ML20040G050
| ML20040G050 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/11/1981 |
| From: | NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20040G049 | List: |
| References | |
| 80A0475, 80A475, NUDOCS 8202110179 | |
| Download: ML20040G050 (59) | |
Text
a PROCEDURE NO.
80A0475
SUBJECT:
MANUAL SAFEEND WELDS PAGE 1
0F 35 MANUAL ULTRASONIC EXAMINATION PROCEDURES FOR VE
, SSEL N0ZZLE SAFEENDS AND. CLOSURE, HEAD N0ZZLE-FLANGE WELDS LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWER STATION UNIT 1 1
CONTROLLED COPY VA.lD ON.Y F TS ST,lP.S RED t-Prep'd by o
NES l2 2 17 Project Mgr Date REV. NO.
DATE NES
. 7-M A/2/7f 0
2-15-78 NES m
2 7g ISI Pro'
. Level 111
~ Date '
1 7/27/79 NES J-4~7f QA Mgr.
Date 2
1/16/81 I*
4[7/78 e
me u 3
2/3/81 LILCO Date 4
8/28/81 5
12/11/81 Date G
PDR t
e PROCEDURE NO.
80A0475
SUBJECT:
MANUAL SAFEEND WELDS PAGE 2 0 F _'Fi, 1
Rev-Prep'd No.
Date Description Reason By
' App'd By 1
7/27/ Changed; 2.1(4) & (5),5.2.3, General revision to incorporate F. T.
79 5.3.1, 6.1(2) & (3), 7.3.2, latest NES requirements.
Carr C 5.2.7, 7.3.3, and Figures 2,5, W
6, and 7.
Incorporated Field Change 1 g/7/11 Deleted; 2.3 Added; 3.1.3 CRA-972 pl 2
1/15/ Para 1.1 Added Item 6 Update procedure 01 Para 1.2.1 Revised Para 1.2.3.Added Para 1.4 & 1.5 Changed to Figures 1 through 7 Para 2.1.3, 2.1.4, 2.1.5, Updated Para 5.2 Revised Para'6.1 Revised Para 6.2'Added Item 10 Para 7.1 Revised Para 7.2 Added & renumber-ed accordingly Section 8, 9, 10 Revised Added Fig. 7 Delete Fig. 9, 10, 11, 12, 13, 14, & Table 1 Added nes Figs, and numbered accordingly CRA 1670 f
NUCLEAR ENERGY SERVICES, INC.
Procedure No.
80A0475
Subject:
Manual Safeend Welds Page 3
of 35 e
d w
N l
p.Ev.
PRE'D APPROVED l
NO.
DATE DESCRIPTIOL REASON BY BY 3
2/3/21 Para. 4.1.2 added '
Customer Con. ment S. L.
NES LILCO
... Level I Trainee Foote Para. 4.2.2 changed sub-mitted to available Para. 5.2.1 deletes last sentence Para. 5.3.4 added
...when required Para. 6. l(5) revised Para. 6. l(8) added
...when required-Para. 6'.~ 2 (10) added-feedwater Para. 8.2 - typo Para.'8.4.2 revised title Para. E.4.3 revised title Para. 8.4.4 deleted and revised Para, 10.1.1 (1) deletad (as a percent'of T)
Para. 10.1.2(4) deleted
... hole reprenanting T Para. 10.1.3 revised Para. 10.1.5 deleted (as a percent of T)
Revised to upstream and downstream NUCLEAR ENERGY SERVICES, INC.
a
e:acecure no, cuaun.2
_p
- /
Subiset:
Manual safeend Walds _
Pega 4
(2f
.D -
o
{
PRE'D APPROVED sp;'/.
No.
DATE DESCFIPTTON REASON BY BY
+
3 2/3/81 Para. 11.1 changed shall Custe er C6mment
- 5. L.
NES LIICO Fo'ote to =ay Para. 11.2 changed exa-4her to NES 4
8/28/
Para. 5.3.4 deleted where Ince:perate all previous >
G 1
7.f/
al required...
field changes e
Deleted para. 7.5.5 Rent =bered remainder of section Revised para. 8.4.
I Revised para. 10.1.6
~
Revised Figure 7 Revised Figure 12 Refer to CRA 2086 5
12 Procedure completely re-To t=gade the examination
[
81 vised. Due to the extent Tech'.ique J
of Technique and Fornat change, pmvious Revision ntabers will not be illus-trated on the boarder of l
the revised paragmphs.
e I
NUCLEAR ENERGY SERytCES. IRCD
DOCUMENT NO.
80A0475 NUCLEAR ENERGY SERVICES, INC.
A MANUAL ULTRASONIC EXAMINATION PROCEDURES FOR VESSEL NOZZLE SAFE ENDS AND CLOSURE IIEAD NOZZLE-FLANGE WELDS
- 1. SCOPE 1.1 AREA OF EXAMINATION This document covers the manual ultrasonic examination procedures for:
1.
Main Steam (N3) nozzle to transition piece welds.
2.
Jet Pump Instrumentation (JP1) (N8) nozzle to safe end piece welds.
3.
Control Rod Drive (CRD)(N9) return nozzle to cap weld.~
4.
Core Differential Pressure ( A P) (NIO) nozzle to safe end piece weld.
5.
Closure IIcad Vent (N7) and Instrumentation (N6) nozzle to flange welds.
6.
Feedwater (N4) nozzle to safe end welds.
7.
Core Spray (NS) nozzle to safe end welds.
8.
Recirculation Outlet (N1) nozzle to safe end piece weld.
9.
Recirculation Inlet (N2) nozzle to safe end piece weld.
1.2 TYPE OF EXAMINATION 1.2.1 Volumetric examination shall be performed using ultrasonic pulse echo nominal 350 or 450 angle beam shear wave, 450 refracted longitudinal wave, and 00 straight beam techniques applied to the outside surfaces of the piping, safe ends transition pieces and flanges.
1.2.2 The examination shall be performed manually using contact search units (transducers).
1.2.3 Other beam angles may be used as alternative examination techniques when they facilitate examination or evaluation.
1.3 TIME OF EXAMINATION These procedures shall govern the preservice examination and reexamination of repaired areas of the pipe welds as required by the ASME Boiler and Pressure Vessel Code,Section XI.
FORM :NES 205 2/80 l
DOCUMENT NO.
80A0475 mur M
=
NUCLEAR ENERGY SERVICES, INC.
1.4 WELD CONFIGURATION 1.4.1 The nozzle and safe end/traasition piece / flange weld configurations covered by this procedure are shown in Figures 1 through 9.
1.4.2 Nominal weld thicknesses range from 0.28" to 1.844" and are specified in Figures 1 through 9.
1.5 MATERIALS The nozzles, safe ends and fittings are constructed of austenitic stainless steel, carbon steel, or inconel, as designated in Figures 1 through 9.
- 2. REFERENCES The following documents form a part of this examination procedure:
1.
ASME Boiler and Pressure Vessel Code,Section XI,1971 Edition and Summer of 1972 Addenda 2.
ASME Boiler and Pressure Vessel Code,Section III,1971 Edition and Summer of 1972 Addenda 3.
