ML18026A227
| ML18026A227 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/19/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| PLA-813, NUDOCS 8105220071 | |
| Download: ML18026A227 (169) | |
Text
4. The original exclusion Size, calculated per General Electric specification utilizing on-site power, is consistent with other BNR facilities. Exclusion size calculations have been confirmed using plant specific data by both GE and Bechtel.
The following provides a partial response to FSAR Question 121.14, 15, and 16. Additional information or revision may be required following completion of SSES 41 preservice examinations.
121.14 A. Attachment gl provides a table compiled in accordance with ASME Section XI Tables IWB-2600 and IWC-2600. Only the categories applicable to SSES gl have been listed. Where full compliance to the requirements of the governing code edition and addenda were considered impractical, requests for relief are included with this submittal, and are so noted on the table.
B. Relief requests for pressure retaining welds in the reactor pressure vessel will be provided by June 15, 1981; C. 100K volumetric examination has been performed on Class 1 and 2 vessel and piping system welds, including ~q inch or less nominal wall thickness. Examintions have been performed on SSES Nl including 6 inch schedule 40 piping having a nominal wall thickness of 0. 280 inches.
D. Relief Request Number 4, 5, and 6 include the specific information requested.
E. The reactor support skirt -to reactor vessel weld (Category B-H) has been examined volumetrically using manual ultrasonic techniques. The examination volume includes the welds to the vessel and the base metal beneath the weld zone and along the support attachment member for a distance of two (2) support thicknesses.
The requirements for ASME Category B-K-1 have been for PSI to be compliant with the 1977 edition to 'pgraded the Summer 1978 addenda of ASME Section XI. (See Relief Request g3f. A surface examination to the extent shown in Figures IWB-2500-13, IWB-2500-14, and IWB-2500-15 will be performed.
The requirements for Class 2 bolting. examinations have been upgraded to meet the requirements of the 1977 edition of ASME Section XI to the Summer 1978 addenda, (See Relief Request N2). In accordance with Table IWC-2500-1, examination of bolting under 2" in diameter is not'required.
I 121 15 1
Copies of, the piping and instrumentation diagrams for the Class 2 systems referenced have been included for review.
These "scoping" documents have been cbded to indicated appropriate system classifications, ASME Section XI boundaries, and areas where Code allowable exemptions per paragraphs IWB-1220 and IWC-1220 have been taken.
The scoping, piping and instrumentation diagrams have been included for your review and indicate systems and line sizes exempted from preserviceexamination based on para-graph IWB-1220(b) (1) utilizing"normal make-up systems."
Piping 2" and under and 3" and under, below a'nd above normal reactor water level, respectively, have been exempted from examination based on the referenced paragraph.
PP&L believes that the definition as stated in the Code, 1974 Edition to Summer 1975 Addenda is contradictory for the SSES Ql boiling water reactor; however, the intent of the Code to exempt such small pipe from examination has been technically met based on the following-
- l. During normal operation of SSESgl start-up, hot standby, operation, and cool down Reactor coolant inventory is maintained utilizing off-site power. Systems powered on on-site power, utilizing the emergency diesel generators are ECCS systems and are not considered normal operation.
- 2. General Design Criteria 33 defines the reactor coolant make-up system as follows A system to supply ~
reactor coolant make-up for protection against small breaks in the reactor coolant pressure boundary shall be provided. The system safety function shall be to assure that specified acceptable fuel design limits are not exceeded as a result of reactor coolant loss due to leakage from the reactor coolant pressure boundary and rupture of small piping or other small components which are part of the boundary. The system shall be designed to assure that for onsite electric power system. operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be
- accomplished using the piping, pumps, and valves used to maintain coolant inventory during normal reactor operation.
The SSES Pl systems meet GDC 33.
- 3. Should the utilization of "on-site" power be the major criteria for satisfying this exemption, both the RCIC and the HPCI systems may be used. HPCI and RCIC, with the exception of pumping capacity, are identical high pressure systems (SSES FSAR 5.4,6).. Both start on low water level, stop at high water level and restart again on low. water level. Both automatically transfer from the condensate storage tank to the suppression pool for suction and provide a closed loop of make-up from the suppression pool to the vessel through the leak to the suppression pool. At a maximum pressure of 1010 psig, 5600 gpm make-up is available to the reactor vessel, adequately allowing for the 2" and 3" exemption size.
EXAMINATION AND INSPECTION (CLASS 1)
COMPONENTS, PARTS, HETHOD OF EXAHINATION AND REMARKS ITEH EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD REl1ARKS NO. TABLE IWB 2500 TO BE EXAMINED
- REACTOR VESSEL-81.1 8-A Pressure-retaining welds Longitudinal and circumferential Volumetric (7)
~
in reactor vessel beltline shell welds meridional and region circumferential head welds vessel-to-flange and head-to-flange circumferential welds 81.4 8-D Full penetration welds of Primary nozzle-to-vessel welds Volumetric (7) nozzle in vessel and nozzle inside radiused section 81.5 8-E Pressure-retaining partial Vessel penetration, including Visual (IWA-5000) (7) penetration welds in control rod drive and vessels instrumentation penetration 81.6 8-F Pressure-retaining dissimilar Nozzle-to-safe end welds Volumetric (7) metal welds and surface 81.7 8-G-1 Pressure-retaining Nuts Surface (7) bolting greater than 2 inches in diameter 81.8 8-G-1 Pressure-retaining Pressure-Retaining bolts and Volumetric and (7) bolting greater than' s tuds surface inches in diameter 81.9 8-G-1 Pressure-retaining bolting Ligaments between threaded stud- 'olumetric (7) greater than 2 inches in holes diameter 81.10 8-G-1 Pressure-retaining bolting, Closure washers, bushings Visual (7) greater than 2 inches in diameter
'1. Numbers listed desigrhte applicable relief request.
Page l,of 8, REVISION 0
EXAMINATION AND INSPECTION (CONT'D)
(CLASS 1)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS MET1IOD REMARKS NO. TABIE IWB - 2500 TO BE EXAMINED Bl.ll 8-G-2 Pressure-retaining bolting, Pressure-retaining bolting Visual (7) smaller than or equal to 2 inches in diameter 81.12 8-H Vessel supports Integrally welded vessel Volumetric (7) supports 81.13 8-I-1 Interior clad surface of Closure head cladding 1) Visual and (7) reactor vessel surface or
- 2) Volumetric 81.14 8-I-1 Interior clad surface of Vessel cladding Visual (7) reactor vessel 81.15 8-N-1 Interior of reactor vessel Vessel interior 'isual (7) 81.16 8-N-2 Integrally welded core support Interior attachments and core Visual (7) structures and interior support structures attachments to reactor vessel 81.18 8-0 Pressure-retaining welds in Control rod drive housings Volumetric (7)
'ontrol rod drive housings 81.19 . 8-P Components exempted from Exempted components Visual (IWA-5000) (7) examination by IWB-1220
-PIPING PRESSURE BOUNDARY-84.1 8-F Pressure-retaining dissimilar Safe-end to piping welds and Volumetric metal welds safe-end in branch piping welds 84.2 8-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric and (2) .
