ML20039B263

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Forwards Manual Ultrasonic Exam Procedures for Reactor Pressure Vessel,Circumferential & Longitudinal Welds, Revision 2, & Ultrasonic Exam Procedures for Reactor Vessel to Flange Weld & Stud Ligaments,Revision 1
ML20039B263
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 12/09/1981
From: James Smith
LONG ISLAND LIGHTING CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20039B264 List:
References
NUDOCS 8112220470
Download: ML20039B263 (2)
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SHOREHAM NUCLEAR POWER STATION

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P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 Decernber 9, 1981 j

0) i[Q GCE!VED Mr. Harold R.

Denton, Director

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Office of Nuclear Reactor Regulation

-l DEC 211981* :._

Light Water Reactors, Branch 4 N ts uca r.aumn'2 b U.S. Nuclear Regulatory Comm;ission Washington, D.C.

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Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Denton:

Enclosed, please find ten (10) copies each of the following revisions to the Preservice Inspectico Program.

8)A0462, Rev. 2 80A0471 Rev. 0 80A0468, Rev. 1 80A0480, Rev. 2 l

80A0475, Rev. 4 80A4437, Rev. 0 80A0481, Rev. 6 These documents are furnished to comply with LILCO's response.

No. 1 to NRC request 121.16.

Please acknowledge receipt of the documencs by aigning and returning the enclosed document trans-mittal control form.

Very truly yours, Q 6< g ru( (r/

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Smith Maneger Special Projects 3007 Shoreham Nuclear Power Station AP/mp Enclosures

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December 10, 1981 Mr. H.

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Denton, Direc to'.

Preservice Inspection Program Plan Transmittal Shoreham Nuclear Power Station - Unit 1 W.

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44430/48923 As holder of a controlled copy of the PS1 Program Flan Manual, you will receive all revisions to the Manual as they are issued.

At-tached you will find instructions for inserting the en.losed docu-ments in the PSI Program Plan Manual.

The instructions wil! also serve as a checklist to assure thac you have received all the re-quired material.

ENCLOSURE (S) :

Please acknowledge receipt of these documents by signing and dating this transmittal n the space provided below.

Return the completed transmittal form to:

Mr.

A. Peters, Staff Assistant Long Island Lighting Company Shoreham Nuclear Power Station P.O.

Box 618, North Country Road Wading River, New York 11792 Attachnent & Enclosure cc:

Eng. File /SR2...SHI-397 Signed Date 5

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80A0462

Subject:

RPV-SUPS-1 Issue Date:

June 10, 10 1 _

Revision I!o. : 2 Date: 8/ 31 /8?

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~- Procedure No. : 80A0462

Subject:

RPV SNPS 1 Issue Date: June 10.,198 Revisien No.:,2; Date: 8/31/81 Page 2 cf 34 _ RECORD OF REVISIO:IS Frz. ion 37 _ J2:!Aer Date Descrittien Reason O g inator S&W

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12/8/75 Add issue date to .. efine o r ' ai - J. J. Lance J. Lance al1 pages ' ia l issue date Bl. Har-bins r $6 4L. Change 25 to 930 Scanner arm J. J. Lance y/ onWefdEL55g length reduced to 25 to 104 from 57" to A '. #- 30" Change 1770 to 245 on Weld EL 553 to 1660 to 245 Change 293 to 335 on Weld EL 553 to 282 to 335 Change 47 to 93 on Veld EL 403 to 36 to 104 Add 128 to 142 on Weld EL 403 Change 177 to 2320 on Weld EL 403 to 1660 to 2320 Add 256 to 262o on Weld EL 403 0 Change 297 to 324C x 4 eld El 403 to.?d to 3480 e e O fJUCLEAR ENERGY SERVICES, INC.

Proce ~tu e No.: 80A0462

Subject:

Rpy _ sups 1 Issu2 Date: June 10. 1975 Revision No.: 2 Date: C/ 31/ 81, Page 3 of 34 RECORD OF REVISIO.IS Revision AI/ Number Date Description Reesen Originator S&W liES 0 to 1270 I hont) Change 47 on Weld EL 253 to 36 to 1270 Change 177 to 2460 on Weld EL 25' to 1660 to 2460 Change 2970 to 001C on Weld EL 253 to 2860 to 0120 2 8/31/ Para. 1.1.7 added To accocro- ~ [f-81 note date parallel 1,gf cove 9 age of NI'# Revised paragraph' the flange 2.1 l(2) to shell weld Revised paragraph - 2.1.1(3) Revised paragraph 2.1.l(5) g Revised paragraph 2.3 Revised paragraph 4.1.l(A) Revised paragraph 4.1.l(B) Para. 5.2.l(B) Added For the...is required Revised para. 5.3.1 0 NUCLEAR ENERGY SERVICES, INC. O

NUCLEAR ENERGY SERVICES. INC. PAGE 4 OF 34 .fo ' DATE DESCRIPTION APPROVAL 2 S/3'/81 Para. 5.7.2 added For the...is recuired I tj 8 l Revised para. 6.1.l(8) Fevised para. 6.1.l(9) Revised para. 6.1.l(101 Revised Figure 1 Added note to Figures 10 - 13 Revised Table 1 Refer to CRA 2087 I i l i l l 1 1 I l i l l l l l l l l l l l i l h l l l i i i f I i l l i l l l l l l l i \\ l l l 8 0 A V

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DOCUMENT NO. 80A0462 av 11 " _ NUCLEAR ENERGY SERVICES, INC. MANUAL ULTRASONIC EXAMINATION PROCEDURES FOR REACTOR PRESSURE VESSEL, CIRCUMFERENTIAL AND LONGITUDINAL WELDS

1. SCOPE 1.1 AREA OF EXAMin., TION This document covers the ultrasonic examination procedures for the reactor pressure vessel:

1. Circumferential welds - upper vessel shell (Ref. CE-E234-237) shown in Figure 1 2. Longitudinal welds - upper vessel shell (Ref. CE-E234-237 & CE-E234-234) shown in Figure 2 3. Circumferential weld - upper to lower vessel shell (Ref. CE-E234-242) shown in Figure 3 4. Longitudinal welds - lower shell (Ref. CE-E234 473 and CE-E234-234) shown in Figure 4 5. Circumferential weld - lower torus bottom head to dome (Ref. CE-E234-235) shown in Figure 3 6. Lcngitudinal welds - lower torus bottom head (Ref. CE-E234-235) shown in Figure 6 7. Sup;t t skirt to reactor pressure vessel weld (Ref. CE-E234-475) shown in Figure 7. Note: Refer to Procedure 80A0468 for perpendicular coverage of the shell h to flange weld. 1.2 TYPE OF EXAMINATION 1. Volumetric examination shall be performed using ultrasonic pulse echo angle beam and O straight beam techniques applied to the outside surfaces of the reactor pressure vessel and the support skirt. 2. The examination shall be performed using manual search units. FCR'/ :NES 25 2/80