ASNT Recommended Practice, SNT-TC-1A,1975 Edition 4.
NES Document 80A0482, Preservice Inspection Program Plan, Unit 1 (latest revision) 5.
NES Document 80A0448, Quality Assurance Program Plan for Inservice Inspection Program (latest revision) l 6.
NES Document 80A9068, Procedure for Training and Certification of Nondestructive Examination Personnel (latest revision) 7.
NES Document 80A9053, Procedure for Ultrasonic Instrument Linearity Verification (latest revision) as modified in paragraph 7.4.2 of this procedure 8.
NES Document 80A9005, Inservice Inspection Data Review Procedure (latest revision)
I' 9.
NES Document 80A9060, Inservice Inspection Field Change Procedure (latest revision)
- 3. PROCEDURES CERTIFICATION The examination procedures described in this document comply with Section XI of the ASME Boiler and Pressure Vessel Code,1971 Edition, including 1972 Summer Addenda,
(
except where examination coverage is limited by pa-t geometry or access.
FORM :NES 2C5 2/SO
DOCUMENT NO.
80A0175 4
m NUCLEAR ENERGY SERVICES. INC.
- 4. PERSONNEL CERTIFICATION 4.1 PERSONNEL CERTIFICATION REQUIREMENTS 1.
Each person performing ultrasonic examination governed by this procedure shall be certified in accordance with the documents referenced in paragraphs 2.1,2.3 and 2.6 above.
2.
An examination crew shall consist of one or two members as needed. At least one member of each crew shall have a minimum qualification of Level II in accordance with the above referenced documents.
The remaining member (s) shall have a minimum qualification of Level I or Level I Trainee.
4.2 PERSONNEL RECORDS 1.
Records of personnel qualification shall be maintained by the Examination Contractor.
2.
A copy of the examiner's certification summary and a current eye test report as required by SNT-TC-1 A shall be filed with each permanent examination record, with a copy available for the Plant Owner, or his Agent, prior to performing examinations per this procedure.
- 5. EXAMINATION REQUIREMENTS 5.1 EXAMINATION FREQUENCY 1.
The nominal examination frequency shall be 2.25 MHz for all straight beam and angle beam examinations.
2.
Other pulse frequencies shall be used if suen variables as material attenuation, grain structure, etc., necessitate their use to achieve penetration or resolution. This information shall be recorded on the data sheets.
3.
5.0 MHz transducer may be required to achieve resolution of the side drilled holes in the calibration blocks.
5.2 EXAMINATION ANGLES AND COVERAGE 1.
The intent of this procedure is to provide maximum coverage to ensure weld integrity. Each weld shall be scanned with a minimum of 25% overlap of the transducer element dimensional width (diameter) for each scan pass.
The area to be examined shall be divided into two (2) zones; carbon and stainless steel.
The instrument shall be. properly calibrated for examination of each separate zone.
i FORM NES 205 2/SO
D DOCUMENT NO.
80A0475 m
=
NUCLEAR ENERGY SERVICES, INC.
k t
2.
The rate of search unit movement shall not exceed 6" per second.
3.
Each weld and the required volume of metal (WRV) for IT on each side of the weld shall be ultrasonically examined using 350 or 450 shear wave or 450 refracted longitudinal wave angle beam techniques applied in two directions towards the weld and in two directions parallel with the weld, except where restricted by part geometry or access.
Note:
Circumferential scanning performed on safe ends with thickness /diamete- (T/D) ratios greater than.15 shall utilize a 350 angle beam technique.
4.
Straight beam techniques shall be applied, where part geometry permits, to all base material through which the angle beams will pass during angle beam examinations. Indications detected are to be recorded in accordance with paragraph 10.1.1 of this procedure.
In addition, straight beam techniques shall bc applied to the WRV where part geometry permits.
Indications shall be recorded in accordance with paragraph 10.1.2 of this procedure.
5.
Other beam angles and or longitudinal waves may be used as determined necessary, i.e., for evaluation of reflectors, to compensate for geometric constraints, etc. All information shall be recorded on the data sheets.
6.
Where the examination surface, geometry, or other conditions (weld, contour, access, etc.) do not permit a meaninful ultrasonic examination to be performed, the examiner shall record the area of non-examination and the particular interfering condition in the space provided on the Weld Scan Data Sheet. In addition, he may make a sketch of the weld and adjacent pipe and fitting conditions on a separate sheet of paper and attach to the Calibration Data Sheet.
Photos may be taken when possible and incorporated as part of the report.
l 7.
All examination weld / areas shall be entered in the space provided on the Calibration Data Sheet. If there are no recordable indications, it shall be i
so recorded.
8.
Coverage for the welds specified in this prceedure is shown in Figures 1 l
through 9.
5.3 LIQUID COUPLANT 1.
The ultrasonic couplant shall be suitable for use on nuclear plant materials and be certified not to exceed 50 ppm halogen and 200 ppm sulfur.
l 2.
Tha c% plant shall be supplied in clean containers of sufficier quantity to i
perform the examination.
3.
The couplant shall be applied manually with a brush or other suitable device.
l FORM = NES 205 2/80
DOCUMENT NO.
80A0475 mv W
NUCLEAR ENERGY SERVICES, INC.
A 4.
The examiner shall be responsible for removing couplant from the examination surface at the conclusion of the examination, when required.
5.4 SURFACE PREPARATION All examination surfaces shall be clean and free of dirt, weld spatter, etc., or any other condition which would interfere with the examination or impair proper transmission of the sound beam.
5.5 WELD IDENTIFICATION Each weld shall be located and identified per appropriate weld maps in the Program Plan Book.
5.6 DATUM POINT 1.
The examiner shall verify that there has been marked a reference datum point on each weld from which all examination data and reported indications shall be referenced.
2.
Datum points shall be marked by the use of low stress stamps or vibratooling and shall not be deeper than 1/32".
3.
The datum point for all safe end/ transition piece welds in horizontallines shall be located on the top of the pipe at weld centerline.
4.
Closure Head nozzle to flange weld datum points shall be on the weld centerline at Closure Head 00 5.
Each weld datum point, along with respective weld reference points and divisions, shall be shown on each examination report.
l
- 6. EQUIPMENT REQUIREMENTS 6.1 EXAMINATION CONTRACTOR'S EQUIPMENT The following test equipment, or its equivalent, shall be provided by the i
Examination Contractor (as a minimum) for examination of welds specified in l
this procedure.
l 1.
Pulse echo ultrasonic instruments.
2.
Search Units,1/4" thru 1-1/8" dia., 2.25 MHz, 00 1
3.
Search Units,1/4" thru 1-1/8" dia., 5.0 MHz 00 l
l 4.
Search Units,2.25 MHz (all sizes) for angle beam wedges 5.
Wedges: Assorted sizes to accomodate search units Y
l FORM :NES 205 2/80
DOCUMENT NO.
80A0475 m =
NUCLEAR ENERGY SERVICES, INC.
6.
Any additional angle wedges to aid in examination or evaluation 7.
Couplant 8.
450 Dual refracted longitudinal wave for use on material >.750" in thickness, when required 9.
Miniature angle beam verification block 10.
Thermometer 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.
Calibration Block No. STEAM 6.