greater than 2 inches in in place surface-diameter Page 2 of 8, REVISION 0
EXAMINATION AND INSPECTION (CONT'D)
(CIASS 1)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD REMARKS NO. TABLE IWB - 2500 TO BE EXAMINED 8-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric and greater than .2 inches in when removed surface
. diameter (2)'4.4 8-G-2 Pressure-retaining bolting, Pressure-Retaining bolting Visual (2) smaller than or equal to 2 inches in diameter 84.5 8-J Pressure-retaining welds Circumferential and longitudinal Volumetric in piping piping welds 0
84.6 8-J Pressure-retaining welds Branch pipe connection welds Volumetric in piping exceeding six inches in diameter 84.7 8-J Pressure-retaining welds 'in branch pipe connection welds six Surface inches diameter and smaller 84.8 8-J Pressure-retaining welds Socket welds Surface piping 84.9 8-K-1 Support members for piping, Integrally welded supports Volumetric -(3) valves and pumps 84.10 8-K-2 Support components for Support components Visual piping, valves and pumps 84.11 8-P Components exempted from Exempted components Visual (IWA-5000) examination by IWB-1220 Page 3 of 8, REVISION 0
EXAMINATION AND INSPECTION (CONT'D)
(CLASS 1)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD REMARKS NO. TABLE IWB 2500 TO BE EXAMINED PUMP PRESSURE BOUNDARY-85.1 B-G-l Pressure-retaining bolting Pressure-retaining bolting, Volumetric (2) greater than 2 inches in in place diameter 85.2 8-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric and (2) greater than 2 inches in when removed surface diameter 85.3 8-G-2 Pressure-retaining bolting, Pressure-retaining bolting Visual (2) smaller than or equal to 2 inches in diameter 85.4 8-K-1 Support members for piping, Integrally welded supports Volumetric (3) valves and pumps 85.5 8-K-2 Support components for piping, Support components Visual valves and pumps 85.6 8-L-1 Pressure-retaining welds in Pump casing welds Volumetric pump cases 85.7 B-I,-2 Pump casings Pump casings Visual 85.8 8-P Components exempted from Exempted components Visual (IWA-5000) examination by IWB-1220
- VALVE PRESSURE BOUNDARY 86.1 8-G-1 Pressure-retaining bolting Pressure-retaining bolts and Volumetric and (2) greater than 2 inches in studs surface diameter Page 4 of 8, REVISION 0
EXAMINATION AND INSPECTION (CONT'D)
(CLASS 1)
ITEH EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD NO. TABLE IWB - 2500 TO BE EXAMINED 86.2 8-G-1 Pressure-retaining bolting Pressure-retaining bolting Visual greater than 2 inches in
~
diameter 86.3 8-G-2 Pressure-retaining bolting, Pressure-retaining bolting Visual smaller than or equal to 2 inches in diameter 86.4 8-K-1 Support members for piping, Integrally welded supports Volumetric valves and pumps 86.5 8-K-2 Support cog>ponents for piping, Support components Visual valves and pumps 86.6 8-H-1 Pressure-retaining welds in Valve-body welds 0
Volumetric valve bodies 86.7 8-H-2 Valve bodies Valve bodies Visual
'6.8 8-P Components exempted from Exempted components Visual (IWA-5000) examination by IWB-1220 RP: pd 19-Q Page 5 of 8, REVISION 0
0 EXAHINATION AND INSPECTION (CLASS 2)
(CONr'D)
ITEH EXAHINATION CATEGORY COHPONENTS'ND PARTS HETHOD NO. TABLE IWC-2520 TO BE EXAHINED PRESSURE VESSELS C1.1 C-A Pressure-retaining welds Circumferential butt welds Volumetric in pressure vessels C1.2 C-B Pressure-retaining nozzle Nozzle-to-vessel welds Volumetric welds in vessel C1.3 C-C Integrally welded support Integrally-welded supports Surface attachments to vessel Cl.4 C-D Pressure-retaining bolting Pressure-retaining bolting Visual and either exceeding 1 inch diameter surface or Volumetric PIPING C2.1 C-F Pressure-retaining welds in Circumferential butt welds Volumetric ., (1) (4) (5) (6) piping, pumps and valves in system which circulate reac-tor coolant C2.1 C-G Pressure-retaining welds in Circumferential butt welds Volumetric (1) (4) (5) (6)
'iping, pumps and valves in system which circulate other than reactor coolant C2.2 C-F Pressure-retaining welds in Longitudinal weld joints in Volumetric (1)(4)(5)(6) piping, pumps and valves in fi.ttings system which circulate reactor coolant C2.2 C-G Pressure-retaining welds in Longitudinal weld joints in Volumetric (1) (4) (5) (6) piping, pumps .and valves in fittings system which circulate other than reactor coolant Page 6 of 8, REVISION 0
EXAMINATION AND INSPECTION (CLASS 2)
(CONT'D)
ITEM EXAMINATION CATEGORY COMPONENTS'ND PARTS METHOD NO. TABLE IWC-2520 TO BE EXAMINED C2.3 C-F Pressure-retaining welds in Branch pipe-to-pipe weld joints Volumetric (I)(4)(5)(6) piping, pumps'nd valves in system which circulate reactor coolant C2.3 C-G Pressure-retaining welds Branch pipe-to-pipe weld joints Volumetric (1) (4) (5) (6) in piping, pumps and valves in system which circulate other than reactor coolant C2.4 C-D Pressure-retaining bolting Pressure-retaining bolting Visual and (2) exceeding li'inch diameter either surface or volumetric.
C2.5 C-E-1 Support members for piping Integrally-welded supports Surface (3) valves and pumps C2.6 C-E-2 Support components for Support components Visual piping valves and pumps
- PE1PS-C3. I C-F Pressure-retaining welds casing welds Volumetric in piping, pumps and valves coolant'ump in systems which circulate reactor C3 1 C-G Pressure-retaining welds Pump casipg weld Volumetric in piping, and valves in systems which circulate other than reactor coolant C3.2 C-D Pressure-retaining bolting Pressure-retaining bolting Visual and ~
(2) exceeding 1 inch in diameter either surface or volumetric Page 7 of 8, REVISION 0
EXANINATION AND INSPECTION (CLASS 2)
(CONT'D)
ITEH EKV1INATION CATEGORY COHPONENTS'ND ..PARTS HETHOD NO. TABLE IWC-2520 TO BE EXAllINED C3.3 C-E-1 Support members for piping Integrally-welded supports Surface valves and pumps C3.4 C-E-2 Support components for Support components Visual piping valves and pumps
- VALVES C4.1 C-F Pressure-retaining welds Valve body welds Volumetric in piping, pumps and valves in systems which circulate reactor coolant C4.1 C-G Pressure-retaining welds in Valve body welds Volumetric piping, pumps and valves in systems which circulate other than reactor'coolant C4.2 C-D Pressure-retaining bolting Pressure-retaining bolting Visual and exceeding 1 inch in diameter either surface volumetric C4.3 C-E-1 Support members for piping Integrally-welded supports Surface valves and pumps C4.4 C-E-2 Support components for. Support components Visual piping valves and pumps RF:pd 19-Q Page 8 of 8, REVISION 0
PRE-SERVICE INSPECTION RELIEF REQUEST 81 I. IDENTIFICATION OF COMPONENTS:
All components in Class 1 and Class 2 piping systems requiring ultrasonic examination as the method of examination.
II. CODE RE UIREMENT:
The preservice inspection program for Susquehanna Ql was prepared in accordance with Section XI of the ASME Boiler and Pressure Vessel. Code, 1974 Edition to the Summer 1975. This Edition and Addenda does not specifically address volumetric examination of welds in piping systems but references the pro-visions of Article 5 of ASME Section V.
III. BASIS FOR RELIEF:
Relief is requested from utilizing the provisions of ASME Section V, Article. 5, from the referencing code edition and addenda;in lieu of this requirement, PPGL proposes to use Appendix III, "Ultrasonic Examination Method for Class 1 and 2 piping systems made from Ferritic Steels" from the Winter 1975 Addenda. I'-
Rev. 0 5/15/81
IV. JUSTIFICATION:
Appendix III, 1977 Edition to the Summer 1978 Addenda has been accepted for use by incorporation of this edition and addenda into 10 CFR 50.55a. Appendix III, Winter 1975 Addenda closely parallels the later Code except that the required examina-tion volume is more conservative in the Winter '75 Addenda (i.e.,
Figure IWB-3514. 1 (a) of Winter '5 versus Figure IWB-2500-8 of the 1977 Edition).
