SR) Committee h7n reviewed the untire event and han concluded that continued operation until refueling outage in October, 1983, is 9ata, philadelphia Electric Company's renponse to I.E. | |||
Bulletin 83-02, to be submitted before resuming power operatione af ter refueling outaqo, will provido all additional. information on this subject. | |||
S ncerely, | |||
/c w ' | |||
. Cooney erintendent Nuclear Generation Division Attachment . | |||
cc: Document Control Desk A. R. Blough/Sito Inspector | |||
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DODW.)C.A3lb D.VDV\J U UVtDV X2A>U V | |||
. CONTROL 0 LOCK: l l l l l l (PLEASE PRINT OR TYPE ALL RECulRED INF ORMATION) i e@ . | |||
O li j lP J A J P j B l S l 2 l@l0 10 l 10 LICENSE l0 l0 NUMeEH l0 l0 l- l0 10 @26l 2h 4l1LICENSE l1 11TYPE l 1.j@l 40 l | |||
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P O 9 LICENSEE CODE 44 IS CON'T I 0liI $"nN LL_J@l015 10 l- 10 1217 1760 l@l GU 01 EVENT s !0DATE I s I el 374 l@lo 7b l REPORT | |||
<;l a DATEi of n I 60,l@ | |||
J 0 GU G8 DOCKET NUMUEll EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES h l0l2] lDuring a forced outage on Unit 2, while performing a special inspection,( | |||
l0j3j l an indication was found in the heat af fected zone of a 20" RIIR shutdown l 10141 I cooling suction line weld. Indications were found in both the pipe and l Indications were circumferential in pipe and l 10151 l elbow side of the weld. | |||
101c 1 t elbow. A'similar event is referenced in Ler 3-83-12/lT. ; | |||
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OE COOg S DC OE COMPONENT CODE SUS O'E SU lOI9l lC l Fl@ LxJ@ LzJ@ (P l Il Pl E I xl X '@ . Ej@ J i a e iQ in 12 :a a e ao RE R 005 N EVENT YEAR LE H I 0111 11 M 10111 [TJ [ -j lol | |||
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* 30 31 32 UP Li MANL ACTURER AK N ACT O PL NT METN[ HOUR $ 72 58 IT POR S. | |||
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42 IN 43 l@ 44 di CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 11101l The indientions show nattern typical of intercranular stress corrosion [ | |||
cracking. A fracture mechanics analysis performed by the NSS Vendor , | |||
gl i showed that crack growth from now to fall 83 refueling outage is , | |||
g j negligible and continued operation is justified for up to 6 months without repair. EPRI approved water sensitive tape applied to 10 welds, gl | |||
* OiscovERY OEsCRi, TION @ | |||
'sT2Ws* srowER E LoJ@ l 01 of ol@l OTnERsTATUs NA | |||
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A[TIVITY CO TENT LOCATION OF RELEASE CTIVITY j RELE A5ED OF RELEASE AMOUNT MF i NA i | |||
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NAME 01 PREPARER-lMV . 000nOY M PHONE: | |||
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LER 2-83-11/IT Attachment II ., May 20, 1983 i | |||
Peach Botton Unit #2 j | |||
RHR Suction; Pipe to Elbow Weld: 10-0-6 20" diameter Assume 64" circumference tt\ | |||
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ATTACHMENT I May 20, 1983 LER 2 11/IT | |||
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May 23, 1993 Docket No. 50-277 ATTACHMENT TII PEACH BOTTOM UNIT 2 INSTALLED MAY 1983 Moisture Detection Systems | |||
===System Description=== | |||
The system utilizes a moisture sensitive tape that was developed in 1957, patented in 1969 and has been marketed since 1991 by Techmark Limited. The system has a digital display / control unit which uses a multiplex sensor scanning technique. The moisture censitive tape consists of a membrane construction containing two layers of polimide film (one with a 0.5 square inch hole) sandwiching a chloride -f ree salt impregnated web. The sensitivity of this tape is such that a few drops of water or the presence of saturated steam will activate the tape. | |||
The digital display / control unit which is located in the reactor building outside the primary containment contains a digital sensor identification display and green, red and yellow LED's to indicate system operation, detection of l eak, and system troubles, respectively. | |||
There are 10~nensors installed on 6 recirculation risers and 4 PHR shutdown cooling suction line welds. The welds with the moisture sensitive tape installed.are welds, 2-AHK-2, 2-AHJ-2, 2-AHH-2, 2-BHE-2, 2-BHD-2, 2-BHC-2, 10-0-3, 10-0-5, 10-0-6 and 10-0-7. These welds in Unit 2 were chosen for tape installation because similar welds in Unit 3 had been found with cracks durina Unit 3 refueling outage. (See attached sketch.) Leak detection annunciation is provided in the main control room with visual indications at the display / control unit in the reactor building. | |||
Surveillance Procedure The operating staff will check the functions of the display / control unit once per shift. The control room alarm will be checked concurrently. | |||
Page 2 Action Requirements The *ollowing actions are reouired for leak indications or monitoring system failures. | |||
In the event that the alarm is received in the control room: | |||
: 1. The control room operator (ACO or CO) shall check the Drywell sump flow recorders for any increase in pump-out frequency and check on the status of the Drywell radiation monitor trouble alarm (indicates alarm at the local panel). | |||
: 2. The control room operator (ACO or CO) shall I dispatch a qualified floor man to check the moisture monitor local display / control unit immediately. | |||
: a. If the " Red" Led is lit, the floor operator | |||
, should reset it. Tf it relights, call the i Unit 2 Assistant Control Operator (ACO) or the Control Operator (CO) immediately. If it does not relight (if there is moisture on the tape, the red light should come back on in about 6 seconds), wait for 5 more minutes and then report results to the Unit 2 ACO or the CO. | |||
The qualified floor man should also check the drywell radiation monitor recorder charts at the local panel for any increased activity (this panel is located at 135' elev. in the reactor building). | |||
I | |||
: b. If the "Yallow" Led is lit, the floor operator j should attempt to reset it. If it relights, shift supervision is to be notified. | |||
1 | |||
: 3. If the indication of leakage appears to be valid, l shift supervision is to be notified and the unit is to be shutdown in an orderly manner. The Unit should be in hot shutdown condition in 12 hours and in the cold shutdown condition in the next 24 hours. Shift supervision will inform the duty senior staff engineer. The NRC must be contacted via the RED PHONE within one hour; an open line is not required. | |||
: 4. If the moisture monitoring system is found to be inoperable, shift supervision shall initiate an | |||
Page 3 hourly monitoring of the Drywell sump operation to detect any increase in pump-out frequency and an hourly incpection of the Drywell radiation monitor recordern to detect any increase in Drywell airborne activity, until the moisture monitoring system can be returned to service. The duty senior staff engineer should be notified as soon as possible. The NRC should also notified promptly via normal reporting channels. | |||
Bases The water sensitive tape is being used to alarm leakage from piping within the pressure boundary. To be consistent with Standard Technical Specifications, NUREG-0123, Revision 3, if leakage is known and located to be pressure boundary leakage, the reactor will be shutdown to allow further investigation and corrective action. | |||
Duration of Need # | |||
This Moisture Detection System (moisture sensitive tape) shall only be in-servi'ce until start of October, 1993, refueling outage on Unit 2. | |||
l | |||
, ATTACHMEIPR III. DOCKET NO. 50-277 MAY 23, 1983 I I ON LINE _Li i l LEAK DETECTION i | |||
~- | |||
SYSTEM r l-FOR NUCLEAR & FOSSIL FIRED GENERATING PLANTS Early warning of small steam leaks Continuous on line monitoring of piping integrity Precise location of leak announced by visual and audible alarm Reduces radiation exposure of personnel Can be installed during scheduled outages Production capacity to meet the most demanding schedules 15 years experience in Leak Detection | |||
( | |||
l TECHMARK LIMITED Yacht Haven,326 First Street, Annapolis, MD 21403 Telephone: 301-263-6600 Tele >c 87-424 l | |||
l 1 _ _ _ _ _ _ _ _ | |||
4 | |||
+ ON LINE LEAK DETECTION SYSTEM + | |||
The Techmark Leak Detection System is designed to 180*F. The present temperature limit of the tape is relay the status of leak detection sensors to a central over 300*F. | |||
control location. The exact method of signal transmission When a small area of the web bete een the two depends upon the chosen system: two wires or multiplex. conductors is moistened by water or saturated steam, the The System as originally designed by Nutec, has been sensing element experiences a drastic change of electrical further developed by Techmark to utilize the latest modular, resistance. The high-purity water normally encountered in solid state construction, designed and constructed to power plants has a resistivity in the megohm range, so the meet the most stringent requirements. A wide range of water itself would not provide this change in resistance of control functions are available. the sensor. However, the web is impregnated during 7he moisture sensitive tape was developed originally to manufacture with chloride free chemicals whictt wtlen cc,ntinuously monitor possible leaks from valves, flanges activated by water, become electrically conductive. The and pumps, etc in a heavy water reactor system. Dunng sensing element maintains a low resistance as long as the the years since its development the need for a simple, moisture remains When the moisture evaporates and the reliable and inexpensive system for the early detection and web becomes dry, the resistance returns to its original locating of small leaks has escalated, high value. | |||
THE TECHMARK LEAK DETECTION SYSTEM provides A few drops of water will activate the tape. 5atu EARLY WARNING AND SPECIFIC LOCATION or the leak. rated steam has the same effect. Operation of the The present utilization of humidity, sump level and radiation system is independent of water quality, since the con-monitoring provide only the information that a leak has ductivity factor is established by impregnants in the occurred somewhere. tape. Borated water will activate the tapejust as well in a nuclear plant, the ability to precisely locate a leak as pure water, during cperation minimizes the time and exposure to Upon reaching the moisture sensitive tape the steam radiatio iin taking corrective action. The Techmark System will condense and activate the tape; the display / control provides the operator information that currently is senses this change and triggers the alarm. | |||
not a./ailable. | |||
The System consists of a sensing element that provides SENSOR CARRIER an electrical signal when activated by moisture, and an ir'dicating device which converts the electrical signal from in order to provide an unrestricted path for the steam to the sensor to a visual and/or audible signal. The display / reach the moisture sensitive membrane, a 0.5" diameter control alerts the plant cperator to the presence of hole is dalled through the insulation to the annulus moisture in a specific loca'. ion. between the steam pipe and the insulation. The sensor carrier consists of a stainless steel tube welded to a plate approximately3.0" x 3.5",and a fast disconnect connector. | |||
MOISTURE SENSITIVE TAPE The sembpermeable membrane is adhered to the plate with the non-permeat'le side exposed to ambient and the The moisture sensitive tape is a semi-permeable mem- hole centered over the tube. This insures that only steam brane permitting steam or moisture to enter from the pipe, moisture from the pipe will reach the membrane's while prohibiting moisture entry from ambient. impregnated web. | |||
The membrane construction is two layers of polimide When used with the TUM System, the transponder is an film l one with 0.5 sq in. hole) sandwiching a chloride free integral part of the assembly. | |||
salt impregnated web. Pnor to assembly two silver con-ductors are applied to the impregnated web. Thermo- DISPLAY CONTROLS SYSTEMS setting adhesive bonds the layers as well as the membrane to mounting surface. The original Nutec System required four (4) wires per The moisture sensitive tape i'; applied on the exterior of sensor to be returned to the Display Control Panel. With the thermalinsulation The tape is mounted on a stainless the rising costs of field wiring and few penetrations steel plate for ease of installation and to ensure an available; Techmark developed three new Display Controls impervious seal to ambient conditions The tape is therefore - TM 1008 (hard wired) (two w!res per sensor) and the near the skin temperature of the insulation - 150*F- TUM 100 and the TUM 700 multiplex system. | |||