Calibration Block No. JPI 7.
Calibration Block No. CRD 8.
Calibration Block No. AP 9.
Calibration Block No. VENT
~10.
Calibration Block No. Later (feedwater) 11.
Calibration Blocks Nos. CS-1-1B, CS-1-1 A, CS-2-A and CS-2-B 12.
Calibration Block No. RC IN 13.
Calibration Block No. RC OUT 14.
Test Surface Preparation (cleaning and finishing) 15.
Drawings of each Examination Area 16.
Post-examination cleanup of Test Area if FORM = NES 205 2/80
DOCUMENT NO.
80A0475 av NUCLEAR ENERGY SERVICES. INC.
A
- 7. CALIBRATION REQUIREMENTS 7.1 CALIBRATION DATA SHEETS Calibration Data Sheets shall be numbered 475-1, 475-2, 475-3, etc., and shall be signed by the examiner (s) upon completion noting applicable SNT-TC-1 A levels.
7.2 CALIBRATION BLOCKS 1.
The miniature angle beam calibration block designated in 6.1(9) shall be used to establish horizontal linear instrument range.
2.
The calibration blocks designated in 6.2 (5) through (13) shall be used for establishing reference sensitivity levels for examination of the specified welds.
3.
Spot thickness checks of the components shall be made prior to preservice examinations to ensure that the proper calibration block is used.
4.
The identity of the calibration block used for performing calibration shall be recorded on each Calibration Data Sheet.
5.
System calibration shall be performed using the material side which corresponds to the material which will be examined; i.e., carbon and carbon; stainless and stainless; of the calibration block.
6.
The temperature of the calibration block shall be within 250F of the component temperature. Calibration block and component temperatures shall be recorded on the Calibration Data Sheet.
7.3 REFERENCE SENSITIVITY LEVEL 1.
The reference sensitivity level shall be the distance-amplitude curve initially obtained directly from the calibration block and shall be the sensitivity level used for evaluating and recording allindications.
I 2.
During actual weld scanning, the reference sensitivity level shall be l
increased a minimum of 2X (6dB), but not more than 10dB. The actual scan sensitivity shall be recorded on the data sheets.
7.4 TIMES OF CALIBRATION 1.
Basic instrument calibration shall be performed using the appropriate calibration block, search units and instrumentation immediately prior to the examination of the welds specified in this procedure.
2.
Instrument vertical linearity checks shall be performed at the beginning of l
cach day of examination in accordance with the technique in the procedure referenced in paragraph 2(7) using an angle beam search unit applied to a j
code calibration block.
T l
FOR.*.i:NES 205 2/80
DOCUMENT NO.
80A0475 11 NUCLEAR ENERGY SERVICES, INC.
A 3.
Examination system calibration checks shall be performed at least at the beginning and at the completion of each four (4) hour period of examination and/or at the change of LevelII examination personnel, equipment, search units, coupler shoes, etc., and at the completion of the examination of each similar series of welds in accordance with Sections 8.3 and 8.6 of this procedure.
7.5 CALIBRATION RESPONSE 7.5.1 Calibration response shall be checked at the primary reference sensitivity level.
7.5.2 Signal response obtained during calibration check shall be within plus or minus 20% of that established during basic instrument calibration.
7.5.3 If any point on the Distance Amplitude Correction (DAC) curve is below the 20% limit, the examiner shall:
1.
Mark rli Weld Data Sheets since previous calibration " void".
2.
Recalibrate examination system.
3.
Reexamine voided areas.
7.5.4 If any point on the DAC curve is above the 20% limit, the examiner shall:
1.
Recalibrate examination system.
2.
Reevaluate all indications recorded since the previous calibration at the corrected sensitivity level.
7.5.5 If any point on the DAC curve has moved horizontally more than 5% of the sweep line from its original settings, the examiner shall:
1.
Correct sweep calibration indication data taken since the previous calibration or calibration check and reexamine the applicable area l
using the corrected sweep.
l 2.
Void any recorded indication data taken since the previous calibration or calibration check and reexamine the applicable area using the corrected sweep.
I T
FORM NES 2C5 2/80
DOCUMENT NO.
80A0475 mur 11 W
NUCLEAR ENERGY SERVICES, INC.
A
- 8. EXAMINATION SYSTEM CALIBRATION 8.1 STRAIGHT BEAM CALIBRATION FOR BASE MATERIAL Straight beam calibration for all base material through which the angle beams will pass shall be performed at a sensitivity level which gives an initial back reflection signal amplitude from the component safe ends of at least 80% FSH.
8.2 STRAIGHT BEAM CALIBRATION FOR WRV Straight beam sweep calibration and Distanc rAmplitude Correction shall be performed as follows for each type of material which will be examined; i.e.,
carbon and carbon; stainless and stainless on the Safe end calibration block.
1.
Adjust the instrument sweep controls so that the examination area is displayed on the CRT screen.
Mark the horizontal screen positions selected for the hole or holes directly on the CRT screen and on the chart on the Calibration Data Sheet.
2.
Position search unit to obtain maximum response from the side drilled (1/4T if T > 1" or 1/2T if T < 1") calibration hole. Adjust sensitivity control to provide a signal amplitude of 80% of FSH and mark location and amplitude on CRT screen.
3.
This is the reference sensitivity level.
Record all sensitivity control settings on the appropriate Calibration Data Sheet.
4.
This completes calibration for thicknesses < 1".
No DAC is necessary.
5.
For weld thicknesses > 1" DAC curve shall be established as follows:
A.
Without changing the sensitivity obtained in (2) abova, position the search unit for maximum response from the 3/4T hole and mark amplitude on the CRT screen.
B.
Plot a DAC curve by connecting the two signal response positions with a continuous line extending over the full examination range.
6.
Upon completion of calibration, ensure that all data and instrument settings are recorded on the Calibration Data Sheet. The examiner (s) shall sign the completed data sheet, noting applicable SNT-TC-1 A levels.
7.
Repeat steps (1) thru (6) for each different weld thickness just prior to examination.
l Y
FORM NES 205 2/80 l
DOCUMENT NO.
80A0475 IN OF 35 PAGE NUCLEAR ENERGY SERVICES, INC.
/s\\
8.3 STRAIGHT BEAM CALIBRATION CHECK Straight beam calibration check as required by paragraph 7.4.3 shall be performed as follows:
1.
Position the search unit on the material side, i.e., carbon or stainless and adjust the sensitivity control settings to match those recorded in paragraph 8.2(6).
2.
Reposition search unit at each respective test hole and observe maximum signal response amplitudes, and horizontal screen positions.
3.
Position the search unit on the other material side of the safe end calibration block and repeat step (2).
4.
See Section 7.5 for signal response requirements during calibration check.
8.4 ANGLE BEAM CALIBRATION NOZZLE SIDE EXAMINATIONS (Where ID conditions have no stainless steel cladding the technique outlined in Section 8.5 shall be utilized.)
1.
Adjust the instrument sweep and delay controls so that the entire calibration presentation for 1/2 vee path is displayed on the CRT (see Figure 10 for the appropriate metal path calibration).
j 2.