DOCUMENT NO. 80A0462 my PAGE 6 Or 34 NUCLEAR EN6RGY SERVICES. INC. w. 1.3 TIME OF EXAMINATION These procedures shall govern the preoperational (baseline), inservice examination and reexamination of repaired areas of the reactor pressure vessel as required by the ASME Boiler and Pressure Vestel Code, Section XI. 1.4 WELD CONFIJ TION 1. The reactor pressure vesse! longitudinal and circumferential weld configurations are shown in Figures I thru 7. 2. Nominal weld thicknesses are: 3-7/S" Upper vessel shell 6-7/8" Lower vessel shell 6-13/16" Bottom head - lower torus & dome 7.0" max. - Support Skirt to react,r pressure vessel. 1.5 MATERIALS The reactor pressure vessel is constructed of low carbon steel with stainless steel cladding on the ID surfaces.

2. REFERENCES 2.1 REFERENCE DOCUMENTS The following documents form a part of this examination procedure:

1. ASME Boiler and Pressure Vessel Code, Section XI 1971 Edition throagh the Summer of 1972 Addenda 2. ASNT Recommended Practice, SNT-TC-1 A,1975 Edition h I 3. 30A9068; NES Procedure for Training and Certification of Nondestructive Examination Personnel (Latest Revision) 4. S&W Specification - SH1-397 ISI Program 3. Quality Assurance Plan 80A0448 FC='.9 c %ES 2C5 2.63

DOCUMENT NO. 80A0462 w GE 7 OF M NUCLEAR ENERGY SERVICES, INC. 2.2 APPLICABLE DRAWINGS The following drawings form a part of this procedure: 1. CE Drawing E-234-234 6. CE Drawing E-234-476 l 2. CE Drawing E-234-235 7. S&W FV-14E-2 3. CE Drawing E-234-237 S. S&W FV-14F-2 4. CE Drawing E-234-242 9. NES SOD 0412 5. CE Drawing E-234-473 10. CE Drawing E-234-475 2.3 OPERATIONAL MANUALS The equipment operational manuals for the particular ultrasonic inst uments k used form a part of this procedure.

3. PROCEDURE CERTIFICATION

} The examination procedures described in this document comply with Section XI of the ASME Boiler and Pressure Vesse! Code except where examination coverage is limited j by part geometry or access. The applicable code addendum is the Summer 1972 to the 1971 Edition.

4. PERSONNEL CERTIFICATION 4.1 PERSOB'NEL CERTIFICATION REQUIREMENTS 1.

Each person performing ultrasonic examination governed by thi procedure shall be certified in accordance with the following: A. ASNT Recommended Practice, SNT-TC-1 A,1975 Edition B. NES Docurnent 80A9068; Procedure for Training and Certificanen of Nondestructive Examination Personnel (Latest Revision) C. ASME Boiler and Pressure Vessel Code Section XI(1971 Edition). 2. At least one member of each crew shall have a minimum qualification Level H in accordance with the above referenced documents. The Level II shall be responsible for the performance of all the examinations and shall be present at all times during the examination. The remaining member shall have a minimum qualification of Level I or Level I Trainee. 4.2 PERSONNEL RECORDI 1. Records of personnel qualification shall be maintained by the Examination Contractor. FOW

  • Nr.ti 205 2/80

DOCUMENT NO. 80A0462 11 ~~ NUCLEAR ENERGY SERVICES. INC. 2. A copy of the examiner's certification and a current eye test (as required by SNT-TC-1 A) shall be fileo with each permanent examination record, with a copy submitted to the plant owner or hi: agent prior to performing examinations per this procedure.

5. EXAMINATION REQUIREMENTS 3.1 EX AMINATION FREQUENC7 1.

The neminal examination frequene es shall be 2.25 MHz for all straight beam and angle beam examinations. 2. During preoperational examination, other pulse fr:,uencies shall be used only if such variables as material attenuation, grain structure, etc., necessitates their use to achieve penetra tion or resolution. This mformation shall be recorded on the data sheets. 5.2 EXAMINATION ANGLES 1. Examination angles for the reactor pressure vessel longitudinal and circumferential welds shall be as follows: A. O straight beam from the unclad surface one direction through the weld and through all parent material at each side of the weld through which the angle beams will pass during angle beam examination. B. 45 angle beam two directions perpendicular to the weld axis and two directions parallel with the weld axis. For the circumferential snell /k to flange weld, only two directions } arallel with the weld axis is required. C. Other angle beams may :: used for evaluation of reflectors, if necessary for clarification, or when specified as additional requirements dictate. 1 2. Examination angles for the support skirt to reactor pressure vessel weld l are as follows: A. O straight beam through the support skirt and filler weld and including the heat affected zone in the reactor pressure vessel. B. 45 in two directions circumferentially and one direction longitudinally, directed toward the outside skirt to vessel junction. C. 60 in two directions circumfer entially and one direction longitudinally, directed toward the outside skirt to vessel junction. FCP.i t NES 2^5 2E

DOCUMENT NO. 80A046-PAGE 9 OF 34 NUCLEAR ENERGY SERV!CES. INC. 5.3 LIQUID COUPLANT 1. The ultrasonic t.ouplant shall be suitable for use on nuclear plant materials k and be cenified not to exceed 59 ppm ha! ogen and 200 ppm sulfur. 2. The couplant shall be supplied in clean contamers of sufficient quantity to facilitate the examination. I l 3. The couplant shall be applied manually with a brush or other suitable i device. 4. The examiner shall be responsible for verifying that the couplant has been removed from the examination surface at the conclusion of the examination. 3.4 SURFACE PREPARATION 1. All examination surfaces should be clean and free of dirt, weld spatter, etc., or any other condition that wou'd interfere with the examination or impair proper transmitsion cf the sound beam. 2. Irregularity of surface contour to be contacted by the search unit should not exceed 1/3" in any 2" of surface travel. Teld crown and edges should blend smoothly into adjacent base material. 5.5 TELD IDENTIFICATION Each weld shall be located and identified per the appropriate weld map. 5.6 DATUM POINT 1. The examiner shall verify that a reference datum point has been marked on each weld, from which all examination data and rcported indications shall be referenced. 2. The CE Weld Identification Plan for SNPS-1 shall be used as the reference for all examination datuer. points. 3. Each weld datum point, aiong with respective weld reference points and divisions, shall be shown on each examination report. 5.7 EXAMINATION COVERAGE - RPV CIRCUMFERENTIAL AND LONGITUDINAL I SHELL WELDS l. The intent of this procedure is to provide maximum examination coverage to insure weld integrity. Each weld shall be scanned with minimum 25% overlap o' the transducer width (diameter) for each scan pass. 2. Each w. 'd shcIl be ultrasonically examined where part geometry and access permit useg 45 angle beam techniques applied in two directions toward the weld an ' ir' two directions parallel with the weld, and on both sides of 4 /2 \\ this weld. Foi the circumferential shell to flange weid, only two directions parallel with weld axis is required. FCW c %ES 2;5 2!6;