I TM 100B-TWO WIRES / SENSOR System allows the installation of up to 700 Leak Detection CHANNEL-HARD WIRED Sensors or locations utilizing only 4 conductors. A digital display provides the exact location of the sensor which is in G:neral: alarm or trouble. | |||
Techmark's TM 1008 is a solid state control receiver Redundancy is achieved with the TUM 700 by returning which receives and displays alarms from the moisture 4 conductors to the display / control. Even if all conductors sensitive tape. The System continuously supervises all were severed at a particular location, there is no loss of wires leading to the sensors as well as the sensors larm or trouble cono; tion from subsequent sensors. | |||
themselves Provisions to control remote functions are System | |||
== Description:== | |||
available to suit indwidual requirements A. Display / Control: Two models are available-TUM System | |||
== Description:== | |||
100 (capacity 99 sensor zones) and TUM 700 (capacity The System consists of multiple, two channel circuit 700 sensor zones). | |||
cards Each channel can have one or more sensors 1. Digital LED display of sensor location for A! ARM connected by a pair of unshielded wires with a resistor or TROUBLE. | |||
placed at the end of each sensor channel to supervise not | |||
: 2. Multiple alarms are displayed in ascending order and only the wires, but the sensors themselves Each channel has indrvidual LED indicators, which are latched in memory until manually eliminated. | |||
provides the operator with quick and positive identifica- 3. All sensor zones are interrogated every 1.5 seconds tiort The indications are as follows. Alarm condition must be sensed in two consecutive sweeps before display. | |||
Self Test Alarm 4. RED LED - Indicates leak. | |||
Green Red 5. GREEN LED - Flashing indicates system logic System Status LED LED functioning. | |||
Normal Steady Out 6. YELLOW LED - Activated in the event of any Leak Alarm Steady Flashing system trouble. | |||
Channel Fault-Sensor Out Out 7. Additional YELLOW LEDS are activated in the event ' | |||
Channel Fault-Wiring Out Out of Battery Trouble, Ground Fault or Disconnect (any Sensor Dry (After Alarm) Steady Steady (Until Reset) function out of normal operations). | |||
When a channel is in alarm, the alarm red LED will flash 8. Controls-SYSTEM TEST and an audible signal will sound. The LED will continue to flash while the sensor is wet. When the red LED is steady, ALARM RELAY CVERRIDE TROUBLE SILENCE indicating the sensor is dry, the channel is ready to be SYSTEM RESET reset. This is accomplished by depressing the toggle switch to the lowest position (Reset),and then placing the ACKNOWLEDGE switch to the upper position l Normal). The channel is now 9. Operating Voltage 120 VAC. No other external ready to receive another alarm. power is required for system operation. | |||
A manual test switch is included for each two channel circuit card which checks the ability of the display / control B. Wiring Required: 4 Conductor- 18 Gauge Shielded to receive an annunciate the sensor status. By depressing the switch the red LEDs will show alarm (Flashing), the C. Transducer: For each sensor zone or location a transducer is required. The transducers and sensors are green LEDs will be steady and the audible alarm will sound. Once the operator is satisfied with the results, wired in series , | |||
both channels shou;d be reset. D. Redundancy: By returning the 4 conductor,18 The TM 100B is dasigned with provisions for multiples gauge shielded wire to the TUM 700 Display / Control, of two channel circuit cards mounted into standard sensors are monitored in both the clockwise and 19" racks counter clockwise direction in the event of a line break Power requirement is 120 VAC. or other trouble. This feature is not available on the TUM 100. | |||
TECHMARK/ TIME DISTANCE MUTIPI.EX DETECTION SYSTEM (TUM) E. Options: | |||
Battery Standby General: Remote Digital Display Techmark introduces a unique multiplex system utilizing Computer or Printer Interface DC interrogation of sensor status, based on the time-distance principle, rather than AC discrete address. This F. Qualification: Environmental Qualification only design is less susceptible to spunous alarms The TUM supplied for TUM 700. | |||
BACKGROUND monitoring feedwater and main steam (90 welds per plant) since 1978. | |||
The moisture sensitive tape was developed in 1957 by The ability of the tape to dry out after being wet was ACF. The tape was installed on sma!I test reactors demonstrated at Pennsylvania Power and Light's Martins including Georgia Tech., M.I.T., ispril, and R-2 Test Creek Plant in a three month demonstration in 1980. | |||
Reactor (Sweden). The tape was patented in 1969, and Demonstration of the Techmark Leak Detection System manufactured by Allis Chalmers and Nutec Inc in 1981, was conducted for the EPRI BWR owners group at the Techmark Limited purchased Nutec Inc non-destructive test center in Charlotte on June 15,1981. | |||
Testing and evaluation of the Nutec system began in A contract has been awarded to Action Environmental 1957 at the ACF Nuclear Products Erco Lab. Testing has Testing Corporation to environmentally qualify the TUM been conducted at the University of Maryland, M.I.T., 700 Techmark Leak Detection System using IEEE 323-74 Brookhaven Combustion Engineering and Detroit Edisort and Nureg 0S88 as program guides. | |||
A demonstration of sensitivity to small leaks was given to observers from the N.R.C. and the Power industry at CLIENTS Acton Environmental Testing Corporation on March 1,1982. | |||
Dairyland Power, Commonwealth Edison, Brookhaven National Laboratory, Detroit Edison, NUS (Antartica), CLIENTS - TUM MULTIPLEX Misubishi, Sumitomo, RWE (Germany), Viginia Electric and Power ( l 80 locations), Pennsylvania Power and Light Tennessee Valley Authority Browns Ferry 2. Installed 2/83. | |||
(test), and Argonne National Laboratories. | |||
The installation at Virginia Electric and Power's North Vermont Yankee Nuclear Pt Ner Corporation: Sensors Anna Units 1 and 2 Steam Plants has been in service shipped 3/83. | |||
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+L1MiTED-Yacht Haven 326 First Street. Annapolis, MD 21403 Telephone: 301-263-6600 Teler 87-424 I | |||
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ATTACHMENT IV Docket No. 50-277 Philadel phia El ectric Company Peach Bottom Atomic Power Station Responses to Questions Addressed In May 20, 1993 Meeting between Philadelphia Electric Company and Nuclear Regulatory Commission Technical Staff Question: | |||
(1) What procedures were used to measure through wall depth of cracks? | |||
===Response=== | |||
Procedure for sizing non-geometric indications is as follows: | |||
: 1. Thickness readings and surface contours are taken on all welds at a minimum of three locations arouond the circumference. Additional thicknesses and contours are taken as required. See Fiqure 1. | |||
; 2. Metal paths W1, WM; W2 are taken, where: | |||
W1 = Minimum metal path at 20% DAC. | |||
WM = Metal path at maximum amplitude W2 = Maximum metal path at 20% DAC. | |||
: 3. Cross sectional plots are constructed using the appropriate surface contours and thicknesses. | |||
: 4. The shear wave refracted anale is determined from the calibration standard of the same material, diameter and thickness as the weld being examined. | |||
: 5. The ultrasonic data is then anplied to the cross sectional plots and the maximum thru wall depth of the | |||
- indication is measured directly. | |||
Page 2 This technioue has proven to be the most conservative, i.e., provides the deepest thru wall dimension of an indication. The crack tip method using the formula: d= | |||
(WM - WI) cos 0 has been shown to provide depths 10 to 20 percent less than the method described herein. | |||
Question: | |||
(2) Does the code permit averaging of varying crack depth measurements to arrive at a uniform depth for analysis purposes? Where is this documented? | |||
===Response=== | |||
The code procedures characterizing long (approaching 360 degrees) circumferential cracks with local variations in depth are unclear. However, the allowable flaw sizes in Apendix X, Section XI, are based on a limit load treatment of the cracked section which is strongly dependent upon the cracked area rather than the local maximum depth. Therefore, the use of an average depth based on the crack area is consistent with the technical basis for Appendix X. | |||
Question: | |||
(3) By what procedure was the 0.3 inch " Average" flow depth determined: What is the error bank? | |||
===Response=== | |||
The assumed crack depth of 0.3 inches represented a reasonable but conservative measure of the average depth. | |||
i This depth was exceeded only at two isolated locations of 2 in ches (depth 0.4 inch) and 3 inches (depth 0.35 inch) out of a total circumference of 64 inches. In fact, the crack depth was 0.2 inches or less over 57% of the circumference. | |||
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1 e | |||
i Page 3 Question: | |||
(4) This weld was-stated to have a SRI of 2.95. This is very high, and appears to be inconsistent with the stress ratio of 7 | |||
0.8 weld in the code calculations for allowable crack depth. | |||
: How were these values determined? Can they be shown to be 3 | |||
inconsistent with each other? | |||
===Response=== | |||
f The stress rule index considers pressure, sustained thermal | |||
;~ | |||
expansion, and residual stresses. It also includes the effects of local discontinuities and stress concentrations. | |||
On the other hand, the stress ratio numbers, (Pm + Pb)/Sm, used in determining the allowable flaw sizes consider only the primary loads across the whole section. Such loads are pressure, dead weight, and seismic. Thus, there is no inconsistency between the higher SRI and the assumed (Pm + | |||
Pb)/Sm stress ratio. | |||
Question | |||
! (5) What are the loads and stresses in this joint during | |||
-emergency and faulted conditions including SSE? | |||
===Response=== | |||
The highest calculated OBE stress in the RHR supply line is i | |||
given in the stress report as 2050 PSI. Therefore, the maximum SSE stress would be expected to be no greater than 2 x 2050 or 4100 PSI. The primary stress for emergency / faulted conditions are expected to be less than 14 KSI. However, the allowable flaws were calculated on the basis of the-normal / upset condition loads because they were more limiting than those considering the emergency / faulted loads. | |||
i Question: | |||
(6) Provide the details of crack growth rate estimate. What are the crack growth rates used in the calculations of the remaining operating life? | |||
e f | |||
Page 4 i | |||
===Response=== | |||
The IGSCC crack growth rate was based on a conservative i estimate of the sustained stresses. The sustained stresses l consist of pressure (axial), weight, and thermal-expansion | |||
! stresses and the residual stress. In order to make a conservative estimate.of the crack growth rate, the residual stress, which is compressive in the mid-thickness region in a large-diameter pipe, was not considered in the evaluation. | |||
The sustained stresses at the weld 10-0-06 were determined to be approximately 13 KSI. The calculated crack growth is | |||
, shown on the flaw acceptence diagram shown in Figure 2. | |||
Additional information relative to this question has been provided directly to the NRC staff and will be submitted formally as soon as hard copy is available. | |||
Question: | |||
~ | |||
4 (7) Provide details of calculations that show the allowable crack l denth of 58% of the wall. | |||
===Response=== | |||
, The allowable circumferential crack depth is based on the-I stress ratio, (Pm + Pb)/Sm. The (Pm + Pb)/Sm term consists of pressure, weight and OBE (inertia) stress terms. These were determined to be approximately 11 KSI at the weld 10 , | |||
: 06. With Sm = 16.8 KSI @ 550 degrees F, this gives a stress ratio of approximately 0.7. Per Table IWB-3641-1, Section i XI, the acceptable depth as a fraction of thickness for a j fully circumferential flow is 0.58 when (PM + Pb)/Sm is 0.7. | |||
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O I i i i 0 0.2 0.4 0.6 0.8 1.0 FRACTION OF CIRCUMFERENCE a/ir Figure 2 Plow Acceptance Diagram for Indications at Peach Bottom Units 2 and 3 Weld 10-0-06. | |||
May 23, 1993 Docket No. 50-277 ATTACHMENT V INTERIM SURVEILLANCE AND LIMITING CONDITION OF OPERATION FOR PEACH BOTTOM-ATOMIC POWER STATION, UNIT 2 THROUGH OCTOBER 1983 Attached are the interim proposed surveillance and limiting conditions for operation regarding coolant leakage to be incorporated into the Peach Bottom technical specifications to support Peach Bottom Unit 2 operation through October 1993. | |||