From the OD surface of the calibration block, position the search unit to obtain maximum response from the hole which gives the highest amplitude signal. Mjust the sensitivity control to provide a signal amplitude of 80% f ull screen height (FSH) and mark location and amplitude peak on CRT.
3.
Without changing sensitivity, posit.on the search unit respectively on the remaining hole and mark signal location and amplitude on the CRT.
4.
Plot a DAC curve connecting the locations marked on the CRT with a continuous line extended to cover the full examination range (OD to ID).
5.
Repeat steps I through 4 for each different weld thickness just prior l
to examination.
y l
FORM :NES 205 2/80
1 DOCUMENT NO.
80A0475 mur 11 W
NUCLEAR ENERGY SERVICES. INC.
A 6.
Record all data and instrument settings on the Calibration Data Sheet and sign upon completion, noting applicable SNT-TC-1 A certification level (s).
8.5 ANGLE BEAM CALIBRATION SAFE END SIDE EXAMINATIONS (Where ID conditions have stainless steel cladding, the technique outlined in Section 8.4 shall be utilized.)
1.-
Adjust the instrument sweep and delay controls so that the entire calibration presentation for one full vee path is displayed on the CRT (see Figure 10 for the appropriate metal calibration).
2.
From the OD surface of the calibration block, position the search unit to obtain maximum response from the hole which gives the highest amplitude signal. Adjust the sensitivity control to provide a signal amplitude of 80%
FSH and ' ark location and amplitude peak on CRT.
m 3.
Without changing sensitivity, position the search unit respectively on the remaining holes and mark signal location and amplitude on the CRT.
4.
Plot a DAC curve connecting the locations marked on the CRT with a continuous line extended to cover the full examination range. (OD to ID to OD) 5.
Repeat steps I through 4 for each different weld thickness just prior to examination.
6.
Record all data and instrument settings on the Calibration Data Sheet and sign upon completion, noting applicable SNT-TC-1 A certification level (s).
8.6 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 match those recorded for the calibrated reference sensitivity.
2.
Reposition search unit at each respective test hole and observe signal response amplitudes and horizontal screen positions.
3.
See Section 7.5 for signal response requirements during calibration check.
TCRM :NES 2:5 2/80
DOCUMENT NO.
80A0475 au 11 16 OF 35 PAGE NUCLEAR ENERGY SERVICES. INC.
k
- 9. EXAMINATION PROCEDURES 9.1' STRAIGHT BEAM EXAMINATION FOR BASE MATERIAL Straight beam examinations to detect laminar reflectors which might affect the i
I interpretation of angle beam results shall be performed at a sensitivity level giving a back reflection from the component of at least 80% FSH as noted in Section 8.1.
9.2 STRAIGHT AND ANGLE BEAM EXAMINATION OF WRV 9.2.1 All straight and angle beam examination of weld and required volume shall be performed at a scanning sensitivity level, a minimum of 2X (6dB) but no more than 10dB greater than the calibrated reference sensitivity level. All scanning sensitivity levels shall be recorded on the Examination Data Sheets.
9.2.2 For straight beam examinations, a rectilinear scan pattern shall be used.
9.2.3 For angle beam examinations, the search unit shall be swivelled to ensure maximum coverage as it is moved along a rectilinear scan pattern.
9.2.4 For the location and numbers of the welds, refer to the Program Plan.
Examinations shall not be considered complete until all recordable indications have been evaluated.
- 10. EVALUATION CRITERIA 10.1 RECORDING OF INDICATIONS 10.1.1 For straight beam examinations of base metal for laminations, all areas presenting indications equal to or greater than the remaining back reflection shall be recorded on the appropriate data sheet prior to angle beam examination of the weld and required volume.
1.
Each recorded area shall be identified as to distance from surface, length and position relative to the weld datum point.
2.
Pertinent recorded data shall be taken on each parallel scan pass at increments not to exceed that permitted by the 25% overlap of transducer element (width).
f FORM : NES 205 2/80
DOCUMENT NO.
80A0475 m
11 PAGE 17 OF 35 NUCLEAR ENERGY SERVICES. INC.
L 2.
Reposition search unit at each respective test hole and observe signal response amplitudes and horizontal screen positions.
3.
See Section 7.5 for signal response requirements during calibration check.
- 9. EXAMINATION PROCEDURES 9.1 STRAIGHT BEAM EXAMINATION FOR BASE MATERIAL Straight beam examinations to detect laminer reflectors which might affect the interpretation of angle beam results shall be performed at a sensitivity level giving a back reflection from the component of at least 80% FSH as noted in Section 8.1.
9.2 STRAIGHT AND ANGLE BEAM EXAMINATION OF WRV 9.2.1 All straight and angle beam examination of weld and required volume shall be performed at a scanning sensitivity level, a minimum of 2X (6dB) but no more than 10dB greater than the calibrated reference sensitivity level. All scanning sensitivity levels shall be recorded on the Examination Data Sheets.
9.2.2 For straight beam examinations, a rectilinear scan pattern shall be used.
9.2.3 For angle beam examinations, the search unit shall be swivelled to ensure maximum coverage as it is moved along a rectilinear scan pattern.
9.2.4 For the location and numbers of the welds, refer to the Program Plan.
Examinations shall not be considered complete until all recordable indications have been evaluated.
- 10. EVALUATION CRITERIA 10.1 RECORDING OF INDICATIONS 10.1.1 For straight beam examinations of base metal for laminations, all areas presenting indications equal to or greater than the remaining back reflection shall be recorded on the appropriate data sheet prior to angle beam examination of the weld and required vo?.'me.
l 1.
Each recorded area shall be identified a:. to distance from surface, length and position relative to the weld datum point.
2.
Pertinent recorded data shall be taken on each parallel scan pass at increments not to exceed that permitted by the 25% overlap of transducer element (width).
p l
FCW :NES 205 2 E3
DOCUMENT NO.
80A0475 m
11 NUCLEAR ENERGY SERVICES, INC.
=
A 10.1.2 For straight beam examinations of weld and required volume, and angle beam examinations, all nongeometric indications showing a signal amplitude response equal to or greater than 50% of the reference response shall be recorded on the appropriate data sheet at the time of weld examination.
1.
Each recorded nongeometric indication shall be identified as to depth, distance from surface, length, signal amplitude, and location relative to the weld datum point.
2.
Recorded data shall be taken on each parallel scan pass at increments not to exceed that permitted by the 25% overlap of transducer element diameter (width).
3.
The end points of recorded indications shall be determined by 50%
DAC amplitude points.
4.
Planar indications at or near the far surface shall be compared directly with the amplitude obtained from the notch if available.
10.1.3 Geometric indications shall be recorded at one location and noted as geometric caused by thickness change, ID geometry, etc.
10.1.4 Nongeometric Indications for straight beam examinations of weld and required volume and angle beam examinations, all indications showing a signal amplitude response equal to or greater than 50% of the reference response shall be recorded on the appropriate data sheet at the time of examinations.
10.1.5 Each recorded indication shall be identified as to depth, length, signal amplitude, and location relative to the weld datum point.
10.1.6 Indications from all welds shall be recorded in inches upstream or downstream in relation to the flow from the weld center line, and in inches CW or CCW from the datum point.