DOCUMENT NO. 80A0462 = " NUCLEAR ENERGY SERVICES. INC, 3. Straight beam techniques shall be applied, where part geometry permits, to all parent material through which the angle beams will pass during angle beam examinations of the weld. Indications discovered that might affect the interpretations of angle beam results are to be recorded on the data sheet. In addition, straight beam techniques shall be applied to the cield surface where part geometry permits. Reportable indications will be recorded in accordance with Section 11 of this procedure. 4. Where the examination surface or other conditions (weld, contour, access, etc.) do not permit a meaningful ultrasonic examination to be performed, the examiner shall record the area of nonexamination and the particular interfering condition in the space provided on the Weld Scan Data Sheet. 5.8 EX AMINATION COVERAGE - RPV TO SKIRT WELD 1. The intent of this procedure is to provide maximum examination coverage to insure weld integrity. Each weld shall be scanned with minimum 25% overlap of the transducer width (diameter) for each scan pass. 2. The we!d shall be ultrasonically examined where part geometry and access permit using 45 angle beam techniques applied in two di ections circumferentially and one direction longitudinally directed toward the outside skirt to vessel junction. 3. The weld shall be ultrasonically examined where part geometry and access permit using 60 angle beam techniques applied in two directions circumferentially and one direction longitudinally directed toward the outside skirt to vessel junction. 4 The weld shall be J1trasonically examined using straight beam techniquu through the skirt material, weld, and heat affected zones. The examination shall be performed in accordance with Section 10.1 of this procedure.

6. EQUIPMENT REQUIREMENTS 6.1 EX AMINATION CONTRACTOR'S EQUIPMENT The following test equipment or its equivalent shall be provided by the Examination Contractor for examination of the reactor pressure vessel welds:

1. Pulse Echo Ultrasonic Instrument 2. Scan Fixture,45,85Cl34 or 57A8407 (wedge) 3. Scan Fixture, O,85C157 4. Search Unit, 3/4" Dia., 2.25 M Hz, 57 A3135 5. Search Unit,1/2" x 1", 2.25 MHz,31225 6. Couplant FCRM # NES 205 2/80

DOCUMEf4T NO. _f.0A046 2 my 1 11 34 ' \\GE OF NUCLEAR ENERGY SERVICES. INC. 7. Scan Fixture,60,85C155 or 57AS417 (wedge) Note: RPV to skirt weld only S. Wedge,45 to accomodate search units 9. Search units,2.25 MHz angle beam of suitable size 10. Search units,1/2 ' through 1-1/2" dia,2.25 MHz, O. l 6.2 PLANT OWNER'S EQUIPMENT The plant owner or his agent shall provide the following service facilities and equipment as required: 1. Scaffolding 2. Water, air, and electricity 3. Temporary lighting 4. Crane or lif ting devices 5. 6" Reference Standard SNPS-1 6. 7-1/4" Reference Standard SNPS-1 7. Radiation monitoring equipment 8. Radiation shielding 9. Test surface preparation (cleaning and finishing) 10. Drawings of each examination area 11. Post-examinatien cleanup of test area.

7. CALIBRATION REQUIREMENTS 7.1 REFERENCE STANDARDS 1.

The reference standards designated in 6.2 (5) and (6) shall be used for basic instrument calibration and for establishing reference sensitivity levels for examination of the reactor pressure vessel. See Figure 8. 2. The appropriate reference standard corresponding to each respective weld thickness shall be recorded on each Calibration Data Sheet. Figure 10 is an example of the Calibration Data Sheet to be used with this procedure. 3. Calibration Data Shets shall be numbered 631-1, 631-2, 631-3, etc., at the time of calibration. 4. Calibration procedures shall be performed from the unclad surface of the reference standard. F O W 8:NES 205 2 80

DOCUMENT NO. 80A0462 PAGE 12 34 OF NUCLEAR ENERGY SERVICES. INC. 7.2 TRANSFER MECHANISM A one to one ratio between the reference standards and the examination areas shall be used. The effects of We clad surface of reference standards and the reactor pressure vessel on the reflected signal cannot be predicted, and thus a transfer mechanism for this examination wot.ld not be valid. The reference standards shall be acoustically similar material and therefore a transfer is nct required. 7.3 REFERENCE SENSITIVITY LEVEL 1. Reference sensitivity levels shall be initially calibrated directly on the reference standard and shall be the sensitivity levels used for evaluating and recording all indications. 2. During actual weld scanning, the reference sensitivity levels shall be increased 2X or 6 aB. 7.4 TIMES OF CALIBR ATION 1. Basic instrument calibration shall be performed using appropriate reference standards, search units and instrumentation immediately prior to the examination of reactor pressure vessel welds. 2. Basic instrument calibration shall be performed at the beginning of each day of examination in accordance with Section 8 of this procedure. 3. Calibration checks shall be performed at least at the beginning and at the completion of each 4 hour period of examination and/or at the change of examination personnel, equipment, search units, coupler shoes, etc., and at the completion of the examination of each similar series of welds in accordance with paragraphs 9.2 and 9.4 of this procedure. 7.5 CALIBRATION RESPONSE 1. Calibration response shall be checked at the primary reference sensitivity level. 2. Signal response obtained during calibration check shall be within plus or minus 20% of that established during basic instrument calibration. 3. If for any reason the sensitivity level must be increased due to improper response during calibration check, all welds examined since previous calibration must be reexamined at the corrected sensitivity level. 4. If for any reason the sensitivity level must be decreased.due to improper response during calibration check, all indications recorded since the previous calibration must be reevaluated at the corrected sensitivity level. FCRM # NES 205 2/80

DOCUMENT NO. 8CA0462 11 av NUCLEAR ENERGY SERVICES. INC. 7.6 VERIFICATION OF SEARCH UNIT ANGLES AND POINTS OF INCIDENCE Search Unit refracted angles and points of incidence shall be chec;:ed in accordance with paragraph 5.3 of the Quality Assurance Plan (Ref. 2.l(3)) at the start of each shift. If for any reason the angles or the points of incidence, have changed during the calibration check, all indications recorded since ine previous calibration must be reevaluated with corrected angles and points of incider ce.