These interim measures are required to support continued power operation of Unit 2 with a crack at weld No. 10-0-6 on the non-isolable 20" RHR shutdown cooling suction line. | |||
The interim limiting conditions for operation reflect those contained in the Standard Technical Specifications (NUREG 0123, Rev. 3) with the following exception. The rate of change of 2 gpm per 24 hour surveillance period is applicable only when the reactor mode switch is in the RUN position. Standard Technical Specifications apply this LCO to reactor operations in the RUN, STARTUP or HOT SHUTDOWN mode. During reactor operations in the startup mode, large variations in primary coolant system pressure result in changes'of measured leakage not indicative of | |||
, system degradation. This rate of change criteria, if applied during STARTUP operations , could preclude reactor power operation since the LCO for the rate of change of unidentified leakage would most likely be exceeded, resulting in unit shutdown. The maximum leak rate of 5 gallons per minute during the limited duration of the startup phase will assure primary coolant system | |||
* j integrity during this time period. | |||
1 To monitor and alarm pressure boundary leakage, a moisture detection system, consisting of water sensitive tape, has been applied to ten susceptible welds in the RHR shutdown cooling suction line and vertical recirculation system risers. | |||
To be consistent with the Standard Technical Specifications (NUREG 0123, Rev. 3) if leakage is known and located to be pressure boundary leakage, the reactor will be shutdown to allow further investigation and corrective action. This system will remain in service as an interim additional leak detection system through October 1093. | |||
l | |||
_2_ | |||
To determine coolant leakage monitoring systems operable, the current Peach Bottom Technical Specifications (see Table 4.2.E of PBAPS Tech Specs) will remain in ef fect. This includes the Equipment Drain Sump Flow Rate Monitor, Floor Drain Sump Flow Rate Monitor, and Primary Containment Air Sampling System. These systems are all demonstrated operable in the following manner at the stated frequency: | |||
- functional test once per month | |||
- instrument check once per day calibration once per 3 months t | |||
INTERIM SURVETLLANCE AND LIMTTING CONDITION OF OPERATION FOR PEACH BOTTOM ATOMIC POWER STATION, UNTT 2 THROUGH OCTOBER 1983 LIMTTING CONDITIONS FOR OPERATION SURVETLLANCE REQUIREMENTS 3.A.C. Coolant Leakage 4.6.C Coolant Leakage | |||
: 1. Any time irradiated fuel is 1. Reactor coolant system leakage in the reactor vessel and reactor shall be determined by the coolant temperature is above sump or air sampling system 212 degrees F, the rate of and recorded every 4 hours reactor coolant leakage to the or less. | |||
primary containment from unidenti-fied sources shall not exceed 5 gallons per minute. The rate of change of unidentified leakage shall not exceed 2 gallons per minute per 24 hour surveillance period when the reactor is operated in the "Run" mode. In addition, the total reactor coolant system leakage into the primary contain-ment shall not exceed 25 gpm averaged over any 24 hour surveillance period. | |||
: 2. Upon receipt of valid alarm from 2. The function of the moisture the moisture monitoring system, monitoring system display and the unit shall be placed in HOT control unit will be checked shutdown within 12 hours and be once per shift, in COLD shutdown within the next 24 hours. | |||
: 3. If the moisture monitoring system is found to be inoperable, an hourly monitoring of the Drywell sump operation to detect an increase in pump-out rate and an houriv inspection of the Drywell radiation monitor recorders to detect an increase in Drywell airborne activity will be initiated until the moisture monitoring system can be returned to service. The NRC will be notified promptly in accordance with Technical Specification 6.9.2 (Prompt | |||
-146- | |||
~ | |||
INTERIM SURVEILLANCE AND LIMITING CONDITION OF OPERATION FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 | |||
.THROUGH OCTOBER 1983 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS Notification with Written Followup) From and after the the date that_the moisture monitoring system is made or - | |||
; found to be inoperable for any reason, reactor power' operation is permissible only during the succeeding seven days unless the system is made operable sooner. | |||
i 4. Both the sump and air sampling systems shall be operable during reactor power oneration. From | |||
; and after the date that one of | |||
! these systems is made or found to be inoperable for any reason, reactor power'oneration is permissible only during the succeeding seven days unless the | |||
' system is made operable sooner. | |||
l | |||
: 5. If the conditions in 1, 3, or 4 | |||
' cannot be met, an orderly shutdown shall be initiated and the reactor shall be in Cold Shutdown Condition within | |||
, 24 hours, i | |||
1 L | |||
\ | |||
l -146a- | |||
-. .- -}} | |||
Latest revision as of 17:50, 13 May 2020
| ML20084M716 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/05/1983 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20084M711 | List: |
| References | |
| PB-83-1, NUDOCS 8306020303 | |
| Download: ML20084M716 (53) | |
Text
{{#Wiki_filter:A ULE ASONIC EXAMI!aTION rW ' SUBJECT CF WEEDS IN PIPE adams EASTERN SERVICE DEPARTMENT I pn f ,"n* ho P.B. 83-1 REV. 4PAGE 10F ( a**y,Q,*,*g4a"'o PREPARED 8Y/DATE f. f- , , 3 /h/8 "S PEA 01 BCTI'KM A'KHIC POWER STATION /(,[8 * - APPROVED BY/DATE (( , OA APPROVED BY/DATE jh p/ 3 Attachment 1 I)ocket no 50 277 May 23, 1933 l Exhibit 1 - I STATEMENT OF INIDOED USE l THIS DOQJMENT CDNTAI!6 INEOiWiPION PREPARED BY 'INE GENERAL ELECIRIC ODMPANY FOR' WE PHIIADELPHIA ELECTRIC CIEPANY NO IS INTE20ED POR USE BY WE EMPIDYEES OF B0frH COMPANIES. IT IS SUBMITTED 'IO THE PHIIADELPHIA ELBCIRIC COMPAW UPON 'INE CONDITION 'IHi IT WILL BE USED IN 'IHE (DtOUCT OF PHIIADELPHIA ELECTRIC CDMPANY INTERNAL TEDINICAL WRi MO WILL N3r IE RELEASED BY 'IHE PHILADELPHIA ELECIRIC CDMPAW 'IO COMPE'rI'IORS OF 'IEE l GENERAL ELECIRIC CIEPANY, WILL N7f BE DISEIBUTED EOR GENERAL IMXJSTRY MO WILL PM BE USED DIRECTIX OR ItOIRECILY IN AN UNFAIR CJMPETTITIVE MANNER 'IO 'IME INTERESTS OF EE GENERAL ELECTRIC COMPANY. I i PROCEDURE GAPGES OIA?GES 'IO 'IHIS PROCEDURE WIII, BE MACE IN N WTIE GENERAL F
- ECIRIC QUALITY ASSURA.C MANUAL, AND APPROVED BY PECo DGINEERI!G.
PEID APPROVAL PEED Ergineering Approval ( D& . ate C 4/ch3 EVIEWED BY7 bd, , APR 7 1983 PHILA. ELECTRIC CO. INSa.'.'i; a * 'CPECTION ( 8306020303 830323 PDR ADOCK 05000277 P PDR G EN ER AL h ELECTRIC
aro No P.B. 83-1 Revision No 4 Page: 1A of 20 f 'Ev'."." ens -
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gy pg i i i l PAGE REVISION IWIE CCM4ENTS
- 1 4 03/14/83 Opver Page
- 1A 4 03/14/83 List of Effective Pages i
2 0 12/01/82 3 2 01/03/83
- 4 3 03/14/83 5 0 12/01/83 s 6 0 12/01/82 7 3 02/04/83
'( 8 1 12/03/82 9 3 02/04/83 10 1 12/03/82 11 3 0.2/04/83 12 1 12/03/82 13 0 12/01/82 14 2 01/03/83 15 2 01/03/93 ., 16 2 01/03/83 17 2 01/03/83 . 18 2 01/03/83 19 2 01/03/83 20 2 01/03/83 ( . GEN ER AL h ELECTRIC
*' Procedure No. P.B. 83-1
- 1 Revision No. 0
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1.0 SCOPE 1.1 The ultrasonic pulse echo contact method examination described herein is applicable to full penetration circumferential and longt tudinal welds in piping systems. 1.2 The appitcable material thickness range is from 0.200 to 2.50 inches. 1.3 This procedure covers angle beam shear wave ultrasonic examination of piping welds and a straight beam longitudinal wave examination of piping base material through which the angle beam passes. 2.0 APPLICABLE DOCUMENTS 2.1 Codes and Standards. The following documents form a part of this specification to the extent specified herein.
- a. American Society of Mechanical Engineers (ASME) Bailer and Pressure Vessel Code
( (1) Section Y. Nondestructive Examination, Article 5,1974 Edition, Sumer 1975 Addenda (2) Section XI, Inservice Inspection of Nuclear Power Plant Components,1974 Edition, Sumer 1975 Addenda
- b. American Society for Wondestructive Testing (ASNT)
(1) Recomended Practice for Nondestructive Testing Personnel Qualification and Certification, SNT-TC-1A, Ultrasonic Testing Method - 1975 Edition
3.0 DESCRIPTION
3.1 The objective of the methods given herein is the location and recording of indications within the counter bore area, the heat affected zone, the fusion zone and the base material within two thicknesses (2T) of the weld. The examination shall be perfonned
- from the outside surface of the piping system.
4.0 REQUIREMENTS 4.1 Personnel 4.1.1 All personnel performing ultrasonic examinations shall be ( certified to at least Level I in accordance with SNT-TC-1 A, Ultrasonic Testing. Level I personnel shall perform the examination under the direction of personnel certifled to Level II or III. GEN ER AL $ ELECTRIC
Procedure No. P.B.03-1 ag of 20 senwicek
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4.1.2 All personnel reviewing the results of the ultrasonic examinations shall be certified to at least Level II in accordance with SNT-TC-1 A, Ultrasonic Testing. 4.1.3 When actual samples containing IGSCC are available at the jobsite, all inspection teams shall be trained on these samples prior to their perfoming any actual examinations. The purpose of this training is to allow the inspection teams to become familiar with the appearance and behavior of IGSCC indications in welded samples and to demonstrate their proficiency to the satisfaction to the person (s) responsible for evaluating the results of the examinations. The duration of the training shall be at the discretion of the responsible individual ( s) . 4.2 Equipment 4.2.1 Pulse echo ultrasonic equipment shall be used with contact search units. The ultrasonic instrument shall be equipped with a d3 calibrated gain or attenuation control. t 4.2.2 Angle beam shear wave examination shall be perfomed using single element trasmit/ receive or cual element pitch-catch ceramic type search units having a nominal frequency fran 1.0 to 2.25 MHz. Other frequencies may be used to obtain adequate penetration or resolution. 4.2.2.1 The size and configuration of search units should conform to the chart below. If piping geometry (weld crown width, mismatch, etc.) preclude the use of the recorvnended search unit (s), alternative
,eerch units may be used. The use of any dternative search unit (s) shall be documented as 3, ell as the reason the alternative was necessary.
Pipe Outer Diameter 7I n.) wa ll Thickness (In.) Search Unit Less Than 4.500 Less Than .750 1/4 Dia. or 1/4 sq. Single 1/4 x 3/8
- Dual Greater Than .750 1/4 x 3/4
- Dual Over 4.500 Through 12.750 Less Than .750 1/2 Dia. or 1/2 Sq. Single 3/8 x 3/4
- Dual 1/4 x 3/8
- Dual Greater Than .750 3/8 x 3/4
- Dual k 1/4 x 3/8
- Dual 1/2 Dia. or 1/2 Sq. Single l GEN ER AL h ELECTRIC
I Proceduro No. P.B. 83-1 sawics Revision tb. 3 Page 4 of 20
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(- ::=:== Pipe Outer Diameter (In.) Wall hickness (In.) Search Unit a Over 12.750 thru 20.000 Iess han .750 1/2 Dia. or 1/2 Sq. Single 3/8 x 3/4
- Dual 1/4 x 3/8
- Dual Greater han .750 3/8 x 3/4
- Dual 1/4 x 3/8
- Dual 1/2 Dia. or 1/2 Sq. Single Over 20.000 Iass h an .750 1/2 Dia. or 1/2 Sq. Single 3/8 x 3/4
- Dual 1/4 x 3/8
- Dual Greater than .750 3/8 x 3/4
- Dual 1/4 x 3/8
- Dual 1/2 Dia. or 1/2 Sq. Single Search units must be qualified on a cracked sample prior to use on piping welds.
i This qualification may take place on site, if a cracked sample is available, or at a location designated by the plant owner. If an alternative search unit is required due to pipirg gecmetry, etc., qualification of the alternative shall be per the direction of the plant owner. On piping 12.750" OD ard larger, consideration should be given to qualifying the largest size search unit passible to minimize radiation exposure. Care in selection of the focal length of dual element search units should be exercise:1. he focal point should fall as close as possible to the pipe ID to precltde crossing cuer beyond the focal point. When an examination requires a 1 1/2 vee path calibration focused dual element search units should not be used. 4.2.3 Wedges shall be used to produce shear mve team angles of 45 degrees, + 3 deg. - 3 deg., as determined using the IIW-2 ultrasonic calibration block. Se distance I frcrn the index point of the wedge to the front erd of the vedge should be short enough to permit 1/2 node examination of the near side of the weld root fusion zone without placing the transducer on Se weld reinforcement. Where a 1/2 node examination cannot be
- performed, wedges producing shear wave beam angles up to 70* + 3* may be used or a DAC may be constructed to allow for 1-1/2 vee path examination. .