V. ALTERNATE PROVISIONS:
Appendix III of ASME Winter 1975 Addenda ultrasonic examination.
will be used for piping system Rev. 0 5/15/81
RELIEF RE UEST g2 I. IDENTIFICATION OF COMPONENTS:
All Class 1 and Class 2 bolting in piping, pumps,.and valves.'I.
CODE RE UIREMENTS:
ASME Section XI, 1974 Edition to the Summer 1975 Addenda requires the following examinations be performed:
ITEM NUMBER CATEGORY
'OMPONENT EXAMINATION METHOD B4.2, B5.1, Pressure retaining bolting, Volumetric B6.1 B-G-1 2 inches and larger, in place B4.3, B5.2, Pressure retaining bolting, Volumetric and B6.2 B-G-1 2 inches and larger, when Surface.
removed.
B4. 4, B5. 3, Pressure retaining bolting, Visual B6.3 B-G-2 smaller than 2 inches.
C1.4, C2.4, CD Pressure retaining bolting Visual and C3.2, C4.2 exceeding 1 inch either surface or volumetric These examinations must be performed completely as a preservice examination requirement prior to initial plant start-up.
Rev. 0 5/15/81
III. BASIS FOR RELIEF:
PPGL requests relief from the examination requirements of ASME Section XI 1974 Edition to Summer 1975 Addenda; examinations shall be performed in accordance with the more current requirements of ASME Section XI 1977 Edition to Summer 1978 Addenda as follows:
ITEM EXAMINATION COMPONENT METHOD NUMBER CATEGORY B6.150, B6.180, Pressure retaining bolting B6.210 B-G-1 larger than 2 inches in place Volumetric B6.160, B6.190, Pressure retaining bolting Surface and B6.220 B-G-1 larger than 2 inches, when Volumetric removed.
B6.170, B6.200, B-G-1 Pressure retaining bolting.* Visual VT-1 B6..230
,B7.50, B7.60, B-G-2 Pressure retaining bolting Visual VT-1 B7.70 2 inches and smaller C4.10, C4.20,
~ ~ C-D Pressure retaining bolting c4.30, C4.40 exceeding 2 inches Volumetric
- Nuts, bushings, washers, threads, in base material and flange ligaments between threaded stud holes.
Rev. 0 . 5/15/81
IV. JUSTIFICATION:
The justification for upgrading the 1977 Edition to Summer 1978 Addenda of ASME Section XI for piping system bolting eXamination, in lieu of the governing code edition and addenda, is to make the Class 2 requirements more closely parallel Class 1 requirements. It is impractical to inspect Class 2 components more stringently than Class 1 components and presents no adverse affect on the integrity of the component or upon overall plant safety.
V. ALTERNATE PROVISIONS:
The requirements of ASME Section XI 1977 Edition to the Summer 1978 Addenda will be used.
Rev. 0 5/15/81
RELIEF RE UEST g3 I. IDENTIFICATION OF COMPONENTS:
All Class 1 and Class 2 integrally welded support members for piping, pumps, and valves.
II. CODE RE UIREMENT:
Category B-K-1 of ASME Section XI, 1974 Edition to Summer 1975 requires volumetric examination of welds to the pressure-retaining boundary and the base metal beneath the weld zone and along the support attachment, member for a distance of two support thicknesses.
Category C-E-1 of ASME Section XI, 1974 Edition to Summer 1975, requires surface examination of welds to the pressure-retaining boundary and the base metal beneath the weld zone and along the support attachment member for a distance of two support thicknesses.
These examinations must be performed completely as a preservice examination requirement prior to initial plant start-up.
Rev. 0 5/15/81
III. BASIS FOR RELIEF:
PP&L requests relief from the examination requirements of ASME Section XI 1974 Edition to Summer 1975 Addenda; examinations shall'e performed in. accordance with the more current requirements of ASME Section XI 1977 Edition to Summer 1978 Addenda as follows:
ITEM EXAMINATION COMPONENT METHOD TEST NUMBER CATEGORY REQUIREMENTS B4.9. B6.5 B-K-1 Integrally welded . Volumetric Table support attachments or Surface* IWB-2500-1 C3.10, C3.40, Integrally welded Surface** Table C3.70, C-E-1 support attachments IWC-2500-1 C3.100
- See Figures IWB-2500-13, 14, 15.
- See Figure IWC-2520-5.
R ev'. 0 5/15/81
IV. JUSTIFICATION:
The justification for requesting relief from the governing ASME Code Edition and Addenda and upgrading to the requirements of ASME Section XI 1977 Edition to Summer 1978 are as follows:
1} The weld geometries involved make a meaningful ultrasoni'c examination, with full coverage of the weld and required volume, questionable.
- 2) Surface examination of the weld and required surrounding base material is a more reliable and sensitive examination for detecting defects in these welds.
- 3) Upgrading makesSection XI examination requirements more consistent with Section III construction requirements and therefore, eliminates additional surface preparation and conflict between the Codes.
Rev. 0 5/15/81
V. ALTERNATE PROVISIONS:
The requirements of ASME Section XI 1977 Edition to the Summer 1978 Addenda will be used.
e P
Rev. 0 5/15/81
RELIEF RE UEST ¹4 I. IDENTIFICATION OF COMPONENTS:
Class 1, Category BJ, pressure retaining welds in piping.
Class 2, Category CF and CG pressure retaining welds in piping.
II. CODE RE UIREMENT:
Category BJ Table IWB-2600, Item Numbers B4.5, B4.6, B4.7 of the ASME Code, 1974 Edition to Summer 1975 Addenda requires volumetric examination of 100%* of circumferential welds, longi-tudinal welds, and branch connections be performed completely as a preservice examination requirements prior to initial plant start-up.
Category CF Table IWC-2600, Item Numbers C2.1, C2.2, C2.3 of the ASME Code, 1974 Edition to Summer 1975 Addenda requires volumetric examination of 100% and 50%*, respectively, of circum-ferential discontinuity welds, longitudinal welds, and branch connection welds be performed completely as .a preservice examination requirement prior to initial plant start-up.
ASME Appendix III, Winter 1975 Addenda, requires an angle beam examination of the weld and required volume (the lesser of
~qt or 1") be perfomred scanning both normal and parallel to the weld.
III. BASXS FOR RELXEF:
Relief is required from the ASME Section XI examination require-ments on the basis of partial'inaccessibility of the weld and required volume due to plant design.
Rev,. 0 5/15/81
WELD NATURE OF OF SCAN NUMBER'ODE
%%d IDENTIFICATION CATEGORY AND SYSTEM CONFIGURATION OBSTRUCTION OBSTR "~( TED ITEM NUMBER (APPROXIMATE)
DBB-114-1-9E CF HPCI Pipe to Cap Two (2)
C2.1 Weldolets 16'BB-13 5-1-7F CF RHR Pipe to Cap one (1) 8%
C2.1 Weldolet DBB-115-1-5D CF RHR Pipe to Tee One (1) 16%
C2.1 Weldolet DBB-115-1-5G CF Pipe to Cap Three (3)
C2.1 Weldolets 34%
HBB-110-2-3C CF RHR Elbow to Tee Instrumentation 3%
C2.1 Nozzle DLA-104-1-FW1 BJ Feedwater Pipe to Valve Permanent Hanger 50%
B4.5 DLA-102-1-FW7 BJ Feedwater Pipe to Valve Permanent Hanger B4.5 HBB-ill-2-3D t Pipe to Elbow Saddle Weld 50'anger CF RHR 13%
C2.1 DBB-3.18-1-1A CF Feedwater Sweepolet to Pipe Hanger Lug Attachment C2.3 Weld 6%
Rev. 0 5/15/81
ASME SECTION III EXAMINATION SAFETY IMPACT RT Leak detection systems detect weld leakage, resulting in either manual or automatic isolation of the leak. These lines are not required for normal safe shutdown, alternate safe shutdown methods are available.