10.2 EVALUATION OF INDICATIONS 10.2.1 Evaluation of all indications shall be made at the reference sensitivity l
level and in accordance with the requirements of the referenced ASME Boiler and Pressure Vessel Code,Section XI, IS-300. All evaluations shall be performed by a LevelII or LevelIII examiner.
10.2.2 Results of this evaluation shall be reported to the Plant Owner, or his i
l Agent, in accordance with the requirements of the ASME Boiler and l
Pressure Vessel Code,Section XI, IS-600. Disposition of evaluation results shall be made in accordance with the Owner's Plant Procedures.
Y 1
l l
l l
FCTA :NES 205 2/80
DOCUMENT NO.
80A0475
=W NUCLEAR ENERGY SERVICES. INC.
A
- 11. EXAMINATION RECORDS 11.1 CERTIFICATION OF RECORDS The Examiner shall complete and sign all data sheets immediately upon completion of each weld examination. The data sheets may be reviewed by the authorized Code Inspector.
11.2 FILING OF RECORDS NES shall be responsible for submitting to the Plant Owner, or his Agent, a completely documented set of examination records including certification of personnel qualifications with a current eye test report in accordance with SNT-TC-1A.
11.3 PROCEDURE CORRECTIONS AND ADDITIONS 11.3.1 All procedure corrections and/or additions required during the preservice examinations shall be made in accordance with requirements of NES QA Program Plan 80A0448.
11.3.2 The Examiner shall contact LILCO representatives on site to initiate all changes.
All changes shall be documented in the record of revisions section of this procedure.
I l
I l
i I
i iI FORM :NES 205 2/80
3 DOCUMENT NO.
80A0475 35 PAGE OF
W NUCLEAR ENERGY SERVICES. INC.
A LEGEND 1 Perpendicular to Weld
= Parallel to Weld
- Base Material WRV Weld and Required Volume As Far As Geometry +
Permits 1
W + 6" -
=
e 2" ++ W 4-*--
2" ~
d J
/
1.78" 45_L
/
45 1 p
r 0 WRV 0 WRV 0
- 0
- 4
\\~
=
45
=
c
/A
\\
h Carbon Steel 21" 1D Transition Piece Carbon Steel A-508 CL 1 Nozzle A-508 CL 1 l
24-9/16" OD l
Figure 1 - Ultrasonic Examination Procedures for Main Steam (N3) Nozzle to Transition Piece Welds. Cal. Block " Steam" l
l FORM NES205 2/80
U DOCUMENT NO.
80A0475 PAGE 21 OF E
NUCLEAR ENERGY SERVICES. INC.
LEGEND Calibrated
_L Perpendicular to Weld On SS Side of
= Parallel to Weld nypin
W + 3"
=
Stainless Steel Safeend A-182 TP
.,_in y,. in _,
304
(
0I 5M
.813" I
0
=
45.L o
0 */
o 0 WRV f
f /
/
j If o*
0
'10
=
/ / A f
a
/
y 5/16" Carbon Cladding 3-3/16" 1D Steel Nozzle A-508 CL 2 5-7/16" OD l
Figure 2 - Ultrasonic Examination Procedures for Jet Pump Instrumentation (N8) Nozzle to Safeend Welds, Cal. Block "JPl" FORM NES 205 2/80
80A0475 DOCUMENT NO.
35 PAGE OF NUCLEAR ENERGY SERVICES. INC.
A LEGEND L Perpendicular to Weld
= Parallel to Weld H
Calibrated on Cladded CS Side WRV Weld and Required Volume Calibrated on Inconel Side of "CRD" W + 3" r
Inconel Cap W + 3" 7
+-1"-+
- - l'4+W +
r f
P 45 L I
L 45 O
V go,
.75" 0
- WRV
, 45 =l
/
k
///A
/
h Carbon Steel
-7/8" ID Nozzle A-508 CL 2 5-3/8" OD Figure 3 - Ultrasonic Examination Procedures for Control Rod Drive (N9) Nozzle to Cap Weld, Cal. Block "CRD" FORM = NES 205 2/80
6 DOCUMENT NO.
80A0475 m
PAGE 23 OF 35 NUCLEAR ENERGY SERVICES, INC.
A LEGEND
.L Perpendicular to Weld
= Parallel to Weld
- Base Material h
WRV Weld and Required Volume Vessel Wall N
W + 1" u
/
m
" + 1" I
+1/ 2" +- W E+ 1/2S
.28" 7
F 45_L U WRV 0 WRV 0
- 0
- p
\\
45
/ 45
=
=
t Stainless Steel Safeend A-182 TP 304 1-15/I6 1D 2.5" OD Figure 4 - Ultrasonic Examination Procedures for Pressure Differential (N10) Nozzle to Safeend Weld.
Cal. Block "
P" FOR*,1 :NES 205 2,80
O DOCUMENT NO.
80A0475 11 mer PAGE-- 2h OF M
NUCLEAR ENERGY SERVICES. INC.
A LEGEND
.L Perpendicular to Weld
= Parallel to Weld
\\
l l
\\
l l
t
- 0 WRV 30
=
Examine As
, /l5L/
Far As Geometry
/
~
Permits 45
/l 0 l
l
/
WRV 30
=
- 1. 28" 3-11/16 ID 6-1/4" OD c
1 4
/
/
N Closure Head Carbon Steel Nozzle A-508 CL 2 Figure 5 - Ultrasonic Examination Procedures for Closure Head Vent (N7)
Cal. Block " VENT" l
l FORM = NES 205 2/80
O DOCUMENT NO.
80A0475 11 PAGE 26 OF. 35 W
NUCLEAR ENERGY SERVICES. INC.
A LEGEND l_ Perpendicular to Weld
= Parallel to Weld
- Base Material
{ WRV Weld and Required Volume Flang/
e A-508 CL 2 i
i
/
t I
o o
=WRV 300
=
Examine as Far As Geometry Permits 45
/
0: WRV e-
/
30
=
e 1.69" w 5-5/8" 1D 9" OD
/
Closure Head /
T l
/
Nozzle A-508 CL 2 l
Figure 6 - Ultrasonic Examination Procedures for Closure Head Instrumentation (N6) Nozzle to Flange Welds.
Cal. Block " VENT" FORM NES 205 2/80
DOCUMENT NO.
80A0475 mer 2b 35 PAGE OF NUCLEAR ENERGY SERVICES. INC.
SCAN LEGEND 1
Perpendicular to Weld
==
Parallel to Weld Base Material
]
WRV Weld and Required Volume Examine as far as Geometry y
a Permits 1.02 W
l.02 1.02 W
l.02
/
I 45cl WRV-1.02" WRV=
1 I
45
- Oo
(
0**
Safe ends A-508 CL1 Note: Due to Configuration of Safe end i
extend scan path as far as geometry permits FIGURE 7.
ULTRASONIC EXAMINATION PROCEDURE FOR FEEDWATER (N4) NOZZLE TO SAFE END WELDS. CAL BLOCK 131C8523 (FEEDWATER) t l
/2,
/1\\
/4\\
x FORM :NES 205 2/80
DOCUMENT NO.
80A0475 PAGE 27 op 35 NUCLEAR ENERGY SERVICES, INC.