8. INSTRUMENT CALIBRATION VERIFICATION

\\ 8.1 AMPLITUDE LINEARITY The linearity of the ultrasonic instrument shall be checked as follows: 1. Position an angle beam search unit on the reference standard so that indications from both the 1/2T and 3/4T holes are visible (other reflectors which provide the 2-to-1 ratio required in (2) may be substituted. 2. Manipulate search unit to establish a 2-to-1 ratic of amptitudes between the two indications with the largest at 80% full screen height (FSH). 3. Without moving search unit, adjust sensitivity to run the higher response from approximately 100% to 20% FSH in 2dB steps (10% if fine control available). 4. Read and record the relative amplitudes of the two indications to the nearest 1%. 5. If the smaller indication does not fan wishin 5% FSH of 50% of the larger indication, the instrument shall not be used for examinations until correctea. 8.2 AMPLITUDE CONTROL LINEARITY The linearity of the instrument gain (attenuation) control shall be checked as follows: 1. Position an angle beam search unit on the reference standard to obtain an 80% FSH indication from the 1/2T hole. 2. Using amplitude control, decrease signal amplitude by 6 dB and by 12 dB to obtain nominal 40% FSH and D% FSH signals. Read and record actual signal amplitudes to closest 1%. 3. Obtain a 40% FSH indication from the 1/2T hole and increase amplitude with the amplitude control by 6 dB to obtain a nominal 80% signal. Re.3 and record as in (2). + ro:V:NES 2:5 2 '8?

DOCUMENT NO. 80A0462

NUCLFAR ENERGY SERVICES. INC. 4. Obtain a 20% FSH indication from the 1/2T hole and increase amplitude with the cmplitude c:ntrol by 12 dB to obtain a nominal 80% FSH signal. Read and record as in '2). .5. If the indications obtained in (2), (3), and (4) are not within 20% of nominal, the instrument shall not be used for examination until corrected. i.3 HORIZONTAL LINEARITY The norizontal linearity is checked by verification that the points on the Distance Amplitudc Correction (DAC) curve are initially linear to 5% and have not shif ted on the sweep line through subsequent calibrations. If during the straight beam or angle beam calibmion checks, the DAC points have shif ted more than.5% of the sweep div.s.on reading, the sweep range sb:ll be recalibrated and a correction noted on the data shee's. If recordable reflectors have been noted on the data sheets, they shall be voided, a new calibratica recorded, and the examinations repeated.

9. CALIBRATION PROCEDURES 9.1 STRAIGHT BEAM CALIBRATION Sinight beam calibration shall be performed as follows and as shown in Figure 9.

The appropriate combinatiens of search unit, reference standard, and test holes for each respective weld are listed in Table 1. 1. Adjust the instrument sweep controls so that the signal response from the 1/4T and 3/4T holes occur at the 2nd and 6th horizonts! screen divisions as shown in Figure 9. 2. Position search unit to obtain maximum response from the hole which gives the highest araplitude signal. Adjust sensitivity control to provide a signal amplitude of 80% of FSH and mark location and amplitude on the CRT. 3. This is the primary reference sensitivity. Record all sensitivity control settings on the appropriate Calibration Data Sheet. 4 Without changing sensitivity, position the search unit res?:ctively on the remaining holes and mark signal amplitudes and locations on the CRT. 5. Plot a DAC curve by connecting the locations (marked on the CRT) with a continuous line extended to cover the full examination range (horizontal screen divisions 0 thr: 8) as shown in Figure 9. 6. Instrument is now calibrated for examination of welds of the thickness for which calibration was just performed. FC Y:NES 2 5 2 50

Amy DOCUMENT NO. 90Ao452 PAGE 15 _OF 34 NUCLEAR ENERGY SERVICES. INC. 7. Record all data and instrument settings on the Calibration Data Sheet, and rign upen completion. S. Repeat steps (1) thru (7) for each different weld thickness just prior to examination. 3.2 STRAIGHT BEAM CALIBRATION CHECK Straight beam calibration check as required by paragraph 7.4(3) shall be performed as follows: 1. Adjust the sensitivity control settings to those recorded for the. calibrated reference sensitivity. See paragraph 9.1.(2) 2. Reposition search unit at each respective test hole and observe maximum signal response amobtades. 3. See paragraph 7.5 for signal response requirements during calibration check. 9.3 ANGLE BEAM CALIBRATION Angle beam calibration shall be perfa med as follows and as shown in Figure 9. The appropriate combinations of search urit, reference standard, and test holes for each respective weld are listed in Table I. 1. Adjust the instrument sweep controls so that the signal response from the 1/4T and 3/4T holes occur at the 2nd and 6th horizontal screen divisions as shown in Figure 9. 2. Position search unit to obtain maximum response from the hole which gives the highest amplitude signal. Adjust sensitivity control to provide a signal amplitude caf 80% of FSH and mark location and amplitude on CRT. 3. This is the primary reference sensitivity. Record all sensitivity centrol settings on the appropriate Calibration Data Sheet. 4 Without changing sensi:viti, position search unit respectively on the remaining angle beam calibration holes and mark signal amplitudes and locations on CRT. 5. Plot a DAC curve by connecting the locations (marked on the CRT) with a continuous line extended to cover the full examination range (horizoncal screen divisions 0 thr" 8) as shown in Figure 9. 6. Instrument is now calibrated for examination of welds of the thickness for which calibration was just performed. FCW.'cNES 2 5 2:50

DOCUMENT NO. 80a0452 M NUCLEAR ENERGY SERVICES. INC. PAGE OF 7. Record all data and instrument settings on the Calibration Data Sheet, and sign upon completion. S. Repeat steps I through 7 for each different weld thickness just prior to examination. 9.4 ANGLE BEAM CALIBRATION CHECK Angle beam calibration check as required by paragraph 7.4(3) shall be performed as follows: 1. Adjust the sensitivity control settings to those recorded for the calibrated reference sensitivity. See paragraph 9.3(3) 2. Reposition search unit at each respective test hole and observe signal response amplitudes. 3. See paragraph 7.5 for signal response requirements during calibration Check.