RT RT RT RT During normal plant power operation, weld is under approximately 20 feet of hydrostatic head. During normal system operation weld is under a maximum pressure of M5psig.
Leak detection systems can detect leakage during plant power or normal system operation.
Weld can be isolated and alternate cooldown paths are available using redundant RHR loop or main condenser.
RT and PT Reactor coolant pressure 'boundary leak detection system detect weld leakage; plant technical specifications require plant shutdown with unidentified leakage greater than 5 gpm.
RT and PT RT During normal plant operation, weld is not pressurized. During normal system operation (maximum.l65 psig), leakage is detected by leak detection systems. Alternate shutdown cooling path is unaffected and condenser is also available for cooldown.
RT Leak detection system detects significant leakage; containment isolation valves (2) perform weld isolation function. HPCI performs back-up function for RPV water addition for safe shutdown.
Rev. 0 5/15/81
IV. JUSTIFICATION:
The justification for requesting relief from ASME Section XI examination requirements is as follows:
l) The structural integrity. of the piping pressure boundary is not in question. All the affected Class 1 and 2 welds were subject to examination and testing requirements of ASME Section III.
- 2) Welds of similar configuration, welding technique, etc., in the same run of pipe, subject to similar operating pressures and temperatures are accessible for examination and, as such, provide adequate verification, by sampling, of the piping pressure boundary.
- 3) Visual examination of the weld during system pressure testing will be performed to detect for evidence of leakage.
- 4) Overall level of Plant Quality and safety is not affected by incomplete examination of welds.
Rev. 0 5/15/81
V. ALTERNATE PROVISIONS:
A supplemental surface examination of the Class 2 welds l
will be performed for preservice examination; Class welds III have received surface examination to satisfy ASME Section retesting at this time is unnecessary.
Based on the most current accepted Edition and Addenda of ASME Section XI ('77 Edition to Summer '78), a surface examination of the welds will be required during subsequent inservice inspections, and will be more meaningful at that time.
Rev. 0 5/15/81
RELIEF RE UEST P75 I. IDENTIFICATION OF COMPONENTS:
Class 1, Category BJ, pressure retaining welds in piping.
Class 2, Category CF and CG pressure retaining welds in piping.
II. CODE RE UIREMENT:
Category BJ Table IWB-2600, Item Numbers B4.5, B4.6, B4.7 of the ASME Code, 1974 Edition to Summer 1975 Addenda requires volumetric examination of 100%* of circumferential welds, longi-tudinal welds, and branch connections be performed completely as a preservice examination requirement prior to initial plant start-up.
Category CF Table IWC-2600, Item Numbers C2.1, C2.2, C2.3 of th4 ASME Code, 1974 Edition to Summer 1975 Addenda requires volumetric examination of 100% and 50%*, respectively, of circum-ferential discontinuity welds, longitudinal welds, and branch
=
connection welds be performed completely as a preservice examina-tion requirement prior to initial plant start-.up.
- excluding those exempt per IWB.-1220, IWC-1220..
ASME Appendix III, Winter, 19.75 Addenda, requires an angle beam examination of the. weld and required volume (the lesser of
~qt or 1"). be performed scanning both normal and parallel to the weld.
III. BASIS 'FOR REL'IEF:
Relief is required from the ASME Section XI examination requirements on the basis of complete inaccessibility of the weld and required volume due 'to plant design.
Rev. 0 5/15/81
WELD CODE CATEGORY IDENTIFXCATION AND XTEM NATURE OF OF SCAN NUMBER NUMBER OBSTRUCTED SYSTEM CONFXGURATXON OBSTRUCTXON HBB-101-.3.-FW-7 CG RCIC . Pipe to Sparger -Piping located .Totally C2.1 in the wetwel1 Obstructed HBB-101-1-lA CG RCXC Pipe to reducing C2.1 elbow HBB-101-1-1B CG C2.1 RCIC Pipe to Elbow HBB-101-1-FW6 CG RCXC Flued Head to Pipe C2.1 Rev. 0 5/15/81
ASME SECTION III EXAMINATION SAFETY IMPACT RT Weld is inaccessible and below approximately 20 feet of suppression pool water.
Adequate steam condensation of any leakage is expected. System is not pressurized during power plant operation. During system operation, maximum pressure is less than 25 psig. System is not required for normal shutdown and backed up by either .
HPCI or feedwater, RT Leakage would be detected by wetwell temperature/pressure increase. Upon such signals RCIC system operation could be terminated. RCIC operation is backed up by HPCI or feedwater. Weld is not pressurized during plant power operation. Maximum pressure the weld could. be subjected to is 25 psig.
IV. JUSTIFICATION:
The justification for requesting relief from ASME Section XI examination requirements is as follows:
- 1) The structural integrity of the welds is not in question.
These Class 2 welds were subject to examination and testing requirements of ASME Section III.
- 2) Relief from examination of these welds do not affect overall plant quality or safety.
V. ALTERNATE PROVISIONS:
Welds are inaccessible to all methods of NDE.
Rey. 0 5/15/81
RELIEF RE UEST A6 I. IDENTIFICATXON OF COMPONENTS; Class 1, Category BJ, pressure retaining welds in piping.
Class 2, Category CF and CG pressure retaining welds in piping II. CODE RE UIREMENT:
Category BJ Table IWB-2600, Item Numbers B4.5, B4.6, B4.7 of the ASME Code, 1974 Edition to Summer 1975 Addenda requires volumetric examination of .160%* of circumferential welds, longi-tudinal welds, and branch connections be performed completely as a preservice examination requirement prior to initial plant start-up.
Category CF Table XWC-2600, Item Numbers C2.1, C2.2, C2.3 of the ASME Code, 1974 Edition to.Summer 1975 Addenda requires volumetric examination of 100% and 50%*, respectively of circumferential discontinuity welds, longitudinal welds, and branch connection welds be performed completely as a preservice examination requirement prior to initial plant start-up.
ASME Appendix III, Winter 1975 Addenda, requires an angle beam examination of the weld and required volume (the lesser of
'jt or 1"), be perfomred scanning both normal and parallel to the weld.
III. BASXS FOR RELIEF; Relief is required from the ASME Section XI examination requirements on the basis, of complete inaccessibility of the weld and required, volume due. to geometric configuration.
Rev. 0 5/15/81
WELD CODE CATEGORY IDENTIFICATION AND ITEM NUMBER SYSTEM CONFIGURATION 'NATURE OF % OF SCAN NUMBER OBSTRUCTION OBSTRUCTED DCA-3.10-.1-FW11 BJ RHR . *'Valve to Tee Part Geometry Totally B4.5 DCA-110-2-FW11 BJ RHR Valve to Tee Part Geometry Totally B4.5 DCA-107-1-FW3 BJ Core Spray Valve to Valve Part Geometry Totally B4.5 DCA-107-2-FW7 BJ Core Spray Valve to Valve Part Geometry Totally B4.5 DBB-115-1-FW13. CF C2.1 Valve to Valve Part Geometry Totally GBB-105-1-FW1 CF C2.1 RHR Valve to Reducer Part Geometry Totally Rev. 0 5/15/81
ASME SECTION III EXAMINATION SAFETY IMPACT RT and PT Reactor coolant pressure boundary leak detection Oystem will detect weld leakage.
Technical specifications require plant shutdown with unidentified leakage greater than 5 gpm.
RT and PT RT and PT RT and PT RT During normal plnat operation, welds are not under pressure. During normal system operation, any leakage is detectable by leak detection systems. Plant can be safely cooled down by unaffected RHR loop or main condenser.
RT Rev. 0 5/15/81
IV. JUSTIFICATION:
The justification for requesting relief from ASME Section XI examination requirements is as follows:
l) The structural integrity of the piping pressure boundary is not in question. The subject welds were inspected in examination nd testing requirements of ASME Section III.
accordance'ith
- 2) Other welds in each of the respective systems are accessible and provide a basis for. the integrity of the pressure boundary.