A Calibrated on SS Side of RC-IN
=
Calibrated on Cladded
-a CS Side of RC-IN Carbon Steel W + 4" Nozzle
=
W + 4"
=
=
SS Safeend Piece 1k"
-.- W -
lk" f
5 45 l
j' 04 0 WRV 00*
l 2" 0*
45
/,45 =
=
,/,
/
a 14-3/8" OD IZGDJD 1 Perpendicular to Weld
= Parallel to Weld 0
0 Base Material WRV Weld and Required Volune Figure 8-Ultrasonic Exa.Tdnation Procedure for Recirculation Irdet Nozzle Safeend Weld (Cal. Block RC-IN).
l FORM:NES 2 5 2/80
O DOCUMENT NO.
80A04'T5 PAGE 2
NUCLEAR ENERGY SERVICES, IC-IEGEND L Perpendicular to Weld Parallel to Weld
=
=
of RC-0UP Calibrated on Cladded SS Sichof RC-OUP Carbon Steel W + 6" Nozzle' W + 6"
=
Stainless Steel 2" _W 2".
I L
L
,/
//
l I
45 f
1.844"
.r o
00 W 00 WRV 00*
5
- 0, 45
/ 45
=
=
\\-
I
///I
\\
////n n
29-916" oD l
25-3/8" ID Figure 9 Ultrasonic Exa:nination Procedures for Recirculation Oatlet Nozzle Safeend Welds (Cal. Block RC-OUT) l FORM:NES 205 2/80
DOCUMENT NO.
80A0475 s
PAGE 29 35 gp NUCLEAR ENERGY SERVICES, INC.
METAL PATH CALIBRATION TABLE 1&l/2 VEE SCAN PATH EXAMINATION Metal Path Calibration Material Thickness Range Recommeaded 45 60 70
~ 2.5 "
5 0.5" j0.4" N/A 5.0 "
> 0.5" - $ 1.0"
> O.4" - 5 0.8"
$ 0.5" 10.0"
> 1.0" - $ 2.0"
> 0.8" - $ 1.6"
> 0.5" - < 1.0" 20.0 "
> 2.0" - 5 4.5" 1.6" - $ 3.3"
> 1.0" - 5 2.2" FULL VEE SCAN PATH EXAMINATION Metal Path Calibration Material Thickness Range Recommended 45 60 70 2.5 "
0.8"
_ 0.6"
< 0.4" 5.0 "
> 0.8"
_< 1.7"
> 0.6"
.< l.2"
> 0.4"
_< 0.8" 10.0 "
> 1.7" - 3 3.5"
> 1.2" - 3 2.5"
> 0.8" - j 1.6" 20.0 "
> 3.5" - 5 7.0"
> 2.5" - 3 5.0"
> 1.6" - $ 3.3" 1/2 VEE SCAN PATH EXAMINATION Metal Path Calibration Material Thickness Range Recommended 45 60 70 2.5 "
$1.7"
$1.2" j 0.8" 5.0 "
> !. 7" - $ 3.5"
> 1.2" - 5 2.5"
> 0.8" - 5 1.6" 10.0 "
> 3.5" - $ 7.0"
> 2.5" - 5 5.0"
> 1.6" - 3 3.3" 20.0 "
> 7.0" - $ 14.0"
> 5.0" - 5 10.0"
> 3.3" - j 6.6" INSTRUCTIONS: The Vee Path and the examination angle are given in the specific procedure.
Using the appropriate Vee Path Examination Chart (1/2 Vee, Full Vee, and 1-1/2 Vee Paths) and the appropriate examination angle column, find the thickness range that encompasses the thickness of the material being examined.
FIGURE 10 AA l
FORM NES 205 2/80
DOCUMENT NO.
80A0475 30 35 PAGE op NUCLEAR ENERGY SERVICES, INC.
ANGLE BEAM VERIFICATION BLOCK
~
(
)
100%
R-2
.R-1
/N jl 1
90
/ p
- N 80
/
1 in.
30 \\
45 00
\\
60 70 l
' 2 in. N N.
60 l
O N
s N
50 60 700 40 1
30
/
20 10 1
2 3 4 5
6 7 8 9
10 METAL PATH CALIBRATION FOR A 2.5" CRT PRESENTATION 1-Obtain a maximized indication from the short radius (R-1) reflection surface of the
" Miniature Angle Beam Verification Block" (l" metal path).
2-Using the material calibration control and the delay control, align this signal at CRT position 4.
3-Revolve the search unit around and obtain a maximized indication from the long radius (R-2) reflection surface (2" metal path).
4-Using the material calibration control align this signal at CRT position 8.
5-Repeat steps 1 through 4 until no further adjustments need to be accomplished.
6-The CRT is now calibrated in inches of metal path, (each major division equaling l
1/4 inch).
Make no further adjustments to the sweep range or delay controls.
Figure 11.
DOCUMENT NO.
80A0475 PAGE 31 OF 15 NUCLEAR ENERGY SERVICES. INC.
ANGLE BEAM VERIFICATION BLOCK
[
}
R-2 100%
R-1
'\\
ll I
90
/ f
'l in.
3 N 80 0
N45 60 70 I
l
\\
\\
60 l
l 0
2 in.
N N
600 N
50 l
I 70 40 0
f 30 1
20 10 I
1 2 3 4 5
6 i
8 9 10
</
METAL PATH CALIBRATION 5" CRT PRESENTATION 1-Obtain a maximized indication from the short radius (R-1) reflection surface of the
" Miniature Angle Beam Verification Block" (l" metal path).
2-Using the material calibration control and the delay control, align this signal at CRT position 2.
3-Increase the instrument gain until a secondary echo occurs.
4-Align the secondary signal at CRT position 8.
5-Far reference check the primary signal from the long radius (2").
This signal should peak at CRT position 4.
6-The CRT is now calibrated in inches of metal path, (each major division equaling 1/2 inch).
Make no further adjustments to the sweep range or delay controls.
!'1Elre12.
DOCUMENT NO.
8nAnu7s PAGE
'2 OF
'S NUCLEAR ENERGY SERVICES, INC.
ANGLE BEAM VERIFICATION BLOCK
[
)
R-1 R-2 100%
'N 11 1
l 90 l
s
' /
80 l
l
/ 1 in.00 30 N450 l
l 60 70
\\
60 l
l 0
2 in.
g g
60 N
50 Il 8
70 3
N 20 I
l 10 l
l 1
2 3 4 5 6 7
8 9
10 METAL PATH CALIBRATION 10" PRESENTATION.
1 - Obtain a maximized indication from the long radius (R-2) reflection surface of the
" Miniature Angle Beam Verification Block" (2" metal path).
2 - Using the material calibration, control and the delay control, align this signal at CRT position 2.
3 - Increase the instrument gain until secondary echos occur.
4 - Align the secondary echos shall be aligned at CRT positions 5 and 8.
5 - The CRT is now calibrated in inches of metal path (each major division equaling 1 inch). Make no further adjustments to the sweep range or delay controls.
Figuru 13 EnOM 2NPS 905 P@
DOCUMENT NO.