4.2.4 Couplants. Glycerine, ultra gel - II or Hercules powder 7H and demineralized water shall be used. Alternate couplants require approval by BWRSD Materials Engireering. 4.3 Calibration Blocks (' 4.3.1 Field Examinations: The primary calibration blocks shall be those provided by the plant owner ard shall meet the requirenents of ASME tion XI. GENERAL ELECTRIC
Procedure No. P.B. 83-1 Rcvisten No. O amos Page 5 of 20 ( lU S ayE=g;llll' 4.3.2 An !!W-2 ultrasonic calibration bicck shall be used during calibration to establish angle beam index ootnt and beam angle as required in paragraphs 4.4.6.1 and 4.4.6.2. 4.4 Equipment Calibration 4.4.1 Calibration shall include the complete ultrasonic examination system. Any change in search units, test shoes, (wedges), couplants, cables or ultrasonic instruments shall be cause for recalibration. 4.4.2 The calibration data shall be recorded and plotted for each calibration on the Calibration Data Sheet (Figure 1). These sheets shall be numbered in sequence with the Examination Data Sheets (Figure 2). 4.4.3 Instrument Calibration 4.4.3.1 Laboratory: At the beginning of each period of continuous use, (or every three months, whichever is less), the ultrasonic instrument shall be checked for amplitude linearity and amplitude control linearity per Paragraphs 4.4.4 and 4.4.5, respectively. 4.4.3.2 Field: After any transport of the instruments in any comercial carrier, the instruments shall be checked per Paragraphs 4.4.4 and 4.4.5, respectively. These checks shall also be repeated once each week for the duration of the field examination. 4.4.4 Amplitude Linearity Check An angle beam search unit shall be positioned on a block and signals obtained from two reflectors. The search unit position shall be adjusted to give an exact 2-to-1 ratio of amplitudes between the two. The gain control (sensitivity) shall be adjusted and the larger signal brought to 80 percent of full screen height (FSH), adjust position if necessary, maintaining the 2:1 signal ratio. Without moving the search unit, the gain control shall be adjusted to successively set the larger signal from 100 percent to 20 percent FSH in 10 percent increments.The smaller indication shall be read at each setting. The signal amplitude must be 50 percent of the larger amplitude within five percent of FSH. Instruments ( that do not meet this requirement shall not be used. The data shall be recorded on the calibration data sheet provided. GEN ER AL $ ELECTRIC
Procedure No. P.B. 83-1 r wp ' Revision No. O sammes Page 6 of 20 ( < '6E
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4.4.5 Amplitude Control Linearity Check. The angle beam search unit shall be positioned on a calibration block and a peaked signal amplitude obtained fra a hole. The indication shall be brought as near as possible to 80 percent FSH with the dB control. If necessary, the final adjustment to 80 percent FSH is made with the variable gain control. Using only the dB control, the dB changes indicate ( below shall be made and the resulting amplitude compared with the allowable anplitude limits. The resultant signal must fall within the amplitude limits as specified below. Instruments that do not meet these limits shall not be used. The procedure shall be repeated for the 40 percent and 20 percent FSH amplitudes and the data recorded on the calibration data sheet. Initial Amplitude dB Control Amplitude Limits Set of % FSH Change % FSH 80 -6 32 to 48 80 -12 16 to 24 40 +6 64 to 96 20 +12 64 to 96 4.4.6 Beam Angle Determination 4.4.6.1 Determination of Angle Beam Index. The angle beam search unit is positioned on the 11W-2 calibration block so the beam is directed toward the four-inch radius surface. Move the search unit parallel to the sides of the calibration block until a maximum echo is obtained from the reflecting radius. The beam index point is now above the center line of the radius. Place a mark on the side of the angle beam wedge to identify the index point. 4.4.6.2 Determination of Beam Angle. Place the angle beam search unit on the IIW-2 calibration block and obtain a peak signal amplitude from the two-inch diameter hole. Read the refracted beam angle from the side of the calibration block using the angle which corresponds with the beam index point and record it on the Calibration Data Sheet. 4.4.7 Sweep Range Calibration The calibration block shall be used to calibrate the ultrasonic instrument search unit combination for sweep range over the metal path to be used. ( GENER AL h ELECTRIC
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"" Procedure No. P.B. 83-1
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'"7.'E.'.*MTO 4.4.8 Recalibration, Sweep Only If any indication of the DAC curve has noved on the sweep line more than five percent of the sweep division reading, correct the sweep l range calibration and note the correction en the Calibration Data l Sheet. If recordable reflectors are noted on the examination data sheets, those data sheets shall be voided and &stroyed. A new calibration shall be na& ard recorded, aM the voided examination areas shall te re-examined.
4.4.9 Recalibration, Amplitude Only If the amplitude cn the DAC curve has changed by nere than 20 percent of its amplitude when a check is made on the calibration standard, all data sheets since the last positive calibration check shall be marked void and destroyed. A new calibration shall be mde and recorded and the vaided examination areas shall be re-examined. 4.4.10 Verification of 2X Scannino Sensitivity The dB switches required to obtain the scanning sensitivity shall be detemined using the calibration standards. A reflected signal frcm one of the side-drilled calibration holes shall be detected and the amplitude adjusted to a level between 30 percent ard 40 percent of Full Screen Height. Using the dB switches, increase the signal amplitude to twice the sensitivity level amplitude ard record the setting change required. This dB change shall be used to obtain the
- minimum scanning sensitivity.
4.4.11 Scanning Rate The manual scanning rate for angle team scanning shall be sufficiently sicw to allow careful observation of the ultrasonic instrument screen and shall not exceed six inches per second of search unit novement. l 4.4.12 Calibration shall te performed at the beginning of each series of examinations on the calibration block applicable to the systen(s) being examined. A calibration verification shall be made at the end t of each series of examinations ard at intervals not exceeding four tours daring the examinations. 4.4.13 A curve representing 20 percent of the DAC level shall be marked on
- the display screen durirg calibration to aid in the determination of
( indication amplitude. GEN ER AL h ELECTRIC
Procedure No. P.B. 83-1
- Revision No. 1 Page 8 of 20 sannosh
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4.5. Surface Preparation 4.5.1 The base material scanning surface shall be free of weld spatter and any other condition that would interfere with free novement of the search unit or impair coupling of ultrasonic vibrations to and from the material being examined. Unacceptable surface conditions shall be reported to the customer. 4.5.2 Surface preparation and cleaning operations are not within the scope of this procedure. 5.0 CALIBRATION AND EXAMINATION 5.1 0 Degree Base Material Sensitivity Calibration 5.1.1 Position the search unit on the applicable Plant Owner's calibration standard and obtain a back reflection. Adjust the peak signal amplitude to 75 or 80 percent of the Full Screen Height and mark the position on the display screen. This point represents primary reference level for the base material examination. Record this calibration data on the Calibration i Data Sheet. 5.2 0 Degree Base Material Examination 5.2.1 Scan the volume of base material through which the angle beam examination will be performed to detect reflectors that could interfere with the performance or the results of the angle beam examination. This examination is not intended to be used for acceptance or rejection of piping welds. 5.3 Angle Beam (45 Degree) Sensitivity and DAC Calibration 5.3.1 Position the search unit on the appitcable Plant Owner's calibration standard and obtain the first point on the DAC curve using a sound sath no less than 3/8 of the full skip distance.* Adjust tw peak signal amplitude to 75 or 80 percent of the full screen height and mark its position and amplitude on the display screen. Without changing the gain level, obtain the peak signal amplitude for the next two metal paths of the sound beam. Mark their position and amplitudes on the display screen. Signal responses for metal paths less than 3/8 of the full skip distance may ba obtained by determining the 2/8 node response (off scale) to determine the shape of the DAC curve. Join the points with a smooth line, the length of which shall cover the examination range. This DAC line ( GEN ER AL $ ELECTRIC
k Procedure No. P.B. 83-1 Revision No. 3 om ,, Page 9 of 20 ( <w;
- ( "$2NCLW when adjusted for acoustic sIuivalency, represents the primary reference level (IX Sensitivity) for the angle beam examination. Record this calibration data on the Calibration
- Data Sheet. This calibration shall be perforned using reflectors parallel ard transverse to the weld seam as applicable to the examinations to be perforned.
- Vee path ard skip distance are considered sluivalent terns.
5.3.1.1 The 1/2 ncdal and, if required, the 1-1/2 ncdal point locations for the pipe to be examined shall be determined off the calibration standard notches or corners. Their locaticn(s) shall te rrarked on the screen and on the calibration sheet. Their location shall be narked on the screen ard on the calibration sheet. 5.3.2 Acoustic Euuivalency 5.3.2.1 The calibration block shall be checked as follows for use in cmparisons with the plant pipirs for acoustic i equivalency: a) With the instnment at the primary instruirent gain established in 5.3.1, set instrument for pitcV catch operation. b) Attach two 45 degree single elenent search units to the instrument T/R jacks. c) Couple the transnitting search unit to the calibration standard. d) Manipulate the receiving search unit on the cali-bration stardard to obtain a traxinun (% FSH) CRP indication frcan the received signal. e) Record tha dB change required to brirq the artplitude of the signal to approxinately 80% ESH. 5.4 Angle Beam Exa:rdnation 5.4.1 Establishing Prifrary Reference level 5.4.1.1 The primary reference level shall be adjusted to provide aroustic equivalency between plant piping and the calibration stardard as follows: a) Perform the operations outlined in 5.3.2.1 (a) ard (b) GENER AL h ELECTRIC
-A Procedure No. P.B. 83-1
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' Revision No. I Page 10 of 20 assmas t-( lO
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b) Set the instrument gain to the level established in 5.3.2.1 (e). In three equally spaced (120 degree) locations on the pipe weld perform the operations outlined in 5.3.2.1 (c) and (d). c) Detemine average dB increase or decrease necessary to attain approximately 80 percent FSH. Record this dB difference on the ultrasonic examination data fom and increase or decrease the instrument gain established in paragraph 5.3.1 by this amount. d) These steps (a)-(c) must be perfomed for each weld examined. Care must be exercised to insure that the instrument is returned to primary instrument gain prior to perfoming these steps. 5.4.2 Scanning Sensitivity Level The scanning shall be perfomed at a gain setting equal to or greater than twice the primary reference level . At the scanning level, the operator should be able to distinguish reflectors from the I.D. root geometry, increasing the gain beyond 2X may be required to accomplish this. 5.4.3 Recording Sensitivity Level Indications shall be recorded at the primary reference level (1x). l 5.4.4 Scanning for Reflectors Oriented Parallel to the Weld The search unit shall be placed on the contcct surface with the beam aimed about 90 degrees to the weld and manipulated laterally and longitudinally so that the ultrasonic beam passes through 2T minimum of base material from the edge of the weld. In addition, the search unit shall be angulated 0 degrees (perpendicu-lar to the weld) through 45 degrees to the right and lef t of the nomal (perpendicular to the weld) scan. See Figure 4. This examination shall be perfomed from both sides of the weld dere component geometry l pemits. ( l l GENER AL h ELECTRIC
Proceduro No. P.B. f.3-1 samnce Revision No. 3 ! Page 11 of 20 l k%
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5.4.5 Scannino for Reflectors Oriented Transverse to the )
'"M %'.'0 00"l" Weld l On Irepared or sufficiently smooth surfaces the angle l bean unit shall be aimed parallel to the longitudinal centerline of the weld with the search unit contacting the weld surface. The search unit shall be mcred along the weld so that the sound beam passes through all the wald metal ard weld HAZ on both sides of the weld where practical. Scanning shall be cbne in two directions 180 degrees to each other. In addition, the search unit shall be angulated frcm 0 degrees (parallel to the weld through 45 degrees, ained at the weld) on both sides of the weld for parallel scanning.