- 3) Visual examination of the weld during system pressure tests will be performed to detect for evidence of leakage.
- 4) Incomplete examination will not impact plant safety.
Rev. 0 5/15/Sl
V. ALTERNATE PROVISIONS:
The structural integrity of all Class l welds covered has been verified by satisfactory completion of all ASME Section III examination. Supplemental examination, such as a surface examination performed at this time is redundant and would not result in increas-ing levels of plnat quality or safety.
Based on the most. current accepted Edition and Addenda of ASME Section XI (.'77 Edition to Summer '78), a surface examination of the welds will be required during inservice inspections, and will be'ore meaningful at that time.
Class 2 piping welds will receive a supplemental surface examintion.
Welds requiring relief from examination requirements due to geometric configuration were evaluated for radiographic examina-tion with specific attention to feasibility during an inservice examination. In most cases, current state-of-the-art prohibited this method. due to configuration and environment. New or improved examination techniques may improve inspectability volumetrically during future inspection. intervals; these techniques will be evaluated for applicability to SSES Ql and implemented as required.
Rev. 0 5/15/81
RELIEF RE UEST 'N7 I. XDENTIFICATION OF COMPONENTS:
Class 1 reactor pressure vessel examinations.
II. CODE RE UIREMENT:
The construction permit for SSES Unit gl was issued on November 2, 1973. In accordance with the requirements set forth by 10 CFR 50.55a, SSES fjl must comply with the requirements of the 1971 Edition of Section XI up to and including the Summer 1972 Addenda, the code edition and addenda in effect six (6) months prior to the issuance of the construction permit.
However,.the preservice inspection program has been upgraded to comply wit& the 1974 edition to the Summer 1975 addenda.
III. BASIS FOR RELIEF:
Relief is requested to allow for the use of the 'Winter. 1975 Addenda for reactor pressure vessel examinations.
Rev. 0 5/15/81
IV. JUSTIPICATION:
Use of the Winter 1975 Edition of ASME Section XI for Reactor pressure vessel examination is justified for the following reasons:
- 1) The major differences =applicable to the reactor pressure vessel between the Summer '75 Addenda and the Winter '75 Addenda.
are:
a) Table IWB-2500 Category BA revision; however, for preservice examination, this change has no impact.
b) Acceptance standards were added and/or changed; however, all changes were more conservative.
c) Changes were made to Appendix I, however, primary changes were made to correct typographical errors or to provide clarification.
d) Personnel qualification requirements were expanded and were made more conservative. (IWA-2300}.
- 2) Areas forming the basis for not accepting the use of Winter '75 addenda are not applicable to SSES 81 RPV preservice examination.
e Rev. 0 5/15/81
'I
V. ALTERNATE PROVISIONS:
ASME Section XI 1974 Edition to the Winter 1975 Addenda will be used for the SSES gl reactor pressure vessel preservice examina-tions.
Rev. 0 5/15/81
8I
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0 ADproved" subnlrt final Pg THIS SUBMITTALCOMPLETELY REPLACES THE PREVIOUS proceed.
dw9.- MI9 may SUBMITTAL(S).
0 Aooroved except as noted.-Male chan9es and submil linet ow9.-Mt9. may proceed
'aS approved.
Q THIS IS AN AOOITION TO SUBMITTAL . THE 4 0 Not Aoproved~olrect and relUbnsrt.
9 0 Aooroval nol reouired:MI9. may oroceed.
PAGES SHOULO BE INSERTEO. ADprovar.or lhrs orawm9 poet nol rcireve suppher from full comDliance with contract or Durchase or ~
Q THIS IS AN ADDENDUM,AN ADDITION,OR A SUPPLEMENT er re ur<ensen~s REVIEWED C l L, M I A JOB NO.
TO SUBMITTAL . AOO 8856 THIS TO THE ABOVE SUBMITTAL AND RETAIN THE TOTAL BY DOCUMENT. Bt Crt TEL
~ l REVISION NO.
3/29/78 e
PAGE~ OF PROCEDURAL REQUI REMEHTS PARAGRAPH (a) Meld type and configurations to be examined, including thickness dimensions, 'materials and product form.............. 1.1 (b) The surface or surfaces from which the examination shall be performed............................................ 7.1.9 S urface-Cond>tron.............................................
~
~ ~
(c) 5. 6. 1 (d) C ouplanttt ~ >1 ~ ~ ~ ~ ~ ~ ~ t ~ ~ 00 ~ ~ ~ 0 ~ ~ ~ ~ ~ 0000 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ P ~ oe ~ ~ ~ 0 ~ ~ ~ 5. 6. 2 (e) Technique (Straight beam, angle beam, contact and/or zmmersxon)..................-.-... ~ - ~ ---- -- - -- ~- - - -
~ ~ ~ ~ 1; i@7. 1."
Angles and modes
'I of wave propagation in the material......- --- 7.1.6&7.
Search unit, type, frequency and transducer sizes............... 5. 5 (h) Special. search units, wedges, shoes, or saddles, and type and length of search unit'able......................
if used,
- 5. 5. 3..2 (i) Ultrasonic.c instrument type(s)....;............................ 5.1 (i) Description of Calibration................'......-----------.- ~ 6.0 II
{k) Directions and extent of scanning............................. 7.0 Data to be recorded and method of recording (Manual or automatic).................................................... 8.0
'(m) Automatic alarm and recording equipment, if used.....;........ N/A (n) Rotating, revolving, or scanning mechanisms, if used.......... H/A (o) Personnel Qualification Requirements.......................... 4.3 Approval of the procedure as required by Raragraph IHA-2120 of Section Xi of the ASME Boiler and Pressure Uessel Code..... Later
~ ~
REVISION NO.
DATE PAGE Of, REVISION STATUS SHEET 3/29/78'ocument
~iItle'LTRASONIC EK&CNATION OF SIMILAR AND DISSIMILAR METAL WELDS FOR SUSQUEHANNA REVIS tONS Page ii Added Changed Rev. 2 to Rev. 3 3/29/78 Changed Rev. 0 to.Rev. 1 >>
I 12/8/76 General revisions 'throughout procedure
- 6. 2..1. 2 Changed Table I Page 9 Amplitude Limits 16-14 to.16-24 Cover Sheet Added Rev. 2 >>
Date 2/9/77
.Changed Rev.', 1 to Rev. 2 '.
2/9/77 Page 2 - Par. 3.3.1 Changed to read '%'eld Identifi-cation and Location Plan as recruired by
.I-6200 of'eference
- 3. 2.1.1."
Page 2 - Par. 3.3. 2 (line 2) changed "Paragraph INA-6200" to "par"-
graph I-6200".
Page 13 - Par. 9.,1'line 2) .
Deleted "at .least Level II" to "Level III "-
page 18 Changed Drawing
REVISION NO.
DATE 3/29/78 PAGE 1 OF 1.0 SCOPE 1.1 The scope of this procedure encompasses the manual, '
pulse echo contact, angle beam ultrasonic examination of similar and dissim. lar metal fabrication arid in-stallation welds and adjacent base material in pipingi fittings, nozzles and components.
1.2 This procedure covers the examination of full penetration welds from 0.20" to 6" in thickness.
1.3 Surface conditioning, pre and post test cleaning and weld identi ication and marking are not within the scope of this procedure.
1.4 The actual marking of the pipe for identification and orientation is not within the scope of this procedure.
- 2. 0 PURPOSE 2.1 The purpose of this procedure is to 'provide definitive instructions 'to the ultrasonic test operator in the performance of'he test,. to document the manner in which the test is performed and the manner in which the data obtained will be recorded.