80A0475 PAGE 33 op 35 NUCLEAR ENERGY SERVICES, INC.
t ANGLE BEAM VERIFICATION BLOCK
[
)
R-2 100%
R-1
'\\
ll I
90 y y g
'l in.
300N 450 80 y
0
\\
60 70 0
2 in.
N 60 l
l N
N N
50 60 70 40 1
30 I
20 I
i 10 k
I N
i i
1 2 3 4 5
6 7 8
9 10 METAL PATH CALIBRATION FOR A 20" CRT PRESENTATION 1-Obtain a maximized indication from the long radius (R-2) reflection surface of the
" Miniature Angle Beam Verification Bloc.k" (2" metal path).
2-Using the material calbiration control and the delay control, align this signal at CRT position 1.
3-Increase the instrument gain until secondary echos occur.
4-Secondary echos shall be aligned at CRT position 2.5 and 4.
5-The CRT is now calibrated in inches of metal path (each major division equaling 2 inches). Make no further adjustments to the sweep range or delay controls.
Figure 14.
I
DOCLHENT NO:
80A0475 b
Plant / Unit Page 3 14 of 35 FIGURE 15 Comp / System CALIBRATION DATA SHEET Data Sheet No.
ISO Loop Procedure No.
Subject:
Rev/ Change No.
TNSTDW4M RETTTNCR RFARPM INTT Calibration Mfg /Model No.:
Jgan Anele:
Mode:
Block No.
Serial No.
Fixturine (if any):
Fabrication No.
Surface Block Temp i
Sweep Length :
Style or Tyne No.
o Sweep Delav :
Size & Shnne?
Comp. Temp F
Thickness Pulse teneth/Damnine:
Freonency CRT Calibrated in Frea.:
Ren. Rate:
Serial Nn/Brnnd?
Filter:
Video:
Jack:
Measured Ancle !
DEC/Cate Suirche Rnnent Enhin Tvnn A inngeh-Mode Select:
Reject:
En,.,1 n n e nrnna.
Gain (e nn v eni -
(FinnT-Counlant Bntch!
gn,n gon c 4,4 v4 e,..
1007 DAC PLOT 0" WRV INSTR. LINEARITY CAL.
O Mne'1 Amplitude 70
== To Weld High Low H i x
Low 1 To Weld 5
I 9
40 2
6 30
-en14hrneinn 3
7 20 Ay4,1 4
8 10 HH HH ll l 11 IIH HH HH HH HH Cire 0
1 2 3 4 5 6 7 8 9 10 AMPT.. POWRnT T.TFFARTTY Initial dB Result Recordable
"^
80
-6 WELD / AREA Yes No Geom INCOMPLETED SCAN (S) 80
-12 40
+6 20
+12 CALIBRATION CHECK 5 TIME Initial Cal.
Intermediate Intermediate Intermediate EXAMINERS 1 Date Level Final Cal.
2 Date Level ADDITIONAL SHEETS? CHECK BOX REVIEWERS 1 Date Continuation Benn Plor 2
Date Sunnierents Monn 3
Date
~
NUCLEAR ENERGY SERVICES, INC.
e NUCLEAR ENERGY SERVICES, INC.
Project No.
Site L Location Date: (Day /Mo/Yr) 9 cation Page of Item Identification o
(_ -[,, f Examiner: TC-1A Level Angle 0
45.L 45=
Attached Cal. Data Sheet f
I
" *I lh/
Thickness Examiner: TC-1A Level scanning
,i n Diameter (nom.)
.mq MP Metal Path W max Distance from ( to S.U. at maximum response.
RBR Remaining Back Reflection W
Distance from weld at 50% of DAC (fwd)
R Cl--
Y--
L Distance from Datum 0 l
W2 Distancefromweld{at 50% of DAC (backward) c, j
i d_i i
l Ind.
FWD BACKWARD L
L RER S.U.
2 W
MAX 507 DAC 50%
DAC W
MP W
MP W
MP 50%
max 50%
amp Loc.
-li'Q'*Q}:
- ~~'
2 No.
DRAW FULL SCALE PLOT llERE:
REVIEWER DATE REVIEWER DATE REVIEWER DATE FIGURE 16 PAGE 35 o f' 35
_.-.-,,,..m
d g NUCLEAR ENERGY SERVICES,INC.
- ' NES DIVISION
'* * / /* ;
SHELTER ACCK ROAD P u 8 f?2 M " '
n#r/e/
e
/ p# ate ISI F M CHANGE AUTHORIZATION Doct=ent Title kV MZZlf lfRSE A8/}/()5 Doccent No.D&l N nev. (')
~
f Tield Change No.
F' C - l Criginator
.$. l.,
[rpr1[$
Tescription of Field Change:
3 'pmn b.l@) td)DelEl 7&lf& Kgl S[0 kfEc!% W $ M.
fMO IIF#LS j
- 6. /
/
s g v/ va A :
.2,p D V 2 /'d/ &/E W -
yeati uun; ).omu,'l/; % /"
i7 b.
n a.
Reason for Change:
j CLui}uM7E df diW /AMM b W Approvals:
Ad4 b$ uT~kAJB.
&!AkN' Q j
n6s Q f /22 f f f utco 3
.v
-.f Distribute to a 1 Controlled Copy holders of affected Docu:: tent.
<;g Note:
A copy of this authorization shall be attached to the affected docu=ent until a ' subsequent revision incorporates the field change.
Fw AM Auf0WADCM WOU57445. WC CowAmy
' f) NUCLEAR ENERGY SERVICES, INC.
.'. '; s NES DIVISION i'
SHELTER ROCK ROAD
~
DANBURY. CONN. 06810 (203) 748-3581
'9 12/30/81 Date ISI FIELD CHANGE AUTHORIZATION Document Title Shoreham PSI Program Plan Document No, 80A0482 Rev.
7 Field Change No.
FC-1 Originator A. Koehl Description of Field Change:
RPV Section Pages 11 & 12 Change Cal. Block from SNPS-7-IR to SNPS-ll-IR for the following cotaponents:
15-316A-r,15-316B-r,15-316C-r and 15-316D-r Pages 15 & 16 Change Cal. Block from SNPS-ll-IR to SNPS-7-IR for the following components:
ll-316A-r and ll-316B-r (see attached marked up sheets)
Reason foi-Change:
Correct typographical error Approvals:
Program Engineering Manag b _ [
~
Project Manager ianrwJ'
/&
O, I
Quality Assurance Manager n2 NJ8. A '))24.4 /~2./70/7/
A/4 CO
&C&/J s/si/r/
Distribute to all Controlled Copy holders of affected Document.
Note: A copy of this authoriration shall be attached to the affected document until a subsequent revision incorporates the field change.
L I
sysiEd <eactor-Pressure-Vessel 1
1 r
^'gg' GFEUt4CE OROWicNo,-02-10--
PROGRAlWPLAN AND SCHEDULE Preser_vice_ Inspection APP; DATE:
Shoreham nev-Pace U
OF _
PHoJECT 11EM COMPOt4ENT No,.
IDENilflCATION COMPOt4ENT CALIDHATIOtt CODE PROCEDURE OtOCK CODE EXAM ZONE DESCalPHON NUMBER (ll appilcable)
CATEGORY METH00 No.