(See Figure 4). 5.4.6 Specific Area of Interest Angle beam irdications of intergranular stress corrosion cracking (if present) will be evident at the 4/8 node or 1/2 " Vee path" netal path distance. 6.0 DATA REDRDItG 6.1 0 Decree Base Material Indications 6.1.1 Record on tM data sheet all areas of base material which exhibit a total loss of back reflection. In aCition, record all areas where intermediate reflector (s) with signal amplitudes eugal to or greater than the renaining back reflection appear. If rurerous overlapping irdications of lesser amplitudes exist sich in the opinion of the Level II might prevent a meaningful sheer wave examination they shall be cbcurented. 6.2 Anole Beam Indications 6.2.1 All angle team indications in the HA2 or base naterial in excess of 20 parcent of the primary referenm level DAC shall be recorded on the Examination Data SMets, Figure 2. Irdications observed on the CRT, which eninate at the root (I.D. sarface) and travel along the sweep toward the O.D. shall be investigated regardless of amplituck. Irdications irdica-tive of IGSOC shall be recorded. 6.3 Reference Positions for Physical Measurements 6.3.1 Wo shall be the wald's centerline and shall be used for reasuring transducer novecents perperdicular to the weld. See Figure 3. ( 6.4 Selectino the Incation of In Reference Point (if not previously trarked) GENER AL h ELECTRIC
Procedure No. P.B. 83-1 Revision No. 1 mamash Page 12 of 20 ( l%T
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6.4.1 Piping Within Containment On horizontal pipe. Lo reference shall be an axial line or point at the pipe top dead center. On vertical pipe, lo reference shall be an axial line or point on the pipe circumference farthest fra the reactor pressure vessel. 6.4.2 Piping Outside Containment On horizontal pipe, to reference shall be an axial line or point at the pipe top dead center. When possible, on vertical pipe, the LO reference shall be selected by drawing an imaginary line down fra the outermost radius of the next highest elevation elbow. When no elbows are in sight, the LO reference shall be an imaginary line on the pipe 180 degrees from the neares': wall or obstruction. 6.4.3 Pipe welds with indications my be stamped with low t stress Y stamp. The V stamp shall be placed on the circumferential weld centerline. The top of the Y shall be LO (for circumferential welds) and shall point in the direction from which measurements are made. For longitudinal piping welds, lo shall be the pipe circumferential weld centerline. 6.5 Method of Recording Examination Data 6.5.1 Figure 3 sketches the relationship between transducer 1 weld center movements (positions W , (Wo), weld reference point Loi4(, y)a,nd location and length of indications (L1 and L2 ). This attachment also contains a sample copy of an Examination Data Sheet. Hypothetical information l based on the above sketch has been recorded on it. 6.5.2 Search unit positions W1 and W2 shall be recorded only when the wall thickness of the pipe exceeds one
- inch. Signals caused by geometric changes such as weld crown, mismatch, fitup ID preparations, etc.,
shall require recording of %, W , the peak signal amplitude, and the length of the indication in inches or degrees azimuth.
. 6.5.3 The following " transducer positions" and " data to be
( recorded "information shall be recorded on the Examination Data Sheets for indications which exceed 20 percent DAC at the primary reference level (1x). GENER AL $ ELECTRIC
Procedure No. P.B. 83-1 sannes Revision 0 Pag? 13 of 20 l c ~>
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Transducer Positions Data to be Recorded (a) W1 - Distance between the (1) Distance from referenced search unit index point and centerline (WO I* the weld centerline (Wo) when the signal amplitude (2) Indicated metal path to decreases to 20 percent DAC when moving towards reflector distance (MP)). the weld from Wm . (1) Distance from reference centerline (WO I* (b) W, - Distance between the search unit index point and (2) Indicated metal path to the weld centerline (Wo) reflector distance (MPs ). when the signal amplitude is at maximum. (3) Signal aplitude in 1 DAC at Primary Reference Level . (c) W2 - Distance between the (1) Distance from reference search unit index point and centerline (WO I'
, the weld centerline (Wo) when the signal amplitude decreases to 20 percent DAC (2) Indic:ted metal path of when moving away from the reflector distance (MP2 )*
weld and Wm - 6.5.3.1 The transducer positions L 1 and L2 , correspond to the 20 percent DAC length end points of an indication. The end points of the indication at 50 percent DAC shall also be noted on the d>ta sheet. 6.5.4 When indications other than geometric have been identified within the fusion zone, the heat affected zone or the base material, the transducer's positions should be recorded as follows: 1) The transducer's movement for each data point is perpendicular to the 7ength dimension. 2) The data shall be l obtained at 1/4-inch intervals along the length of the reflector for indications less than 2 inches in length. In addition, the maximiss amplitude points shall be checked at 1/4-inch intervals. 3) For indications greater than 2 inches in length, the data shall be taken at 1-inch intervals. 4) The l continuity of indications between intervals shall be l confirmed. i( GEN ER AL h ELECTRIC
Procedure No. P.B. 83-1 : Revision No. 2 l
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** y o g 7.0 REVIEW OF DATA 7.1 The recorded data shall be reviewed by an individual certified to at least Level II to determine if additional examination and/or evaluation is required.
7.2 Evaluation of Indications Disposition and evaluation of indications shall be as specified in the contr;ct. 7.2.1 Geometric plots of all recordable indications shall te made to show location of the indications with respect to tha weld root and weld heat affected zone (HAZ). 7.2.2 To assist in preparation of geometric plots, the responsible individual shall assure that thickness measurements, where required, are available. 7.2.3 Indications that appear to originate from a geometric condition shall be plotted to determine their origin. 7.2.4 When geometric plotting appears to be inconclusive or plotted data appears to result in a condition that may not be correct, such as a reflector that appears to emanate from the far (opposite) side of the weld root, the Level III may elect to evaluate the indication based on signal behavior. Some characteristics of IGSCC signal behavior are: A) IGSCC indications will originate at or near the sweep position corresponding to the component ID. B) IGSCC indications will walk (travel on the CRT) from ID toward OD. C) When the search unit is angulated (per Figure 4) whfie the indication is peaked, a geometric indication will decrease l in amplitude rapidly with a variation in incident angle. t An indication caused by IGSCC tends to decrease in
^
amplitude slowly and become more broad based as the search unit is angulated. D) At times, an indication will separate from an IGSCC indication, as the search unit is moved toward the indication, and walk toward the OD. This indication, when it appears, is indicative of a crack tip and is associated with indications of IGSCC. ( GEN ER AL $ ELECTRIC
Procedure No. P.B. 83-1 [k Revision No. 2 Page 15 of 20 _ J L_ c .
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These characteristics of IGSCC indications should be checked at or near the middle of the indication. If the i indication is short (less than 3 times the width of the search unit) it will be necessary to move the search unit to an end of the indication before angulation is performed (Step C). 7.2.5 Indications determined not to be from geometric reflectors shall be evaluated as follows: 7.2.5.1 0 degree base material indications shall be evaluated to ensure that no interference to the angle beam examination exists. l 7.2.5.2 Indications which appear to be from IGSCC shall be i reported to the Plant Owner within 24 hours of evaluation. The Owner shall supply disposition of the indication. 7.2.5.3 Indications shall be reported to the Owner for disposition if the amplitude exceeds the reference level, and discontinuities have lengths dich exceed: (1) 1/4 inch fra t up to 3/4 inch, inclusive (2) 1/3t for t from 3/4 inch to 2-1/4 inch, inclusive (3) 3/4 inch for t over 2-1/4 inch where t is the thickness of the weld being examined; if a weld joins two members having different thicknesses at the weld, t is the thinner of these two thicknesses. L GEN ER AL $ ELECTRIC
Procedura K). P.B. 83-1 Revision PC. 2 sammes Page 16 of 20 avaness ( 'w, PIPE ITP CALIBRATION DATA SREEr Tab",,'g* SITE
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l lPreoperational l l I.S.I. SYST94 CALIBRATION BID 3 9 m i w iiRB 10. REV. CALIBRATION SHEEP i DAE CDUPIANT IIW-2 BID 3 $ EXAKINER ASNT EVEL DATA TAKER ASNT IEVIL DEIR'J EN! KDEL PC. DEIRMNr SERIAL $ CAB E .. . CAB 2 TfIE CAB 2 I22 CHI TRA?EDUOR DATA SEDE TYPE STRAIGfr APGLE BEAM BEAM SEDE AIG2 SERIAL 10. IDENTITY LODE PRS 20DCf SIZE (DUPLANr REFI2CKR ORIENTED (PARALLEL & 'DWFJUGE) TO WELD SFJM (Cross Out Ore) DAC CURVE CAL STD TD(P 90 D6IRMNT SETTDGS: 80 l Start Finish Urcalibrated Gain 70 Coarse S g Fine Swwp 60 Coarse Range Fine Range 50 S a nning Gain Attenuation (in) 40 Evaluating Gain Attenuation (in) 30 - Pilter Position Rep Rate 20 Dacping Reject 10 Acoustic apiivalency (Para. 5.3.2) ( 0 1 2 3 4 5 6 7 8 9 10 0 1 2 3 4 5 GENER AL $ ELECTRIC
. : 4
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Proc. P.B. 83-1 mmm.. Rev. 2
"""% Page 17 of 20 f- <w2 m:=::* l Bole Depth . Gain Max "W" D or MF SCH Initial Calibration Time j "T" Inches 91X Acp. Irrh Inch or FE Periodic Checks: Iast 1X Time Value Data Sheet 1/4 1/2 IX 3/4 1X 24I.0 1X lbtch 240.0 1X Final Check:
lbtch Calltration in Dept.(D) [ or Metal Path (!@) O Applitude Idnearity Check Control Linearity (Made Daily) (Made Daily) 100% FSH USH 50 WSH tFSH 80tFSH -64 (32-48) 90% 40% " 80%FSH -12 4 (16-24) 80% 30% *
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Procedure No. P.B. 83-1
* ' ' Revision No. 2 samnes Page 18 cf 20
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( ' ("a ULTRASONIC EXAMINATION DATA FORM Exam Form Cal. Form No. Site O Preoperational O l.s.i.oaio System Weld No. Weld Type _ _ . . . Examiner ASNT Level . _ _ ._ Data Taker _. ASNT Level _ Scarch Angie U.T. Ps ocedure Rev. __ Scan Sens: X2 Other Evaluation Sens: X1 ._. Couplant Comp.Te mp. EXAMINATIONS: Performed Indication Yes No Angle beam for reflectors parallel to weld Yes No _ 1.
- 2. Angle beam for reflectors transverse to weld (dockwise and counter clockwise)
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( Page 20 of 20 , Tests ~ {&3' - Saw as -
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ttachment 1 I)ocket No. $0-277 Exhibit 2 . May 23, 1983 semca "m "weaiGt 51 1 I I IM PIPE UT CALIBRATION DATA SHEET
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SYSTEM T.\4.7. 50 c TIO w CALIBRATION BLOCK NO. 33 A PROCEDUp W A3-l REV. 4 CALIBRATION SHEET NO. 2- /cCO DATE 5 -A3 @0 PLANT Ut.-re.MEL IIW-2 BLOCK NO. 790339 EXAMINER I. D 6.cXt. R- ASNT LEVEL M DATA TAKER l . R ' C. L R 'I.R ASNT LEVEL h
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CABLE NO. C-I5 CABLE TYPE BNC le MC b CABLE LENGTH (o Y ISO ' TRANSDUCER DATA SHOE TYPE Lu c.1r e STRAIGHT BN ANGLE BEM SHOE NO. $\ SERI AL NO. YA B 7.7. 3 0 7 IDENTITY "/A CnA P4M A SilOE ANGLE (oO FREQUENCY N/A 1. 5 M4 s SIZE N/A 5 MODE $ N( N2-PARALLEL COUPLANT LX,TM Gn f L Of REFLECTORS ORIENTED TO WELD SEAM (Cross Out One)
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'd 1 Attachm:nt 1 Docket No. 50-277 Exhibi 3 May 23, 1983 ,
PROCEDURE FOR SIZING NON CEOMETRIC INDICATIONS 1.) Thickness readings and surface contours are taken on all welds at a minimum of three locations around the circumference. Additional thicknesses and contours are taken as required. See Figure 1. 2.) Metal paths W1s W'W2 M are taken, where: W1 = Minimum metal path at 20% DAC.
~
Wg = Metal path at maximum amplitude W2 = Maximum metal path at 20% DAC. 3.) Cross sectional plots are constructed using the appropriate surface contours and thicknesees. 4.) The shear wave refracted angle is determined from the calibration standard of the same material, diameter and thickness as the weld being examined. 5.) The ultrasonic data is then applied to the cross sectional plots and the maximum thru wall depth of the indication is measured directly. This technique has proven to be the most conservative, ie, provides the deepest thru wall dimension of an indication. The crack tip method using the formula: d = (Wg - W1 ) cos 0 has been shown to provide depths 10 to 20 percent less than the method described herein.
UDC 610.179.16: 620.194: 611.365.5.01J: 621.039.536.14 Attachment 1 Docket No. 50-277 Exhibit it May 23, 1983
, '. Effects Brought by Induction Heating Stress improvement 01-1S1)
Measures on Ultrasonic Signals Reflected from intergranular Stress Corrosion Cracks (IGSCC) Saburo Sidbata's Iliroshi Yoneyama'l Shinji Tanaka'8 Moritaka Kishigami'l alTected zone on both sides of the welded joint, of
!. Introtluction various depths and widths cut by EDM, as specified in
.he research efforts directed in recent years toward Table 1. The other specimen was provided artificially
.mnbating Stress Corrosion Cracking (SCC) have re- with IGSCC which was produced in multitude by the
.ulted in the development of a number of materials technique known as " Creviced Pipe Test" in high
- c>istant to SCC and of techniques to provide against temperature pure water 44)(Fig.1). The resulting IGSCC M*C. which have come to be practically applied to was distributed as shown in Fig.1.