3.0 AP LICABLE DOCUPANTSp CODES'RAWINGS AND STANDARDS The following .documents form a part of this procedure
~ to the extent specified herein:
3.1 Gene=al Electric Documents 3.1.1 ISE-QAI-300 Personnel Qualification and Certification Program.
3.1.2 GE IPSE DWG. 160-78C-0255 Ultrasonic Test Calibration Standards Safe Ends (Figure 4) ~
3.2 Codes and Standards
REYISION NO.
OATE 3 29 78 PAGE OF 3 '.1 American Society for Mechanical Engineers, Boiler and Pressure Vessel Code, 1974 Edition including Addenda through Winter of 1975.
3.2.1.1 Section XI, Inservice Inspection of Nuclear Power Plants.
3.2.1.2 Article V, Nondestructive Examination.
3.2.2 American Society for Nondestructive Testing 3.2.2.1 SNT-TC-lA, Recommended Practice for Nondestructive Testing Personnel Qualification and Certification, 1975 Edition, with Supplement C.
- 3. 3 Vessel/System. Fabrication Documents Held Identification and Location Plan as required by I-6200 of reference 3.2.1.1.
3.3.2 Vessel/System reference points as required by Appendix III, Supplement 2 of referenc'e 3.2.1.1.
3.3.3 Held Joint Design Drawings.
- 4. 0 ADMINISTRATIVE RZgrJIREMENTS 4.1 This procedure has been prepared in accordance with the requirements o f re ference 3. 2. l. 1, Appendix III.
4.2 As used in this procedure, "shall" indicates mandatory requirements and "should" or "may" indicates re-commended practice.
4.3 Personnel 4.3.1 All personnel performing the ultrasonic
. examinations shall be qualified and ceritfied in accordance with the provisions of re'-
ference 3.1.1 and 3.2.2.1.
REVISION HO.
pATp 3 29 78 PAGE 3 OF 22 4.3.2 Personnel performing the examinations shall be qualified to at least I-T or I and shall perform the. examination under the direction of personnel qualified to at least Level XX,::.
or IXX.
Prior,to performing examinations in accordance with this procedure personnel .shall receive an indoctrination in its contents, the personnel and date of those attending shall be recorded in the site log.
4.4 Documentation
- 4. 4. 1 Calibrations (Instrument and System) shall be documented on the forms shown in Figures 1A and 1B.
- 4. 4. 2'ecordable indications disclosed during the examination shall be documented on the forms shown in Figure 2.
4.4.3 All entries on the forms shall be made in black reproducible ink.
4.4 ' Erasures, obliterations or strike-overs are not.permitted.. Corrections shall be made by single line cross outs, which shall be initialled and dated.
k 4.S Definitions 4.5.1 Xnstrument,Calibration:
Instrument.Calibration is the verification of the amplitude linearity of "he instrument and consists only of the instrument re-sponse to change in gain (calibrated and uncalibrated) settings.
4.5.2 System Calibration:
System. Calibration is. the verification of the performance of the complete instrumentation system including personnel. It includes the establishment of the Distance Amplitude Correction curve and applies to all ele...ents of the system including but not limited to the instrument, cables, transducers, shoes or wedge personnel,,couplant and their coordinated re-sponse to a specific calibration block.
{See Figure 4).
SPECIFICATION NO.
REVISION 'NO.
DATE PAGE OF
~ 22" 5 ' System Calibration check:
System Ca ibration Check is a verification of system response t" assure that drifting, changing of equipment'power supply or other condi ions affecting the validity of the test has not occurred. System Calibration .Checks a e performed. on 'an IIH-2 block or other owner approved portable calibration ~lock.
5.0 . EQUIPMENT 5.1 'he basic equipment. shall be the pulse echo, Branson 301, 303, or equivalent as endorsed by the Level III Examiner. The instrument shall be equipped with a calibrated gain or attenuation control, graduated in units no larger than 2 dB.
The cables shall .be coaxial, in lengths of 4 to 12 feet. Vhen endorsed by the cables of other lengths may be Level III used.
Examiner, The length, type and number of cable shall be documented on the calibration data shee" (Figure lA).
The calibration blocks used to establish the system calibration shall be those (as applicable) shown in reference 3.1.2. (Figure 4)'he 5.4 calibration block used to establish instrument calibration may be\ the IIN-2 block.
5.5 Transducers 5.5.1 The transducers used for instrument calib""ation should be nominal 2.25 MHz, 1" diameter, straight. beam, ceramic, contact transducers.
5.5.2 The transducers used for system calibra-tion, weld and base metal examination shall be nominal 2.25 MEz, 1.4" dia.
1/2" dia,'or 1/2"xl" straight beam, ceramic, contact transducers, of stan-dard, miniature or subminiatu e con-figuration.
i
$ PECit'ICATION No.
REVISION NO.
3/29/78 oaTE
'AGE E OF~,
Contact shoes or wedges shall be used for system calibration, base and weld metal examination. Contact shoes or wedges may be flat or contoured depending .
upon the diameter of the pipe and the transducer s'ze. Shoes or wedges shall not be interchanged without system recalibration.
5.5.3.1 Selection of the size and contour of the shoes or wedges shall be at the discretion of the Level III provided that the provisions of Figure 5 are met.
5.5.3.2 The contact shoes or wedges shall be capable of introducing .
transverse wave sonic energy into the material to be tested at an angle of 45 with a -2o tolerance. For contoured shoes or wedges, this angle shall be verified on the appropriate calibration block,.
references 3.1.2. For flat shoes or wedges,'he angle shall be verified on the IIN-2 calibration block referenced in Paragraph 5.4.
5.5.3.2;1=If part geometry or metallurgical characteris-tic (for austenitic welds) impede effective use of 45o angle beam examination, the angle may be increased or decreased in accordance with the
'appropriate provisions of Paragraph III 3230 and 4410.. The appropriate provisions of Paragraph 5.5.3.2 also apply.
SPECIFICATION NO.
REVISION NO.
DATE 3/29/78 PAGE 6 OF 02 5.5.3.2.2 Other transducers frequencies and shoes of special design may be used in lieu of those specified in the preceding paragraphs.
The use of other transducers, frequencies and shoes shall have the concurrence of the Level III and this concurrence and the design of the transducers, frequencies and shoes shall be documented on the calibration and data sheets. A dimensional sketch shall be included with the final report.
5.6 Couplant and Surface Preparation 5.6.1 The contact surface of the calibration blocks and the hardware undergoing examination shall be clean and free of
.dirt, dust, weld splatter,*loose scale or other material which could interfere with free movement of the transducer or impair transmission of ultrasonic energy into the material. Unacceptable surface conditions shall be referred to the customer for disposition.
5.6.2 Glycerine (with or without added surfactants) or other coupling materials as specified
'in Gene al Electric "Operating Plant Services Material and Processes Manual" ~
shall be used in sufficient quantity to maintain continuous sonic contact. The couplant shall be noted on the calibration data sheet and the examination data sheet.
6.0 CALIBRATION 6.1 General Requirements for Calibration
- 6. 1.1 The surface temperature of the calibration block(s) shall be within 25 F of the component temperature.
REVISION NO.
DATE PAGE OF 22
'eam spread measurements are not required for this procedure.
A calibration check shall be made after any change in power supply, or after any period of instrument inactivity in excess of four (4) hours.
General Requirements for System Calibration.
6.1.4.1 System calibration shall include the complete ultrasonic calibrat'on system, including personnel, search units, shoes or wedges, couplants, cables or ultrasonic instruments.
Any change in the sys em shall .
be cause for recalibration.
6.1,4.2 System Calibrations shall be
-made on the applicable basic calibration block as described in reference 3.1.2. (See Figure 4) .
6.1.4.3 In accordance with the provisions of Paragraph III-3300 of appendix III, reference 3.2.1.1, System Calibration shall consist only of the'onstruction of the Distance Amplitude curve at the Primary Reference Level, and a verification of sweep range linearity on the 2"&4" radiused sections of the IIH-2 block, or from calibration block.