10. EXAMINATION PROCEDURES 10.1 STRAIGHT BEAM EXAMINATION OF WELD AND HEAT ZONE 1.

Straight beam examination of the weld and heat affected zone shall be performed at a scanning sensitivity level 2X or 6 dB greater than the calibrated reference sensitivity level. 2. A rectilin-a Scan pattern 2nall be used allowing a minimum of 25% overlap of the transe.;cer width (diameter) fo, each scan pass. 3. Maximum scanning rate shall not exceed 6"/second. 4. See Table I and Figures 1 through 7 for scan path distances and sequences of weld examinations. 5. Continue scanning sequences until all we!ds have been examined. Equipment must not be removed from the wNd area until all indications have been ev-luated. 10.2 STU IGHT BEAM EXAMINATION OF BASE MATERIAL The base metal shall be examined in accordance with paragraph 10.1. 10.3 ANGLE BEAM EXAMINATlONS 1. All angle beam exa.ninations shall be performed at a scanning sensitivity level 2X or 6 dB greater than the calibrated reference sensitivity level. FORM:NES 205 2 50

DOCUMENT NO. 8030462 PAGE 17 OF 34 NUCLEAR ENERGY SERVICES. INC. 2. The search unit shall be swivelled as it is moved along a saw tooth scan pattern to ensure a minimum of 25% overlap of the transducer width (diame: r). 3. Maximum scanning rate shall not exceed 6"/second. 4. See Table I and Figures 1 through 7 for scan path distances and sequences of weld examinations. 5. Continue scanning sequences until all welds have been examined using angles and dircctions shown in Table I. Equipment must not be removed from weld area or disassembled until all indications have been evaluated. 6. All angle beam examinations shall be performed using 1/2 Vee path.

11. EVALUATION CRITERIA 1: 1 RECORDING OF INDICATIONS 1.

All indications that exceed 6 dB below DAC (50M of reference level) shall be recorded on the appropriate data mheet at the time of the weld examination and prior to removing equipment from the reactor pressure vessel. 2. Each recorded indication shall be identified as to depth, length, signal amplitude and locction relative to the weld datum point. A. Indications from all longitudinal welds shall be reported in inches above the weld datum point and in inches clockwise (CW) or counterclockwise (CCW) from the weld centerline when looking down upon the top of the reactor pressure vessel. B. Indications from all circumferential welds shall be repcrted in inches above or below the weld centerline and in inches CW or CCW from the weld datum point when looking down upon the top of the reactor pressure vessel. 11.2 EVALUATION OF INDICATIONS All recordable indications that exceed DAC or are interpreted to be cracks, lack of penetration, or lack of fusion, as per the requirements of the ASME Boiler and Pressure. Vessel Code, Section XI-IS-300, shall be reported to the client by the end of the shift. Results of this evaluation shall be reported to the Plant 0.mer or his Agent in accordance with the requirements of the ASME Boiler and Pressure Vessel Code, Section XI-IS-622.

C:1.M NES 205 :/8Q

DOCUMENT NO. 8 m 462 PAGE 18 OF 34 NUCLEAR ENERGY SERVICES, INC. i

12. EXAMINATION RECORDS 12.1 CERTIFICATION OF RECORDS The examiner shall complete and sign the appropriate Weld Scan Data Sheet (s) immediately upon the completion of each weld examination.

12.2 FILING OF RECORDS 1. The examiner shall be responsible for submitting to the Plant Owner, or his Agent, a completely documented set of exainination records including certification of personnel qualifications with a current eye test report in accordance with SNT-TC-I A. 2. Distribution will be in accordance with Stone and Webster SH1-397.

13. EXAMINER'S CRITIQUE 13.1 PROCEDURE CORRECTIONS AND ADDITIONS 1.

All procedure corrections and/or additions required during the preoperational and/or inservice examinations shall be made in accordance with Stone & Webster Engineering Corporation Engineering and Design Co-ordination Report (E&DCR) Form No. A5210.4D SNPS, SNPS-1, Rev. 7/73. 2. The examiner wSI centact the Stone & Webster representative on site to initiate all such changes. 13.2 CRITIQUE REPORT 1. Upon completion of the examination of all reactor pressure vessel welds, the examiner shall submit a written report to the plant owner or his agent listing pertinent information for future enmination such as procedure additions, corrections and revisions, or unique problems or actions to be taken. 2. Distribution shall be in accordance with the Stone and Webster 151 Program (SH1-397).

14. FIELD QUALITY CONTROL Stone and Webster Field Quality Control (FQC) will perform a surveillance / audit function-to in.,ure that this examination is performed in strict accordance with the requirements of the NES Quality Assurance Plan for SNPS-1,80A0448 FORM = NES 205 2/80

i Drec.tir.o: CE-E '2%-23'T Proccdure Lo.:

Jonnu, Toollt;:

Mant:al Secrch Units 6"

Subject:

lif4'-SNPS-1 Be* c' -

  • ~"*
  • Icsue Date:

June 10, 1975 Revision Uc.: 2, Date: 8/31/81_ Page 19, of 34 n :: :. : ::-) cz=:; A j , a. A, i i l 1 l.5* 1 ._.7'_ 3f'= Lh. cf ':0 e e... '. )eai J - 1 i A /*s $ - *I. p ~ l. L *. E k**5 , / i -= s

  • : ' i l, i.

j 5 y / '[ 4 5.'.==... _ O .m j. 3,'A e:e.t c--> ); 1' s___ 2. 0', . ___'..,..f 1'_:/?,'V/////////!//////) 2L O'Y- $ ll!!!!!!l!!!!! l t-I t 1 -- { 4 5. 'g=;f2 __9.___. c s f -- 5-7/8" S m,,t. n, u r - r et,,-4, 4 o Inre.llel to Weld I = 1 - Ferpendicular to Weld

  • - O' Eare l'etal her;*

10.0" iEAZ '. eld snd Heat Affectea Zone q 45' L i h

> O ' *

..,....-..../ Note: Eor the circu::tferential shell to flange weld only two directions parallel with the weld axis is required i ; 1 2\\ ' FZj'73 1. Eri.CTOR PC'GSU?S 03F'., Ci"CtJ 2I?%'Tll L LIi,L3 UI-FEP GEELi, COUdS23 j ,~ 0 ?. - f.,j IWCLEAH ENEHGY SERYlOCO. k'C. d

Dru in;: C-E-2t-237 L CE-E-23 4-29 Precedure I!o.: 80Ac462 Toolin;:

2nual C.er.rch Un$ ts Subj ect:

RFV-SNPS-1 ~

n....-.

-n <, _... u 13 sue hte: June 10. 1975 o -.. Revicion Ro. :

2. Date:

8/31/El Page 20 of 34 7 / .I l .~ ~ n.1, w, a.n.x _o* A i ,t l 9 t l 1;5 *.L -lL--- jj m_ r. t a. er n l h I1 ~ 1 l 10.O" ~ n:n ura on 2 I i f m,. e Ai. /. / . m it9'.__ . < I; \\ \\y i 'j f 0,._. Z / 1, i., b l.o" ~ W _ 2 i E- ~ A 3^ ' " *' t i i t' Y X 2 0" 5-7/8" 5 't k y e __ O' E' Z I i i f N i. SCAU PATH LEG'C:D = - Farallel to We16 is ., 1; p ~i 1 - Perpendicular to# / Weld

  • - O' Base Metal

_ __3'- > O'

  • Exa:n.