.r.:..e.ir boiling water reactor (BWR) plants"). Induction 2.2 Experimental apparatus fe.nmg Stress . improvement (IHSI)(W3) is one such The ultrasonic apparatus used for the experiment
..nmque that is receiving particular attention both in i.u'an and in other countries, as an efTective counter- ,,,,,,,,,,
O e.nure, against-SCC for BWR-whether in the con- NS 3 W N~ek
. intetson stage or:already in operation. The aim of IHS!
p t,iimprove.the state of residual stress due to welding, /*** through reduction.of' the. tensile component of the / c,.m.u . Suual stresslichte to occasion SCC-or further - wu.:h its conversion into compressive component. On the other hand,in view of the current practice of f ' S{-{ 7 ~ utilizing ultrasonic methods of flaw detection for in-service inspection of. equipment and piping in DWR c
"~ "
./ h[* ' ~
s plants. it is essential to know in advance whether the liiSI treatment applied to such components should
.itfect in any way the ultrasonic' properties of the material . .,
- s. : treated, and if so, what the effects would be. /,*;"_
The present study covers a comparison made of the r- -
~
results of ultrasonic tests applied before and after IHSI ~/ treatment to specimen pipes carrying notches introduced ~ <=. hy Electric Discharge Machining (EDM) and artificially Fig. 1 SCC testing apparatus created Intergranular Stress Corrosion Cracking ilGSCC). A discussion is also given cocerning the deter-mination of defect size by ultrasonic testing. ' _..,s m.,,,,, ,
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- 3. Experimental apparatus and test specisnens
. _ - , _ , - - . _ m .- . - - ~
21 hpecimens used in experiment e=cu> >>
~'u'.u '+"' M -3" The specimens used in the experiment were prepared
' rom 12 inch Sch 100 type 304 stainless steel pipe each . . _ _ . . . _ - _m -
.arrying a butt joint made by conventional automatic '#CC ' '1WC#
viding. Two such specimens were produced, one of smth eine was provided with 12 notches in the heat- y,,. _ .-m._ ,, stet.6Hure liep; rtment. Itcscarch institute - , I " 'inWf mc TJ m m nirainin .3. Development Department.
...i ,,
. i . .cr liis nion Fig. 2 Produced SCC distribuuon S
M M'*% N Ttbla f EDM netch c nfigurttians HAZ No. Al Anmuth ang!c t i A2 0 45 93 135 180 225 270 315 25
= 115 205 295 L tmmt 5 10 20 it'emmt 0.2(, 0.27 0.26 0.33 0.26 0.27 0.30 0.J2 0.26 0.27 O tmme 0.25 0.3 0.43 1.55 3.95 7.90 0.48 1.55 4 95 7.90 0.48 1.55 3.95 7.9 41 9
U
-l ]
i ^ j; q . . _ - _ . j , consisted of: 3.4 Transducer positions for defect measurement and Search unit USIP ll method of ultrasonic testing Transducer .t5 shear wase angle. 2.25 MHz. The defect echo height, as well as the length and depth 12.7 mm diameter Couplant of the defect, were measured using the same transducer Glycerine positions. For deriving the Distance. A mplit ude Correction (1) Defect e.ho height (DAC) curve and for adjusting the working sensitivity level, the reference block i!!ustrated in Tie. J was cut out For the specimen provided with notches (Table 1), the echo height was measured with the transducer from the same material as the specimen. set at the position where it registered maximum
- 3. Method of experiment echo heicht before IHSI. For the IGSCC specimen, 3.1 Preparation of examination surface the measurements were made along the pipe periph.
The external surface of the pipe joint was fmished cry at mtervals of 10 mm (135 positions in all), in smooth so as not to affect the performance of ultrasonic view of the almost uniform distribution of the search. This was done by simple grinding in the case of IGSCC over the entire circumference on both sides of the joint. the specimen notched by EDMt in the case of the other specimen provided with IGSCC, the surface was ma-chined, for the reason that it presented a prominent (2) Length of defect The defect length was measured on both speu-g weld reinforcement. mens by the method prescribed in the ASME 3.2 Experimental procedure Loiler & Pressure Vessel Code Sec. V, using both the criteria of echo height exceeding 1/2 max. and The two specimens were subjected to ultrasonic search , exceeding 50% DAC. before and after lHSi treatment, as schematized in (3) Depth of defect Fig. 4. The pairs of search before and after IHSt were The defect depth was measured by the same made by the same examiner, to climinate any differences due to personal tendencies. method as above, supplemented with additional measurements by the Flaw Tip Echo Method 3.3 Discrimination .etween echoes from defects and illustrated in Fig. J. In this measurement the from root bead surface configuration transducer was located in the same position as for The echoes from the artificial defects (EDM notches. the echo height measurement (see (1) above). IGSCC) were discriminated from those retlectine back ' from the root bead surface by wave pattern identifica. 4. Experimental results and discussion tion. or else by touching with a finger the root bend 4.1 Effects brought by IllSI on echo height surface of specimen at the zone of wave impingement, The echo heights obtained from corresponding measure-which produced a change in echo height in tne case of root bead surface retlection. ments before and after IHSI are correlated in Fig. 6, where the diagonal line represents unchanged echo M b- .c 'Y DMW_= % t.r M . UT h 1
/ \ /
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o 1, s., t 5 No. 4 October 1983
~
, . . ."ight between the two measurements. Extremely little machining of specimen surface applied to remove the gunge due to IHSI is noted for the measurements on asperities on the examir.ation surface. The standard mnhanically applied notch. An equal performance has deviation shown by the plots are, as shown in Table 2, not been obtained for the IGSCC specimen, despite the 1.2 dB for the mechanically notched and 2.7 dB for the l , IGSCC specimen. The poorer stability of measurements g
- i. ~
~
obtained on the IGSCC specimen can be attributed to l l . . the complex configuration of the cracks, which fork into many brar.ches, as evidenced in the photomicrograph of e, _ b a sectioned specimen shown in Fig. 9 as compared with the neat notches that are obtained by EDM. Even the value of 2.7 dB standard deviation obtained k on the IGSCC specimen, however, is already within the i range of scattering normally obtained on similar meas-urements by ultrasonic testing, considering that the
- estimated reliability of flaw detection by ultrasonic testing is said to ensure reproducibility only within
- d2.7 dB standard deviation when counting solely the i
r differences in tendency shown between persons, and if all factors are included, the standard deviation will further increase to 6.7 dBm. The values in Tab /c 2
< - nt,-a ,u.. . given under the column designated i represent the
- mean differences between the measurements before and i m ,
,f after IHSI, i.e. the shift in measured values produced 7 .,$ by the IHSI. A very slight shift is discernible for the case of IGSCC specimen. Corbly et al(8). have reported
[ 7'- - - '- b that the height of defect echo can vary with stress WC applied to the region of crack, and that cracks with tig. 5 Sche natic illustration of the Tip Echo Method for closed gap tend to transmit ultrasonic waves, resulting SCC sizing I ca* csce
* ~
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a : a< n : 4 s r...<> ,..3 Fig. 6 Echo height Table 2 Seatistical daea , EDM notch SCC n e i n e i Echo Height (dB) 12 1.17 0.63 135 2.70 , 1.68 li2 n m . 12 0.39 0.32 44 3.59 - 0.86 Flaw length _
""*' 50!; DAC 11 1.39 0.23 47 5.20 - 0.76 t/2 mas. 12 0.81 - 0.07 51 0.57 0.15
'*d*[ 50!; D AC 11 0.15 0.03 37 0.72 0.06 n.14 Tip echo 10 0 49 0.19 23 0.5 R 8 %te t er Numnct et wrnr'ie r: Standard deu.mn
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l { in lowering of the echo height. This would indicate the Now, if IHS! had brought any physical change to a possibility of echo height being influenced by IHS! defect, both length and depth should have increased, or treatment, since the intensity of residual stress is modified else both decreased: The fact that the data given in by this treatment"1--amounting at times to conversion Table 1 indicate inverse directions of change for these from tensile to compressive stress around a crack. two dimensions would deny the existence of any con. The foregoing results of the present experiment, how-sistent causal relation between IHS! and ultrasonic data, ever, would indicate that such influence of IHSI treat-and the scattering of the measured values should more ment on the ultrasonic property of the material, if any, reasonably be attributed to normal measurement errors. should be negligibly small, from the fact that extremely 4.3 Dimensioning of defect depth small change of echo height was registered for the in what precedes we have found that IHS! treatment specimen with EDh1 notch, and that for both speci-produces no significant shift on the ultrasonic properties mens the values obtained for i have been found to be of the material. Some considerations are presented very small compared to the corresponding values of a.
; below on the relative merits of different methods of 4.2 Effects brought by IHS1 on defect dimensioning defect dimensioning.
Plots similar to those of Fig. 6 are presented in figs. 7
; The data in Table J include those obtained from and 3 respectively for flaw length and depth, to compare Flaw Tip Echo Alethod, as well as from the AShtE the nicasurements obtained before and after IHSI. As technique: Compared with the actual measurements in the case of echo height, an appreciably higher scatter-ing of plots is observed for the specimen with IGSCC, made by microscopic observation, appreciably undefr 3 as compared with that of EDh1 notch. But again, the estimated values are noted for the results obtained wid' the ASNfE technique (both by 1/2 max. and 50% DAC relation of very small I compared with a is indicated in criteria), whereas the Flaw Tip Echo hiethod is seen to Tsjh/c .'. where the negatisc values of I signify a shift ~
give values nearer the direct visual measurements by el crack dimension to the larger side, and rice tersa. microscopy on sectioned specimens. An exampic of the 4
, 'vd 15 N3. 4 October 1982
.This 3 Camparison d flaw h:ight measurement
*f.,.,;. , . - ;,
O... by UT cnd deseructiva assay (unitt mm) .O . ., je N: ,/
~t . ,, ' * ' ')j EDM (post IHSil SCC (post lHSI) *
[e s .. ..l .(., . *. , j;p-w ual 50'; l/2 Tip Actual 50*; il2 Tip -
~
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. . ' j ... ,A , .. - -- t j - . ,
o 43 0.5 2.4 1.5 2.45 1.4 2.0 g .. 2.1 . L. .O. , p,;.A.[ y , 1.55 3.0 1.9 0.9 3.J7 0.3 1.7 3.3 y 1 :, 's v,e . w . .
- d. 1# " m1- . ,' ,7 C ?g~*
aM 4.95 3.i 1.6 3.2 J.So I.8 2.2 3.8 -
- -a
'.90 3.2 2.3 6.6 3.81 0.8 I.7 2.7 V - # t
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. . - ..~..;.
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otomicrographs obtained on sectioned sample for ,, g . _- (,' ,1 7 i tal crack measurement is presented in Fig. 9, which .'.;f .1 ,, M M*g. t
- als a crack configuration very similar to those 3,Q ;,(0,
- terved in IGSCC detected in BWR plants. b ~ .' '
Jt: t u.Re?- . . . - -
.i . s. f
. Conclusion a6
~o.
t, ss
't 4 r.
. ,. p.e .- , .. ; ,,g'l.3,
. I 'g2y S M^R . . ,
- rasonic measurements were applied to two speci. . J,] , v 5 d
ers of welded joint artificially provided with defects t ,___ 9 . . 9" m:,fi means of EDM and IGSCC, these measurements N. - W
- r . ".7*
.M 7$r.'h eing performed on the same position before and after -
k- wr ;- .U
.151, with a view to determining the existence of any 7' N A < %. 5 QD.* '.<j s.nsistent shift in ultrasonic properties due to the IHSI -b 'M g Y-
- Q3 'l .: i
.eatment. The results obtained from this experiment -
.J h -
., -'c,'5 i [\ f i;'c . /n sovided that:
il) in respect of echo height, the effect of IHSI is j .. i
\[.'. ~g
> J$-
S gN V'
.T; ,q ,
- s. , -
negligible, and the deviations of measurement are .
.., p . s .
g.k-}9%.l'"~M
- 3,.
attributable to normal measurement errors. (2) The results of defect dimensioning (crack length and depth), while varying to some extent with the . ,,,,,,,,,, h method of measurement, denied in all cases the esistence of any consistent causal relation between Fig. 9 Produced SCC and microstructure of sample l IHS! and ultrasonic data. l 131 For evaluating crack depth, the Fisw Tip Echo tion Heating. EPRI-NP-814-LD (Prepared by Ishi-Alethod was found to be effective, from comparison kawajima Harima Heavy Industries Co., Ltd.) 1981 i mth actual measurements made by microscopic (4) Nondestructive Evaluation Program: Progress l observation on sectioned cracks. in 1979, EPRI NP-1234-SR Special Report Dec. l , 1979: T. Kawamoto: Production of Controlled REFERENCES IGSCC in large Diameter Pipe, PR 1488-7 l ali Proceedings: Seminar on Countermeasures for (5) Investigation of NDE Reliability and Fracture l hpe Cracking in BWRs EPRI WS 79174 Vol. I- Mechanics, Phase I Report NUREG/CR-1696 4 1980 1980 t2) T. Umemoto and S. Tanaka: Residual Stress (6) D. M. Corbly, P. F. Pacman and H. S. Pearson: Improvement by Means of Induction Heating IH1 The Accuracy and Precision of Ultrasonic Shear Engineering Review Vol.11 No. 4 Oct. 1978 Wave Flaw Measurements as a Function of Stress rp.11-20 on the Flaw, Mat. Eval. 28 1970 131 Residual Stress improvement by Means ofInduc.