6.1.4.4 System Calibrations shall be made once each day prior to
'he use of the system in each thickness range, provided system calibration checks are made and recorded as specified in Paragraph 6.1.4.5.
C I REVISION NO.
DATE PAGE OF 6.1.4.5 System calibration checks shall .
be made to ve ify instrument sensitivity, and sweep calibra-tion, at the finish of examina-tions in each thickness range, with any change in personnel, after every four hours of in-strument use, when any change in power supply is made and if the instrument has been idle for four hours. System cali-bration checks shall be documented on'the calibration data sheet.
6.1.4.6 If during system recalibration or during a system calibration check any refe enced point has moved on the sweep line by more than 10% of the sweep division reading, the system shall be re-calibrated. If any recordable indications have been observed on the data sheets affected, those data. sheets shall be marged void the system recalibrated, the affected areas reexamined and the "voided" data sheets shall be submitted to the Level Examiner.
III 6.1.4.7 If during system recalibration or during a system calibration check any referenced point'f the DAC curve has changed by more than 20% of its amplitude, all data sheets made since the last calibration or calibration check shall be marked void, the system shall be recalibrated and the affected areas reexamined.
The "voided" data sheets shall be submitted to the Level III.
-. 6.2 Instrument Calibration
- 6. 2. 1'mplitud'e Linearity Check
REVISION NO.
PATE 3/29/78 PAGE OF A longitudinal or angle beam transducer shall be placed on the IIN-2 or other calibration block such that two signals of varying amplitudes may be ob-tained. The search unit position shall be adjusted so that the two signals are of a of two to one.. 'atio The uncalibrated gain control shall be adjusted so that th' larger signal is 80% of Full Screen Height (FSH) and the smaller is at 408 FSH. The search unit may have to be re-positioned to maintain the 2:1 ratio. Nithout moving the search unit, adjust the uncalibrated gain control to successively set the larger signal from 100% to 20$ FSH in 10% increments.
The, smaller indication shall be read at each increment.
The signal amplitude of the smaller signa'1 shall be 504 of the larger 'amplitude within 5%
FSH. Instruments that do not meet, this criteria shall not be'sed.
A longitudinal or angle beam transducer shall be placed on the IIH-2 or other calibration block and a peaked signal amplitude shall be obtained from a hole or notch. The indication shall be brought to 80% FSH with the uncalibrated gain control. Using only the calibrated gain control, the dB changes listed in Table I shall be made and the resulting amplitude compared with the allowable amplitude limits.
The resultant signal shall fall within the amplitude limits.
SPECIFICAT)ON NO.
REVISION NO.
OATE 3/29/78 PAGE OF 22 6.2,1.2 (Continued)
Instruments that do not meet these requirements shall not
.be used. The prc=edure shall be =epeated for 40 and 20% FSH amplitudes and the data recorded on the calibration data sheet.
6.2.'.3 Zn all calib"ations it is important that maximum indications be obtained with the sound beam oriented perpendicular to the axis of the calibration reflector. The center line of the search unit shall be at least 3/4" from the neares" side of the block or pipe. (adoration of the beam into a corner formed by the reflecto and the side of the block may produce a higher amplitude signal at a longer beam path: this beam path shall not be used for calibration.)
Table Initial Amplitude dB Control Amplitude Limi Set of FSH of FSH 80 6 32 - 48 '
80 -12 16 24 40 + 6 64-96 20 +12 64 - 96
- Minus denotes a decrease in amplitude, plus denotes increase 6.3 System Calibration (DAC) 6.3.1 1/2 Vee System Calibration 6.3. 1.1 When the examination is limited to 1/2 Vee path, the DAC shall be established by obtaining.
two signals from the two side drilled holes at 1/4T and 3/4T.
SPECIFICATION NO.
REVISION NO.
OATE 3 29 78
'AGE OF 6.3.1.1 (Cont='nued)
The signal with maximum amplitude shall be adjusted .to 80% Full Screen Height (FSH) and a line drawn between the two maximum signal heights. -The line shall.
be ex"rapolated 1/4T to cover the f. 11 examination thickness.
The primary re.erence level sensitivity shall be then es-tablished by setting the amplitude of the s'gnal from the ID surface notch to the corresponding ampli-tude on the DAC curve.
6.3.2 Full Vee System Cal'bration 6.3.2.1 For calibration using the full Vee Path, the DAC curve shall be constiucted using the signal from the ID su ace notch as the primary reference. The amplitude of this signal shall be acjusted to 80% full screen height. With-out changing the gain control, determine the height and loca-tion of the OD sur ace notch.
Draw a line between the two points. This curve shall be the primary reference level.
7.0 EXAMINATION
- 0. 1. General Requirements or Examination 7.1.1 The rate of scanning shall not exceed 6" per second unless calibration is veri-
~
fied at scanning speed.
7.1.2 Weld identification and location shall be as shown on the weld identification
.plan, reference paragraph 3.3.1.
7.1.3 Reference points fo weld inspection shall be as 'shown in reference paragraph 3.3.2.
SPECIFICATION NO.
r REVISION NO..
PAGE 3 2 9/78 OF ~.
7.1.4 Piping and nozzle weld reference points shall be marked or shall have been marked .:
prior to the initiation of the examination, in accordance wi."h the requirements of reference paragraph 3.3.2.
r 7.1.5 To the maximum extent practicable the area to be examined shall be the the lesser of 1/2T or 1" of adjacent weld,'nd base metal. Conditions which preclude this examination shall be noted on the data sheets.
A 7.1. 6 The search unit and beam angle selected shall be capable of detecting the calibra-tion reflectors, reference paragraph 6.1.4.2, over the required beam path.
A beam angle of 4So should normally be used. Where wall thickness of other geometric considerations impedes effec-tive use of the 4So angle beam examina-tion technique, other angles may be used.
The results of alternate transducers, angles and shoe designs which have been investigated to meet the volumetric requirements shall be documented in examina-'ion Figure 2 or other appropriate .documentation form ~
7.1. Where angle beam is specified in this p-ocedure 7
it mode shall be interpreted as meaning shear of transmission. Angle beam longitudinal wave'ay be used however its use shall .
be noted on both the calibration and data sheets.
7.1.8- Examination scanning shall be performed at, least 2X the evaluation level.
7.1.9 Examination shall be performed from the Outside Surface of the pipe or component.
7.2 Ref lecto s Parallel to the Weld Seam
SPECIFICATION NO.~
3/2 9/7 8 PAGg 13 OF 22.
Examination of the weld and the lesser of 1/2T or 1" of adjacent base metal shall be done by full.Vee Path angle beam examination from one side of the weld or a one-half Vee path from two sides of the weld where practical. When because of geometry or other considerations examination is limited to one-half 'Vee path from one or both sides of the weld, the weld and 1/2" of the base metal on either side of the weld shall be examined by a surface method. The surface examinatio shall be selected by the Level III, performed and documented on the data sheet;.
- 7. 3 Reflectors Transverse to the Weld Seam 7.3.1 The angle beam examination for reflectors oriented transverse to.'the weld seam shall be done on the weld crown on a single scan path by one-half Vee path in two directions along the weld or in one direction when full Vee path used.
7.3.2 Angle beam examination of the base metal on each side of the weld shall be performed in accordance with the appropriate provisions of the preceding paragraph.
- 8. 0 DATA RECORDING
\
k 8.1 All indications equal to or exceeding 50% of the primary reference level when evaluated at 1X sensitivity shall be recorded on the data sheet.
8.2 Method of Recording Data Figure 3 sket:ches the relationship between transducer'ovements (positions
'W1, Wm and W2), weld center (Wo') weld p reference point (Lo) and length of indications (L2 minus Ll).. This attach-ment also contains a sample copy of an examination data sheet. Hypothetical information based on the above sketch has been recorded on it.