[ '5IAZ - Weld and Heat

  • I Affected Zone
  1. e(W I

1 h l vi:cI-I ?. nzArtea pr.asme,a.::1;nwn:;a 1as I UFFER 3HDLL con. 3 O e a .6.J ::uct..f.r, a : aav m, vices, me.

F J l

  • Drrem,-

CF-E.23h-ph*2 Procc5u.re Eo.: 90A0462 '? cam r ; 1'anuel :.icarch Units

Subject:

II -SNPS-1 Her..nd.: 6" facue Late: Jun O O. 1975 Revision 1:o. :2 Late: 8/31/81-1 Page 21 of 34 UI.' ' I 1 TM. (0* ) 03.C a s j i l I O'

  • I I

_ 3.s r:3 er sa e 4 et r i j s 4 \\ he* _L w J 5:C ETAN TUC'.,21 12.0" \\ 5-7/8" ) s /.t e o I w.c EI-l l ( S--g-e /= y n j \\. I j -__ ) 1 / l o ? n tt 2

  • - 0 k- -,(

s u. v. e :: 1 j i l 1 '< /8" / j- .v, .n 1? l i [ ,f l i .3 n l ss e \\ v kS * =- i o }. ~ f, O' 'd D.Z h i k C-7/6" 7. SCA:: Pl?_~. '

'GT.3>

I 1 l ~ Parallel to '.. eld I L - Ferpent'icdler. to rl+1 - 13.0" h r-a.l. - O' Bace Metc.1 :'xar., / /' .Ield End ,.A.C ht t i, sw, - L

  • rc

,e 3 g-nAAOCtCC tone u. e 0 i 1 f .6 ? I i ( i As l i ,/ v' ? / e . 7 -. ? .y ..,.-4 nCi t,s s v. s.o - s y3.. ps 3-n.1 ,.3.-.,.,., . ~ 1.s,,., s r. t.yJ.,, . : w. ca.>. r . o.-> I.,' l.4s r.,V n..._

c.....

,,.c L . 6e. .4 's ..), w a th .. _... ~... .....-...~ _...,[- 9,'!j Q[ *,3 {;,';a, g 7 --*3

CE-E-23 -h73 & CE-E-23h-23h Procedure No.: 30A0462 h Drawing: Tcolin;: ?'anual Search Units Subj ect: hPV -SNFS-1 1n Issue Date: June 10.1079 z. 7E ~~' Revicic:1 Kb. :_2 Date: 8/3',1181_ _ < ne. S a.: Page 22 of 34 I I e I m: s r.. : v ) rc.c r.. O*

  • p i

f'N i i l l I I L_ J l_ l l' A h5* L ipi_ i i 3/ Eis.. f L '.: a 0 1 I 11.C" L'. 3*:' t EL'!. r.:J..T.3 c e I_' t h [' / 4 i = w<v;; i t > h5*== \\l' \\, 1 \\. 1 o* WIGZ b- ], ??~ = e m 2.0".,/F" Ik. 3,. - / %'-1-3 i 2.0" - - -. 7/S" - ak I MS* = SCAN FATH LEGOD 0 * '*"" Z

  • = - Parallel te Weld

. L - Perrensicular to i' Ueld I i

  • - 0* Eace Metal 11.0" E;.am.

I WAZ - Weld and Ecat i Affected Zcne i l ,f h 5 '.1- > oo, i f. f. FIGUI:E h. REACPPR FRESSU.7" 'T3.3EL LG:3IRDII:AL ITCLD3 LC'..TR S6'::, CC' % J i s"n ,,,j. ttCLEAR EN.'.CGY 3 T.VICCG. INC. N u._..

Proedre Ho. : 80A0 m Draving: C2-E-234-E35 Dub,)ect : RF/-SWPS-1 Tooling: I.'.anual Sec*ch Units Iccue Dt_te: -Jt:ne 10. 1 o75 Ref. Std. : 7d" Revicior. No.:,2, Dato:_ e/31/s1 Page 23 _of 34 I, s

.euc:r w:p*) n arn 7.-

'NA k f ~~ 0 I l* A . 45* L 7, l: i { g i ,_g__ s m. e r: s 11.0"

s..
t. = u:: : =,== -

.N r t ~ r I l \\ i e i.4 ~, 1 j

.C' L* *. s' '* ',

.n\\. , \\ l \\ : \\ h / g[ \\ 'N / _ _); 2A nec cr s N h5*== s 0* tmz j l j 2.0" c - N \\,\\.],' 4 1-3/8" 'N \\. -s 0" x 'N N\\'. \\ N\\ I C. 6-13/16" h .,',,i, s s 45* -- SCA?! PA~"i LEGEND

g. g,,,g

= - Parallel to Weld _L. - Tarpendicular to Weld / ^ - O Ease l' tal E::a:n. i.EZ - Weld and Eeat / Affected Zen 0

11. 0

k / t ,/ 1 1 L5* L 'y o' x-I y W /, d j l'ICUIiE ~. R" ACTO ~' N'l'55E /E33EL GLSH USLD If.G:R TCliUS 20 DC'E , O. /..- ;,1 !!'JCLEATI Cf!EilGY SERV 6CES, it C. /

1)ravinc: CE-E-?34-235 Toolirc: TQrit al Search Unit: Prece. lure lio,: 80A0462 per "e,3.

Subject:

ITISIiPS-1 t Iccue Date: __.Tymn t o, log _ _ Iie:'icica I!o. : 2 Date: E/ ~31/81 'I Pa;*e 24 ~$[_3 d. - _ ' _. f, r I-l no 4 / ~~ v s f,' 45 1 2-4 10.0" l i. yo = / O* EAZ / l 6-13/16"_ - /g N _ l. 5,,., '7//////////////// \\ 9 /- / (/ / / / / / / / / / // / / / / / .E_0., e 7-t /

1. ),.,,

h5c = O0 ' ".t15.a C ~ I v 4 7 07F1.L ' ; IL'J: (C') O'32.*: :'; S('/d! PATH OE:C = - Parallil te l f l f_. Weld I J .L ~~e:perGl=v-lar to 1.' ele ]_ >;;. ta. cr : -

  • -O

~

Sare I

Metal Exac. 10.0" I

.,f;3 _ ;.; eld and Heat I45" _L Affected l

Zone b r m. a. -/ /,\\ ,'g j \\i j t b i' 0* * \\ (' N, Jll-L__ _ f 3 ':. p' e.: er r;; -. _ _ _ __ y v _ i FIG L S 6. U'E:'c'.CC:;IC U./JEATIC O? LO'c}iT. TORU3 'IRIDIO: AL 1.5LD3 4 t O r -- y --- 4, j f.'UCl.EMI Ef!ERGY SEliv;CES. WC. k

Procedure No. : 80AO'462

Subject:

RPV-SNPS-1 Issue "ntei June 10, 1975 Revision No.:,_2 Date: s/31/g1 Page 7s of 34 cre.In: w,t: (c*) resz:r.c / 1 g i_ _:_.Q t in. or 30 0 0 h5 1/2" CIRC 60 m:. m:: cccar:; 'l h" RSF j 'l ^ ,x meek / XI +w( i t I i .2 \\,. 4O -) O W01 't EL' O g/ ,\\ \\ N \\ g g 13 1/2" O & CIRC \\ ANGLE BEAMS \\ i N 7" LONG ANGLE BEAMS / \\ // \\ / 45 ',I 600 j x t LONG / I'/ SCAN LENGTHS ARE MEASURED / AT -THE SURFACE / 0 0 k ( o C30 . FIGURE 7-ULTRASONIC EXAMINATION OF REACTOR PRESSURE VESSEL TO SUPPORT SKIRT I NUCLEAR ENERGY SERVICES, INC.