Attachment 1 ' Docket No. 50-277 Fi 6ure 1 lby 23, 1983 g Peach 30tto:2 Unit #2 RIIR Suction; ' Pipe to Elbow Weld: 10-0-6 k tig 20
. " diameter Assume 64" circutzference b
Graphie Plot of the location and thru-wall depth of all ultrasonic indications, assumed to be ciacks.
., Ps es s ' oe T=.T E & ,o .3S .%' a h\\\%\\\ \M\\\\\\\\\\
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J 0 GU G8 DOCKET NUMUEll EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES h l0l2] lDuring a forced outage on Unit 2, while performing a special inspection,( l0j3j l an indication was found in the heat af fected zone of a 20" RIIR shutdown l 10141 I cooling suction line weld. Indications were found in both the pipe and l Indications were circumferential in pipe and l 10151 l elbow side of the weld. 101c 1 t elbow. A'similar event is referenced in Ler 3-83-12/lT. ; I 1.2.L1J l l OE COOg S DC OE COMPONENT CODE SUS O'E SU lOI9l lC l Fl@ LxJ@ LzJ@ (P l Il Pl E I xl X '@ . Ej@ J i a e iQ in 12 :a a e ao RE R 005 N EVENT YEAR LE H I 0111 11 M 10111 [TJ [ -j lol
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May 23, 1993 Docket No. 50-277 ATTACHMENT TII PEACH BOTTOM UNIT 2 INSTALLED MAY 1983 Moisture Detection Systems
System Description
The system utilizes a moisture sensitive tape that was developed in 1957, patented in 1969 and has been marketed since 1991 by Techmark Limited. The system has a digital display / control unit which uses a multiplex sensor scanning technique. The moisture censitive tape consists of a membrane construction containing two layers of polimide film (one with a 0.5 square inch hole) sandwiching a chloride -f ree salt impregnated web. The sensitivity of this tape is such that a few drops of water or the presence of saturated steam will activate the tape. The digital display / control unit which is located in the reactor building outside the primary containment contains a digital sensor identification display and green, red and yellow LED's to indicate system operation, detection of l eak, and system troubles, respectively. There are 10~nensors installed on 6 recirculation risers and 4 PHR shutdown cooling suction line welds. The welds with the moisture sensitive tape installed.are welds, 2-AHK-2, 2-AHJ-2, 2-AHH-2, 2-BHE-2, 2-BHD-2, 2-BHC-2, 10-0-3, 10-0-5, 10-0-6 and 10-0-7. These welds in Unit 2 were chosen for tape installation because similar welds in Unit 3 had been found with cracks durina Unit 3 refueling outage. (See attached sketch.) Leak detection annunciation is provided in the main control room with visual indications at the display / control unit in the reactor building. Surveillance Procedure The operating staff will check the functions of the display / control unit once per shift. The control room alarm will be checked concurrently.
Page 2 Action Requirements The *ollowing actions are reouired for leak indications or monitoring system failures. In the event that the alarm is received in the control room:
- 1. The control room operator (ACO or CO) shall check the Drywell sump flow recorders for any increase in pump-out frequency and check on the status of the Drywell radiation monitor trouble alarm (indicates alarm at the local panel).
- 2. The control room operator (ACO or CO) shall I dispatch a qualified floor man to check the moisture monitor local display / control unit immediately.
- a. If the " Red" Led is lit, the floor operator
, should reset it. Tf it relights, call the i Unit 2 Assistant Control Operator (ACO) or the Control Operator (CO) immediately. If it does not relight (if there is moisture on the tape, the red light should come back on in about 6 seconds), wait for 5 more minutes and then report results to the Unit 2 ACO or the CO. The qualified floor man should also check the drywell radiation monitor recorder charts at the local panel for any increased activity (this panel is located at 135' elev. in the reactor building). I
- b. If the "Yallow" Led is lit, the floor operator j should attempt to reset it. If it relights, shift supervision is to be notified.
1
- 3. If the indication of leakage appears to be valid, l shift supervision is to be notified and the unit is to be shutdown in an orderly manner. The Unit should be in hot shutdown condition in 12 hours and in the cold shutdown condition in the next 24 hours. Shift supervision will inform the duty senior staff engineer. The NRC must be contacted via the RED PHONE within one hour; an open line is not required.
- 4. If the moisture monitoring system is found to be inoperable, shift supervision shall initiate an
Page 3 hourly monitoring of the Drywell sump operation to detect any increase in pump-out frequency and an hourly incpection of the Drywell radiation monitor recordern to detect any increase in Drywell airborne activity, until the moisture monitoring system can be returned to service. The duty senior staff engineer should be notified as soon as possible. The NRC should also notified promptly via normal reporting channels. Bases The water sensitive tape is being used to alarm leakage from piping within the pressure boundary. To be consistent with Standard Technical Specifications, NUREG-0123, Revision 3, if leakage is known and located to be pressure boundary leakage, the reactor will be shutdown to allow further investigation and corrective action. Duration of Need # This Moisture Detection System (moisture sensitive tape) shall only be in-servi'ce until start of October, 1993, refueling outage on Unit 2. l
, ATTACHMEIPR III. DOCKET NO. 50-277 MAY 23, 1983 I I ON LINE _Li i l LEAK DETECTION i
~-
SYSTEM r l-FOR NUCLEAR & FOSSIL FIRED GENERATING PLANTS Early warning of small steam leaks Continuous on line monitoring of piping integrity Precise location of leak announced by visual and audible alarm Reduces radiation exposure of personnel Can be installed during scheduled outages Production capacity to meet the most demanding schedules 15 years experience in Leak Detection ( l TECHMARK LIMITED Yacht Haven,326 First Street, Annapolis, MD 21403 Telephone: 301-263-6600 Tele >c 87-424 l l 1 _ _ _ _ _ _ _ _
4
+ ON LINE LEAK DETECTION SYSTEM +
The Techmark Leak Detection System is designed to 180*F. The present temperature limit of the tape is relay the status of leak detection sensors to a central over 300*F. control location. The exact method of signal transmission When a small area of the web bete een the two depends upon the chosen system: two wires or multiplex. conductors is moistened by water or saturated steam, the The System as originally designed by Nutec, has been sensing element experiences a drastic change of electrical further developed by Techmark to utilize the latest modular, resistance. The high-purity water normally encountered in solid state construction, designed and constructed to power plants has a resistivity in the megohm range, so the meet the most stringent requirements. A wide range of water itself would not provide this change in resistance of control functions are available. the sensor. However, the web is impregnated during 7he moisture sensitive tape was developed originally to manufacture with chloride free chemicals whictt wtlen cc,ntinuously monitor possible leaks from valves, flanges activated by water, become electrically conductive. The and pumps, etc in a heavy water reactor system. Dunng sensing element maintains a low resistance as long as the the years since its development the need for a simple, moisture remains When the moisture evaporates and the reliable and inexpensive system for the early detection and web becomes dry, the resistance returns to its original locating of small leaks has escalated, high value. THE TECHMARK LEAK DETECTION SYSTEM provides A few drops of water will activate the tape. 5atu EARLY WARNING AND SPECIFIC LOCATION or the leak. rated steam has the same effect. Operation of the The present utilization of humidity, sump level and radiation system is independent of water quality, since the con-monitoring provide only the information that a leak has ductivity factor is established by impregnants in the occurred somewhere. tape. Borated water will activate the tapejust as well in a nuclear plant, the ability to precisely locate a leak as pure water, during cperation minimizes the time and exposure to Upon reaching the moisture sensitive tape the steam radiatio iin taking corrective action. The Techmark System will condense and activate the tape; the display / control provides the operator information that currently is senses this change and triggers the alarm. not a./ailable. The System consists of a sensing element that provides SENSOR CARRIER an electrical signal when activated by moisture, and an ir'dicating device which converts the electrical signal from in order to provide an unrestricted path for the steam to the sensor to a visual and/or audible signal. The display / reach the moisture sensitive membrane, a 0.5" diameter control alerts the plant cperator to the presence of hole is dalled through the insulation to the annulus moisture in a specific loca'. ion. between the steam pipe and the insulation. The sensor carrier consists of a stainless steel tube welded to a plate approximately3.0" x 3.5",and a fast disconnect connector. MOISTURE SENSITIVE TAPE The sembpermeable membrane is adhered to the plate with the non-permeat'le side exposed to ambient and the The moisture sensitive tape is a semi-permeable mem- hole centered over the tube. This insures that only steam brane permitting steam or moisture to enter from the pipe, moisture from the pipe will reach the membrane's while prohibiting moisture entry from ambient. impregnated web. The membrane construction is two layers of polimide When used with the TUM System, the transponder is an film l one with 0.5 sq in. hole) sandwiching a chloride free integral part of the assembly. salt impregnated web. Pnor to assembly two silver con-ductors are applied to the impregnated web. Thermo- DISPLAY CONTROLS SYSTEMS setting adhesive bonds the layers as well as the membrane to mounting surface. The original Nutec System required four (4) wires per The moisture sensitive tape i'; applied on the exterior of sensor to be returned to the Display Control Panel. With the thermalinsulation The tape is mounted on a stainless the rising costs of field wiring and few penetrations steel plate for ease of installation and to ensure an available; Techmark developed three new Display Controls impervious seal to ambient conditions The tape is therefore - TM 1008 (hard wired) (two w!res per sensor) and the near the skin temperature of the insulation - 150*F- TUM 100 and the TUM 700 multiplex system.
I TM 100B-TWO WIRES / SENSOR System allows the installation of up to 700 Leak Detection CHANNEL-HARD WIRED Sensors or locations utilizing only 4 conductors. A digital display provides the exact location of the sensor which is in G:neral: alarm or trouble. Techmark's TM 1008 is a solid state control receiver Redundancy is achieved with the TUM 700 by returning which receives and displays alarms from the moisture 4 conductors to the display / control. Even if all conductors sensitive tape. The System continuously supervises all were severed at a particular location, there is no loss of wires leading to the sensors as well as the sensors larm or trouble cono; tion from subsequent sensors. themselves Provisions to control remote functions are System
Description:
available to suit indwidual requirements A. Display / Control: Two models are available-TUM System
Description:
100 (capacity 99 sensor zones) and TUM 700 (capacity The System consists of multiple, two channel circuit 700 sensor zones). cards Each channel can have one or more sensors 1. Digital LED display of sensor location for A! ARM connected by a pair of unshielded wires with a resistor or TROUBLE. placed at the end of each sensor channel to supervise not
- 2. Multiple alarms are displayed in ascending order and only the wires, but the sensors themselves Each channel has indrvidual LED indicators, which are latched in memory until manually eliminated.
provides the operator with quick and positive identifica- 3. All sensor zones are interrogated every 1.5 seconds tiort The indications are as follows. Alarm condition must be sensed in two consecutive sweeps before display. Self Test Alarm 4. RED LED - Indicates leak. Green Red 5. GREEN LED - Flashing indicates system logic System Status LED LED functioning. Normal Steady Out 6. YELLOW LED - Activated in the event of any Leak Alarm Steady Flashing system trouble. Channel Fault-Sensor Out Out 7. Additional YELLOW LEDS are activated in the event ' Channel Fault-Wiring Out Out of Battery Trouble, Ground Fault or Disconnect (any Sensor Dry (After Alarm) Steady Steady (Until Reset) function out of normal operations). When a channel is in alarm, the alarm red LED will flash 8. Controls-SYSTEM TEST and an audible signal will sound. The LED will continue to flash while the sensor is wet. When the red LED is steady, ALARM RELAY CVERRIDE TROUBLE SILENCE indicating the sensor is dry, the channel is ready to be SYSTEM RESET reset. This is accomplished by depressing the toggle switch to the lowest position (Reset),and then placing the ACKNOWLEDGE switch to the upper position l Normal). The channel is now 9. Operating Voltage 120 VAC. No other external ready to receive another alarm. power is required for system operation. A manual test switch is included for each two channel circuit card which checks the ability of the display / control B. Wiring Required: 4 Conductor- 18 Gauge Shielded to receive an annunciate the sensor status. By depressing the switch the red LEDs will show alarm (Flashing), the C. Transducer: For each sensor zone or location a transducer is required. The transducers and sensors are green LEDs will be steady and the audible alarm will sound. Once the operator is satisfied with the results, wired in series , both channels shou;d be reset. D. Redundancy: By returning the 4 conductor,18 The TM 100B is dasigned with provisions for multiples gauge shielded wire to the TUM 700 Display / Control, of two channel circuit cards mounted into standard sensors are monitored in both the clockwise and 19" racks counter clockwise direction in the event of a line break Power requirement is 120 VAC. or other trouble. This feature is not available on the TUM 100. TECHMARK/ TIME DISTANCE MUTIPI.EX DETECTION SYSTEM (TUM) E. Options: Battery Standby General: Remote Digital Display Techmark introduces a unique multiplex system utilizing Computer or Printer Interface DC interrogation of sensor status, based on the time-distance principle, rather than AC discrete address. This F. Qualification: Environmental Qualification only design is less susceptible to spunous alarms The TUM supplied for TUM 700.