HEMARKS VESSEL NOZZLES 1
15-316A RPV to MS Nozzle (N3A) Weld at 72 Az.
80A0469 SNPS-6 D
UT 11 I
2 15-316A-r MS Nozzle (N3A) Inner Radius 80A0479 SNPS$1R D
UT 11 11 3
14-316 A MS Nozzle (N3A) to Transition Piece 80A0475
, STEAM J-1 UT 11 Weld 80A0473 VT 4
1.*-316 B RPV to MS Nozzle (N3B) Weld at 108 Az.
80A0469 SNPS-6 0
UT 11 W
5 15-316B-r MS Nozzle (N3B) Inner Radius 80A0479 SNPShlR D
UT 11 11 6
14-316B MS Nozzle (N3B) to Transition Piece 80A0475 STEAM J-1 UT 11 Wcld 80A0473 VT 7
15-316C RPV to MS Nozzle (N3C) Weld @ 2M Az.
80A0469 SNPS-6 D
UT 11 Y
8 15-316C-r MS Nozzle (N3C) Inner Radius 80A0479 SNPShlR D
UT 11 11 i
um u
(.
ME D
sysnu..eactor Prcssuro-V:ssel
^'4 r.
FlfEFlt;OE Of11.Wifr,No.J2-10 PROGRAnfPLAN AND SCHEDULE I
Preservice Inspection Ape; pATE:
Shoreham HEV eAGE I2 OF _
PnoJECT ITEM COMPOtiENT COMPot4ENT CALIDRATIOrd CODE Pf oCEDURE DLoCK CODE EXAM ZOt4E No IDENilflCATIOrd OESCHiPilOf4 (UMBER (ll apphcable)
CATEGORY METHOO No.
HEMARKS i
t VESSEL. Nozz!.gis 9
14-316C MS Nozzle (N3C) to Transition Piece 80A0475 STEAM J-l UT 11 Weld 80A0473 VT 10 I)-316D RPV to MS Nozzle (N3D) Weld @ 288'Az.
80A0469 SNPS-6 D
UT 11 J'
11 15-316D-r MS Nozzle (N3D) Inner Radius 80A0479 SNPS{lkIR D
UT II lJ 12 14-316D MS Nozzle (N3D) to Transition Piece 80A0475 STEAM J-1 UT 11 Weld 80A0473 VT 13 4-316 A RPV to FW Nozzle (N4A) Weld @ 45"Az.
80A0469 SNPS-6 0
UT 11 14 4-316 A-r FW Nozzle (N4A) Inner Radius 80A0479 SNPS-7-IR D
UT 11 80A0472 PT 15 2-316 A FW Nozzle (N4A) to Old Transition 80A0475 SNPS-FW-1 3-1 UT 11 Piece Weld 80A0473 VT 16 FW-45 FW Nozzle (N4A) Old Transition Flece 80A0475 SNPS-FW-2 3-1 UT 11 to New Transition Piece Weld 80A0473 wTF
systEp'neactor-Pressure--Vessel QM A
^3 rarEs~at4CE DRAM $Noc02-1-1 PflOGRATPLAN AND SCHEDULE P4eservice.Inspectica APP:
DATE:
Shoreham REV PAGE IO &
PHoJECT liEM COMPONENT COMPOtJENT CAUDRATION CODE P,1, IDEt{TitlCATION PHOCEDORE BLOCK CODE EXAM ZOt4E DESCRIP1 TON fJUuSER (It appl 6catdel CATEGORY LETHOO No.
DEMADMS VliSSEL NOZZLES L
f i
19-314 A RPV tg JPl Nozzle (NBA) Weld 80A0469 SNPS-7A p
UT 11
@ 105 Az.
2 19-314 A-r JPl Nozzle (NSA) Inner Radius
~80A0479 SNPS-1.4-IR D UT 11 3
10-303 A JPI Nozzle (N8A) to Safe-end Weld 80A0475 JPl F
19-314B RP to JPl Nozzle (N8B) Weld 80A0469 SNPS-7K D
UT 11 s
@ 285 Az.
5 19-314 B-r JPl Nozzle (N8B) Inner Radius 80A0479 SNPS-1.4-lR D UT II 6
10-303B JPI Nozzle (N8B) to Safe-end Weld 80A0475 JPl F
I l-316 A RPV CS Nozzle (NSA) Weld @ 90 Az.
80A0469 SNPS-6 D
UT 11 f
8 I l-316A-r CS Nozzle (NSA) Inner Radius 80A0479 SNPShlR D
UT 11 l
g S
EM:
J
^'g,
React 0FPreSS'Ure vessel No. 1 PROGRAM ~ PLAN AND SCHEDULE REFERENCE DRAWit0 Preservice-Inspection APP:
DATE:
shoreham PROJECT REV PAGE 16 y_
ITEM COMPONENT COMPONENT CALIBRATION CODE to.
IDENTIFICATIOt4 PROCEDURE DLOCK CODE EXAM ZONE DESCR1PIlON NUMBER lit applicable)
CATEGOnY METHOO to REMARKS VESSEL NOZZl.ES 9
CS-I A Core Spray Nozzle (N5A) 80A0475 CS-1-1 A F
UT 11 to Safe-end Piece Weld 80A0472 PT 80A0473 VT 10 CS-2A Core Spray Nozzle (N5A) Safe-end 80A0475 CS-2-2A F
UT to Transillon Piece Weld 80A0472 PT 80A0473 YT 11 l l-316B RPV to CS Nozzle (N5B) Weld @ 270 Az.
80A0469 SNPS-6 D
UT 11 9/
12 I l-316B-r CS Nozzle (N5B) Inner Radius 80A0479 SNPShlR D
UT 7
13 CS-1B-Core Spray Nozzle (N5B) 80A0475 CS-1-1B F
UT 11 to Safe-end Piece Weld 80A0472 PT 80A0473 VT 14 CS-2B Core Spray Nozzle (N5B) Safe-end 80A0475 CS-2-2B F
UT 11 to Transition Piece Weld 80A0472 PT 80A0473 VT 15 15-315 RPV tg CRD Return Nozzle (N9) Weld 80A0469 SNPS-6 0
UT 11
@ 146 Az.
16 15-315-r CRD Return Nozzle (N9) Inner Radius 80A0479 SNPS-4.5-IR D
UT II
r LGsFMW LK@.
REV.
NUCLEAR ENERGY
/2 // / F/
SERVICES. lNC.
I Date '
ISI FTan CHANGE AUTHORIZATION kassaamca hemow buToe,arso G ~,n s.on;s % ~ P a m a Document Title R m e ve cm _ WJ et.6-Document No. fcA44 37 Rev O
Field, mange No.
FC-I originator EYme Cs u serv Description of Field Change:
' Po.
C 2, a~c.a G
Taas. t 6, vuosa s=4 cc~,eam Y "re c - t-3cso, c>=.c4 ica ( 7os rc> 4cs e ssa ecs.tenve<-Y.
7 Tasut iGb, uncsa even cavearea X a u3eco 4-2 cst 5, owwe ass. 63 ro 355a.
'A >>pe.m os v A C.wnruc.w IU "TMl% 9 AC= E.
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