_m 4 4 Procedure No.: 80A0462

Subject:

Epv _snps _1 Issue Date: June 10, 1975 -Revision No.: 2 Date: 8/31/8_1 Page 20 of 34 f EXA!G ATI O SURF 1,CE 0 l h 1AT o d) 1/Fr O f) ) noTCn.DErrn 3AT O O L o u CLAD -- e k D q Fl n

l :.

l'l ' i

ll ll l l t t I f f f e

\\\\ SCRIBE LINE = CALIBRATION HOLES (6) C-E Block l Block Huder Thickness 1/4T 1/2T 3/4T Hole Dia. Notch Depth SNPS-1-6" 5-3/k" Nom 1 5" 3 0" 4 5" .250" .120" BASE MET /L 5/16" CLAD SNPS-7-71/4" 6-7/8" Nom 1.81" -3 62" 5 44" 312" .140" BASE METAL 5/16" CIAD FIGURE 8 ULTRASOUIC REFERENCE ST/JiDARD e NUCLEAR ENERGY SERVICES, INC.

mee ^ Procedure No.: COA 0462

Subject:

RPV-SNPS-1 Issue Date: June 10. 1975 Revision No.:_2, Date : 6/31/81 Page 27' of 34 [t ]-t ft ,norca 3/5t 481/4tnarc., NOTCH nnnnn n. n.

n. -

s a s s i s s s 6 's, 'N, \\Q 6 s% 's n Straight Beam Angle Beam Search Unit Positions Search Unit Positions e Typical DAC Curve Typical DAC Curve r r 'b 'f s j, - s q," 's s x N s s N ) .L l \\ l ) \\ l l l l l l li l l l-o 2 4 5 t (o j 4 ] HTE: For velds under 1" thick, use 1/2r hole only, no DAC required. Step 1 - Adjust sweep controls so that 1/4T,1/2T, and 3/4T holes are located respectively on the 2nd, 4th, and 6th horizontal screen divisions. Step 2 - Adjust sensitivity to provide 8CF' FSH indication from hole s giving maximum response - mark position on screen. Step 3 - Position search unit for maximum response from remaining holes - mark position on screen. 3 Step 4 - Plot DAC by connecting points marked on screen with line extended to cover entire examination rar.ge. Step 5 - Record all sweep and sensitivity centrol settings on respective data sheets. Step 6 - Position search unit for maxi =um response frcm far surface notch and "X" cark screen and data sheet to indicate a=plitude. Step 7 - Repeat Step 6 for near surface notch if detectable. FIGUEE o. ParatE: ICE SEUSITIVITY AND DAC CALIBRATION PROCEDURES l FOR ULTRASONIC E7.AMIIIATION OF WELDS. e NUCLEAR ENERGY SERVICES, INC.

5 Procedure No.: 8CA0462

Subject:

R W _sNps _1_, CALIBRATION DATA SHEET NO.631-1 Issue Date: June 10, 1975 _ MUIUAL EXA?GIATION Revision No. : 2, Date: R/31/81 Page 29 of 31 EXAlE!ATION AREA TRA?!SDUCER IDENTIFICATION ULTRASONIC INSTRU? SIT STYLE OR TYPE NO. MO;EL NO. SIZE SERIAL N6. FREQUEIICY SERIAL NO. COI TROL SETTINGS ANGLE & MODE EEAM DIRECTION (= or_Lto veld) PULSE LENGTH ~~ ~ SCI's FIXTU2E FREQUENCY dB GAIN CALBRATION BLOCK SKTEP LENGTH ID NO. SkIEP DEIAY SIZE VIDEO FILTER EXAIE!ATIGI SURFACE REJECT Hole Depth Amp. ,Atten. ID Ei. G dB INSTRU?ENT LINEARTTY CALIBRATION Ar:plitbae High ' Low High Low .L. ,5. 2. '6. 3. 7. 4. 8. Ref. Angle Incident Pt._ DAC PLOT AMPLITUDE CONTROL LIFARITY 10 Initie.1 8 dB Re uit 9 -C A U DI r n (n, sr 'v NL.Ii 80 _6 S.'t.i.j 80 _12 M VFR SiONS Whiny 40 +6 REQU: :# m r m o r_ ~ 20 +12 llQl~y "i e . n y mi u s.wt AUU!tF FABLE. MMR(S) 3 SNT-TC-IA 2- . 1, Level 1 SUT-TC-1A 2. Level C DATE: 0 1 2 3 4 5 6 7 8 9 10 WITNESS: FIGURE 10 NUCLEAR ENERGY SERVICES, INC.

y a Wild SCid! DATA S11EE:f ! Procedune I:o.: soRo462

,! Sub,]ect

RP!-SNPS-1

1. Calibration Data Sheet I o.

j Iscue Date: .yun.10, ioH

2. Exanination Angle

! EUViCIO3 IIO _2 Dsce: 8/31/81

3. Area of Exanination

,jPage 29 of 34 ,4

4. Examination Surface

--,_,.._,--s,-r..~----~.~-u-~~~~nx. Scan Cor.pletion e Weld, Iten c o m e Corents: a av

e oc c

Or c oc c i e-e o o P D' M O -H f a.e4 .H D e.:>Can I!O. ,o 3810Cn.Or inCOmplCted Scans p e o H-d4 oo oe OL p 4 d e4 d C,c 4O H O 4 0 ,o o o0 0o' O.ra e .,4 ge 0 t9 4 C y HC H C A. C at o 4.> e p. co ao ac ac so A J: EU dO ZH OH p, <l 4 L P. p. v e O d I. =O f r. tn io y o o s-ct i i I J l i I I l l l l d l I I l l l OMDI t-Akin v .C a ii %/ s i t. t l 8 1 i i "M l L Wef VjaFy"LU N 0 '" ~ ^ ^ " "n' tU ' ' ^ 88 VV n i REQUIRF THF7 RAMF .i i i. i T IN' FDRM-ATtOtt%REMEPTABLE. ~ 1 I - J 1 ~~.u.= w-w.w-=-., .;.n-a- .s .s ~, n. - - n t-Calibration Checks e O Additional Sheetc At tached: Exa. int.tienSysteE~!! Inctrunent

Centln m,ien Supplements t.