BACKGROUND monitoring feedwater and main steam (90 welds per plant) since 1978. The moisture sensitive tape was developed in 1957 by The ability of the tape to dry out after being wet was ACF. The tape was installed on sma!I test reactors demonstrated at Pennsylvania Power and Light's Martins including Georgia Tech., M.I.T., ispril, and R-2 Test Creek Plant in a three month demonstration in 1980. Reactor (Sweden). The tape was patented in 1969, and Demonstration of the Techmark Leak Detection System manufactured by Allis Chalmers and Nutec Inc in 1981, was conducted for the EPRI BWR owners group at the Techmark Limited purchased Nutec Inc non-destructive test center in Charlotte on June 15,1981. Testing and evaluation of the Nutec system began in A contract has been awarded to Action Environmental 1957 at the ACF Nuclear Products Erco Lab. Testing has Testing Corporation to environmentally qualify the TUM been conducted at the University of Maryland, M.I.T., 700 Techmark Leak Detection System using IEEE 323-74 Brookhaven Combustion Engineering and Detroit Edisort and Nureg 0S88 as program guides. A demonstration of sensitivity to small leaks was given to observers from the N.R.C. and the Power industry at CLIENTS Acton Environmental Testing Corporation on March 1,1982. Dairyland Power, Commonwealth Edison, Brookhaven National Laboratory, Detroit Edison, NUS (Antartica), CLIENTS - TUM MULTIPLEX Misubishi, Sumitomo, RWE (Germany), Viginia Electric and Power ( l 80 locations), Pennsylvania Power and Light Tennessee Valley Authority Browns Ferry 2. Installed 2/83. (test), and Argonne National Laboratories. The installation at Virginia Electric and Power's North Vermont Yankee Nuclear Pt Ner Corporation: Sensors Anna Units 1 and 2 Steam Plants has been in service shipped 3/83. 1 _t i __L ! __L d_ TECHMARK
+L1MiTED-Yacht Haven 326 First Street. Annapolis, MD 21403 Telephone: 301-263-6600 Teler 87-424 I
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ATTACHMENT IV Docket No. 50-277 Philadel phia El ectric Company Peach Bottom Atomic Power Station Responses to Questions Addressed In May 20, 1993 Meeting between Philadelphia Electric Company and Nuclear Regulatory Commission Technical Staff Question: (1) What procedures were used to measure through wall depth of cracks?
Response
Procedure for sizing non-geometric indications is as follows:
- 1. Thickness readings and surface contours are taken on all welds at a minimum of three locations arouond the circumference. Additional thicknesses and contours are taken as required. See Fiqure 1.
- 2. Metal paths W1, WM; W2 are taken, where
W1 = Minimum metal path at 20% DAC. WM = Metal path at maximum amplitude W2 = Maximum metal path at 20% DAC.
- 3. Cross sectional plots are constructed using the appropriate surface contours and thicknesses.
- 4. The shear wave refracted anale is determined from the calibration standard of the same material, diameter and thickness as the weld being examined.
- 5. The ultrasonic data is then anplied to the cross sectional plots and the maximum thru wall depth of the
- indication is measured directly.
Page 2 This technioue has proven to be the most conservative, i.e., provides the deepest thru wall dimension of an indication. The crack tip method using the formula: d= (WM - WI) cos 0 has been shown to provide depths 10 to 20 percent less than the method described herein. Question: (2) Does the code permit averaging of varying crack depth measurements to arrive at a uniform depth for analysis purposes? Where is this documented?
Response
The code procedures characterizing long (approaching 360 degrees) circumferential cracks with local variations in depth are unclear. However, the allowable flaw sizes in Apendix X, Section XI, are based on a limit load treatment of the cracked section which is strongly dependent upon the cracked area rather than the local maximum depth. Therefore, the use of an average depth based on the crack area is consistent with the technical basis for Appendix X. Question: (3) By what procedure was the 0.3 inch " Average" flow depth determined: What is the error bank?
Response
The assumed crack depth of 0.3 inches represented a reasonable but conservative measure of the average depth. i This depth was exceeded only at two isolated locations of 2 in ches (depth 0.4 inch) and 3 inches (depth 0.35 inch) out of a total circumference of 64 inches. In fact, the crack depth was 0.2 inches or less over 57% of the circumference.
i l . . 1 e i Page 3 Question: (4) This weld was-stated to have a SRI of 2.95. This is very high, and appears to be inconsistent with the stress ratio of 7 0.8 weld in the code calculations for allowable crack depth.
- How were these values determined? Can they be shown to be 3
inconsistent with each other?
Response
f The stress rule index considers pressure, sustained thermal
- ~
expansion, and residual stresses. It also includes the effects of local discontinuities and stress concentrations. On the other hand, the stress ratio numbers, (Pm + Pb)/Sm, used in determining the allowable flaw sizes consider only the primary loads across the whole section. Such loads are pressure, dead weight, and seismic. Thus, there is no inconsistency between the higher SRI and the assumed (Pm + Pb)/Sm stress ratio. Question
! (5) What are the loads and stresses in this joint during
-emergency and faulted conditions including SSE?
Response
The highest calculated OBE stress in the RHR supply line is i given in the stress report as 2050 PSI. Therefore, the maximum SSE stress would be expected to be no greater than 2 x 2050 or 4100 PSI. The primary stress for emergency / faulted conditions are expected to be less than 14 KSI. However, the allowable flaws were calculated on the basis of the-normal / upset condition loads because they were more limiting than those considering the emergency / faulted loads. i Question: (6) Provide the details of crack growth rate estimate. What are the crack growth rates used in the calculations of the remaining operating life? e f
Page 4 i
Response
The IGSCC crack growth rate was based on a conservative i estimate of the sustained stresses. The sustained stresses l consist of pressure (axial), weight, and thermal-expansion
! stresses and the residual stress. In order to make a conservative estimate.of the crack growth rate, the residual stress, which is compressive in the mid-thickness region in a large-diameter pipe, was not considered in the evaluation.
The sustained stresses at the weld 10-0-06 were determined to be approximately 13 KSI. The calculated crack growth is , shown on the flaw acceptence diagram shown in Figure 2. Additional information relative to this question has been provided directly to the NRC staff and will be submitted formally as soon as hard copy is available. Question:
~
4 (7) Provide details of calculations that show the allowable crack l denth of 58% of the wall.
Response
, The allowable circumferential crack depth is based on the-I stress ratio, (Pm + Pb)/Sm. The (Pm + Pb)/Sm term consists of pressure, weight and OBE (inertia) stress terms. These were determined to be approximately 11 KSI at the weld 10 ,
- 06. With Sm = 16.8 KSI @ 550 degrees F, this gives a stress ratio of approximately 0.7. Per Table IWB-3641-1, Section i XI, the acceptable depth as a fraction of thickness for a j fully circumferential flow is 0.58 when (PM + Pb)/Sm is 0.7.
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May 23, 1993 Docket No. 50-277 ATTACHMENT V INTERIM SURVEILLANCE AND LIMITING CONDITION OF OPERATION FOR PEACH BOTTOM-ATOMIC POWER STATION, UNIT 2 THROUGH OCTOBER 1983 Attached are the interim proposed surveillance and limiting conditions for operation regarding coolant leakage to be incorporated into the Peach Bottom technical specifications to support Peach Bottom Unit 2 operation through October 1993. These interim measures are required to support continued power operation of Unit 2 with a crack at weld No. 10-0-6 on the non-isolable 20" RHR shutdown cooling suction line. The interim limiting conditions for operation reflect those contained in the Standard Technical Specifications (NUREG 0123, Rev. 3) with the following exception. The rate of change of 2 gpm per 24 hour surveillance period is applicable only when the reactor mode switch is in the RUN position. Standard Technical Specifications apply this LCO to reactor operations in the RUN, STARTUP or HOT SHUTDOWN mode. During reactor operations in the startup mode, large variations in primary coolant system pressure result in changes'of measured leakage not indicative of , system degradation. This rate of change criteria, if applied during STARTUP operations , could preclude reactor power operation since the LCO for the rate of change of unidentified leakage would most likely be exceeded, resulting in unit shutdown. The maximum leak rate of 5 gallons per minute during the limited duration of the startup phase will assure primary coolant system
- j integrity during this time period.
1 To monitor and alarm pressure boundary leakage, a moisture detection system, consisting of water sensitive tape, has been applied to ten susceptible welds in the RHR shutdown cooling suction line and vertical recirculation system risers. To be consistent with the Standard Technical Specifications (NUREG 0123, Rev. 3) if leakage is known and located to be pressure boundary leakage, the reactor will be shutdown to allow further investigation and corrective action. This system will remain in service as an interim additional leak detection system through October 1093. l
_2_ To determine coolant leakage monitoring systems operable, the current Peach Bottom Technical Specifications (see Table 4.2.E of PBAPS Tech Specs) will remain in ef fect. This includes the Equipment Drain Sump Flow Rate Monitor, Floor Drain Sump Flow Rate Monitor, and Primary Containment Air Sampling System. These systems are all demonstrated operable in the following manner at the stated frequency:
- functional test once per month
- instrument check once per day calibration once per 3 months t
INTERIM SURVETLLANCE AND LIMTTING CONDITION OF OPERATION FOR PEACH BOTTOM ATOMIC POWER STATION, UNTT 2 THROUGH OCTOBER 1983 LIMTTING CONDITIONS FOR OPERATION SURVETLLANCE REQUIREMENTS 3.A.C. Coolant Leakage 4.6.C Coolant Leakage
- 1. Any time irradiated fuel is 1. Reactor coolant system leakage in the reactor vessel and reactor shall be determined by the coolant temperature is above sump or air sampling system 212 degrees F, the rate of and recorded every 4 hours reactor coolant leakage to the or less.
primary containment from unidenti-fied sources shall not exceed 5 gallons per minute. The rate of change of unidentified leakage shall not exceed 2 gallons per minute per 24 hour surveillance period when the reactor is operated in the "Run" mode. In addition, the total reactor coolant system leakage into the primary contain-ment shall not exceed 25 gpm averaged over any 24 hour surveillance period.
- 2. Upon receipt of valid alarm from 2. The function of the moisture the moisture monitoring system, monitoring system display and the unit shall be placed in HOT control unit will be checked shutdown within 12 hours and be once per shift, in COLD shutdown within the next 24 hours.
- 3. If the moisture monitoring system is found to be inoperable, an hourly monitoring of the Drywell sump operation to detect an increase in pump-out rate and an houriv inspection of the Drywell radiation monitor recorders to detect an increase in Drywell airborne activity will be initiated until the moisture monitoring system can be returned to service. The NRC will be notified promptly in accordance with Technical Specification 6.9.2 (Prompt
-146-
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INTERIM SURVEILLANCE AND LIMITING CONDITION OF OPERATION FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT 2
.THROUGH OCTOBER 1983 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS Notification with Written Followup) From and after the the date that_the moisture monitoring system is made or -
- found to be inoperable for any reason, reactor power' operation is permissible only during the succeeding seven days unless the system is made operable sooner.
i 4. Both the sump and air sampling systems shall be operable during reactor power oneration. From
- and after the date that one of
! these systems is made or found to be inoperable for any reason, reactor power'oneration is permissible only during the succeeding seven days unless the ' system is made operable sooner. l
- 5. If the conditions in 1, 3, or 4
' cannot be met, an orderly shutdown shall be initiated and the reactor shall be in Cold Shutdown Condition within
, 24 hours, i
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