Tire l Date Time Date i,; - v.,..m%er(, ) - SNT -TC-1A [ 1. T,cVel 1 1 i SIiT-TC-1A 2 Level 'I. t-0 Date: FIGUE 11. ft ..c. n _.._.___,f{ s:uctt.,n c : n,. can j:c=, :..c,

Procedure.:A: 80A0462 WELD SCAN DATA SHEgr

Subject:

pw _sNps _1 Isst'e Date: Jtme 10. lo75 - SUFFLEMEITf A hevision No.: 2, Date: 8/3178T (BASE !EAL) Page 30 of 34 Weld No. Sheet of Calibration Data Sheet No. A s f. l (- Note: Locatien inerenents are ~ ,-l not to exceed allowable scan inerenents. P ii P 2 H,= c x I-n t. idb fron DAC (1) Indication No. Depth L 1 L2 F1 P2 (Echo (CDAC )(2) CG0GT3 SAMPLE ONLY EIMiLAR VERSIONS WH!CH R EQU; RE TriE S A M E INFOR MATION ARE ACCEPTABLE 8 1 End points of L & distance from surface are 61b belov (50% of) DAC. (e-(2) Signal Anp11tule I db fron DAC SNT-TC-1A and in % DAC, ie-61b (50%) 2. Level Date: ( FIGGE 12. e NUCLEAR ENERGY SERVICES, INC,

I I Procedure ho.: 80A0462

Subject:

RPV-SNPS-1 WELD SCAN DATA SHEET Issue Date: June 10, 1975 Revision No. : 2, Date: 8/31/31 i SUFFLElENT B Page 31 of 34 Weld No. Shee', of Calibrar, ion Data Sheet Iro. EX AM. A N GLE O i s.u. g g g q p._p 4 ( I _ l l L I P (Distance from weld ___[,. Distante C/Llo indication C/L ( from surf ace ' I ' " ! " ' *

  • I ' ' ' )-
s. u.

~' Note: Location increments are not to exceed oink pc[iEf, o En n Ind. BEAM hx ' Dist. 750: P Forward (1)(2 I Back (1)(2) Deeth ( D ) Nc' DIR. I'002 tic" sig surfa e Mst. Fre: P Dist. From F Incher

f. T g)

Surface Surface SAV pl.E OMl_ V Si viiLA,1 V i-RSIONS WHICH REOUi RE THE S AME l.h i C A.D.!A A, Tin h t t.r") r-,A PO CD"T" A Of C . s . v 3 eivi c. u sv v 6. iru.ea a. l 1 NC1'E: Examiner (s): (1) End points of L & distance from S?E-TC-1A surface are 61b below (50% of) DAC. 1. Level (2) Signal Amplitude I db from DAC and SNT-TC-M in % DAC, ie-61b (50%) 2* Level Date: FIGURE 13. e NUCLEAR ENERGY SERVICES, INC.

Procedurc. i'o. : 80A0462

Subject:

RP7-SNPS-1 Issue Date: Jurd_lO lo79 lievision lio. : 2, Date:. 8/31/,81 Pq;c 32 of 34 TABLE I '5IT IDE fIFICATIO:? liUCIZ1J1 CC::FC::E.~fS ~ Sheet 1 of 3 SHE2 C7E.SI it2:. .. t e Weld :5. TMse"irtion IO c9 N f er N Fim'"es .o

  1. 4

-Circu derential 6" SE R-14E-2 Exam Only Elevaticn 553" EES-DE3412 25* to 104 Firure 1 115 to 155' 166o to 245* ~ 282o to 335

  1. 3 Circuderential 6"

SE: W-lhE-2 Eram Only Elevation 403" ITIS EDE2hl2 36 to 104 1280 to 142 Figu e 2 166 to 232 256o to 262 286 to 348o E2 Ci curferential 6" SE-? N-14E-2 Exan Cnly Elevation 253" IES-30D0412 36o to 127* Figure 3 166o to 246* 2860 to 012

  1. 6 Len.gitudinal 7"

SE? N-lhE-2 Exam Only Azinuth 18 Figu e 4 128" to 240" ~

  1. 14 Circunferential 6"

S&W TV-14I-2 0* to 360* Elevation 703" NES 80D0412 Figure 1 Azimuth Ref. - CE Sri i 180* Elevation 0" = invert 0 Flange = 720-63/64 2 Figure 14 0 sa I I *,] ::'JCLEAR E!;ERGY SERVICES, INC.

v Procedul'e Iio. : 80A0462 Sub.j ect : RP'l -SNPS-1 Issue Date: June 10. 1975 Revision No. :_2, Date: 8/31/81 Page 33 of 34 TISLI I ~ MELD IDE~I_~"EATION BELG SL7P:F.2 SEIRI ,3 HUCLEAR Cf *GO:!L'TS

iier, i

1 eld "a. Descrit; tion 91oc'- '3eference Piqures Notes

  1. 19 circunferential 7"

.3E: Fi-14P-2 Elevaticn 5-9/16 " rigure 5 (Ltmer Torus Eing to Dome)

  1. 28 Lengitudinal 3M: Ti-lhP-2 Sean te Skirt Acirath 5*30' ficare 6 i

I

  1. 29 Longitudinal Anirreath 65 30'
  2. 33 Loreitudinal Azir. nth 125*30'
  3. 31 Loncitudinal Azinuth 185*'.0'
  4. 32 Lorsitudinal Azirath 2h5*30'
  5. 33 Longitudinal Azirath 335 30'

'\\r y Azifrat - Ref. - C3 S&W i 180* Elevatica 0" = invert G Plange = '/22-63/d"' Figure 15 co r. ^ /*1* - z ; fiUCLE/ R EllERGY SERVICES, triC.

e- 'j - Procedure 1. >. : 8nA0462 i

Subject:

RPV-SNFS-1 Issue Date: June 10. lo785 Revision No.:

2. naen-8/31/.81.

Page 34 of 34 TABLE I WELD IDEliTIFICATION Sheet 3 of 3 NUCLEAR CCMPOISITS Ref. Weld No. Descrintion Bicek Reference Figures Notes RP7 to Support Circumferential 7h" SPE-E234 h75 F Skirt Elev. 28-1/16" Figure 7 to34-3/4" i i i I 4 e 1 i l e 'l I O NUCLEAR ET4ERGY SERVICES, INC. . - -.... _..... _,. _.}}

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