SPECIFICATION NO.~EE REVISION NO. 3 3/29/79 Search unit positions Wl and H2 shall be recorded only when the pipe wall thickness exceeds 1" and indications are contained within the weld. Signals caused by geometric changes such as weld crown, mismatch, fit-up ID preparations, etc., shall require recording of Ljg L2 F Hm and the peak signa 1 amp 1 itude The following "transducer positions" and "data to be recorded" information shall be recorded on the Examination Data Sheets for indications which exceed 50 .
percent DAC at the primary reference level (1X):
Transducer Positions Data to be Recorded Hl Distance between (1) Distance from refer the search unit entry centerline (Wp).
point, and the weld
.centerline {Wp) when (2) Indicated metal pat the signal amplitude to reflector distan decreases to 50 per-cent DAC when moving.
towards the weld from Wm-Wm Distance between (1) Distance from refer the search unit entry centerline (Wp).
point and the weld (2) Indicated metal pat centerline (Hp) when reflector distance.
.the signal amplitude (3) Signal amplitude ir, is at maximum. at Primary Referenc W2 - .Distance between (1) Distance from refez the search unit entry centerline (Wp) .
point and the weld centerline {Hp) when (2) Indicated metal pa) the signal amplitude reflector distance, decreased to 50 per-.
cent DAC when moving away from the weld and Hm
SPECIFICATIOH NO I REVISION NO.
DATE PAGE 15 OF 22 8.2.4 All "L" dimension measu"ements shall be taken at 50% 'DAC line (Ll) through the peak signal given by the indication to 50% DAC line (L2) .
8.2.5 Nhen indications have been identified within the weld, the transducer's posi-tions shall be recorded as follows: 1)
The transducer's movement for each data point is perpendicular to the length dimension. 2) The data shall be obtained at 1/2 inch interval along the length of the'eflector for indications less then 2-inches in length. Zn addition the maximum amplitude points shall be checked at, 1/4 inch intervals. 3) For indications greater than 2-inches in length, the data shall be taken at 1-inch intervals;
- 4) The continuity of indications between intervals shall be confirmed.
8.2.6 'he direction of scanning shall be re-corded as follows:
Examination 1: For reflectors parallel to weld for full Vee Path or for.l/2Vee path in the direction of flow.
Examination 2: For R~flectors parallel to weld for 1/2Vee Path, counter to direction or resow. ]Only per-formed when Full Vee Path cannot be performed,.)
Examination 3: Angle beam scan along weld in direction of "V" identification Examination-4: Angle beam scan along weld coun to direction of "V" identificat 8.2.7 All indications exceeding 100% DAC line shall be recorded over and above data taken for 50% DAC line. These indications shall be recorded on separate data sheets as pe paragraphs 8.2.3 and 8.2.4, substituting 100% DAC for 50%
DAC in all cases.
SPEC REVISION NO OATE 3 29 78 PAGE 16 OF 9.0 R VIEN OF DATA 9.1 The recorded data shall be reviewed by an individual certified. to Level III to determine if additional exam'ination and/or evaluation is required.
9.2 .Evaluation of Indicat'ons. Disposition and evalua-tion of indication data shall be as specified by contract with the Customer. Evaluations will be determined in accordance with Section XI, ASHE through Ninter of 75 Addenda.
Al V Vmj&l\ jVUlq OaTE 3 29 7 PAGE OF PIPE UT CALIBRATION DATA SHEET SITE Q/Preoperational g~I.S.X.
SYSTEM CALIBRATXOH'LOCK NO.
PROCEDURE HO . REU. CALIBRATXOH SHEET HO.
DATE COU PLANT XXN-2 BLOCK HO.
EXAKrHER ASNT LEVEL DATA TAKER ASHT LEVEL XHSTRUMEHT MODEL HO. XHSTRUMENT SERIAL NO.
CABLE HO. CABLE TYPE CABLE LEHGTH RAHSDUCER DATA SHOE TYPE STRAIGHT BEAt1 ANGLE BEAM SHOE HO.
SERIAL HO.
IDENTITY SHOE ANGLE FREQUENCY SIZE MODE h
PARALLEL COUPLtQK REFLECTORS ORIENTED or HELD SEAM (Cross Out One)
'O TRANSVERSE XHSTRUPDHT S r TTXHGS:
Start OAC Curve . Uncalibrated Gaia Coarse Sweep'ine 1\
Sweep .
.P Coarse Range Fine Range I
~ ~
Scanning Gaia 50 FIGHT Attenuation (in)
Evaluating Gain Attenuation.(in)
Filter Position
~ ~ Rep Rate 10 Damping 0 2 3 4 5 6 7 8 9 10' Re ject 0 1 3 . 6
. 1A SAMPLE CALIBRATION SHEET
'DATE 3/29/76--
PAGE 18 OF 22 Depth "W" SDI<
Peale. Gain Max. Oor MP 8 IX Amp. Inch or initial Calibrar on Time
".:"."nct2cs Inch FDH Pef Iodic Checks:
1X Last .
Time Valve Doto Shoot .
.1X 3/4 TX
-,,i J.O. .
N/A nt ci~
'/cO.O. ~ 'inal'Checks
!otch N/A
~ ~
.Colibrolionin Depth(O) Q or Melal Poth (MP) C3 Amplitude Linearity Check Control Linearity (Made Daily) (Made Daily)
100%FSH 6 FSH 50'FSH H FSH 80%%dFSH -6db (32-481 SGX
" 40% " ~4 BO%%d
" 12db (16-24) t 80 40 3(65 " o 6db (64;.961 70%%d
" 4!O%%d
" +(2db (64-96(.
6004 ee Equip.'ata -Straight Beam For Linearity Checks ~ r Chocks on Iiy/-2 ill/-2 Block on I/8 SOH for Field Calib.
Transducer Data: 8 For, Chocks Q Max Amp.for Both Nec Serial No. Positions in % Screen Height Angl(r
'eam I/8 SOH Near Far Size Max.
Shoe Ho Cable Ho Amp.
Metol Check Made By: Poth
~ ~ ~
R evievret I by FZG. 1s s~Lz mz.zsmrzoN SHzzT SNT.TC Level
~ ~
REVISION NO..
gATp 3 29 78 PAGE OF ULTRASONIC EXAtQNATION DATA FORM Exam. Form Cal. Form Ho.
SI TE. ~Preoperational ~I.S.I. DATE SYSTEM WELD NO.
ASNT LEVEL DATA TAKER ASHT LEVEL SEARCH'NGLE U.T. PROCEDURE SCAN SEHS: X2= EVALUATION SENS: Xl COUPLANT COMP TEMP EXAMINATIONS Perzorwed Indzcatxon Yes Ho
- l. ANGLE BEAM FOR REFLECTORS PARALLEL TO WELD
- 2. ANGLE BEAM FOR REFLECTORS TRANSVERSE TO WELD (CLOCKWISE AND COUNTER 'CLOCKWISE)
Senchmark or Referenced "0" Location:
Wo EI Inches From Wt Wm w 'OAC IX Metal Path Exam A Sunning Mode fk Remarks Amp.
Ref.
Inches Inches Inches Wm WI Wm s.5.'6 ACCEPTABLE + UNACCEPTABLE + FI GURE 2 PER ASME SECTION XI
~ ~
REVISION PATE 20.
OF 3/29/78'AGE 22 --.= i tV) STAuP TOP DKAD CENTER " Lo FOR CIRCUMFERENTIAL TELOS La LEE o FOR LONG SELD Lg Wg Wg SI No FOR CIRCUMFERENTIAL WELD XYZ
~ ~ ~ ~ ~
Xnches From Vl V XDAC Metal Path Exam Scanning Mode Ref Inches Inches Xnckes Ho ~ 6 Remarks Ll 2.0 2.7 3.6 50 2. 7,3.5 22'2;5
'L 2.0 2.6 3.5. 85 2.6 3.4 . 4.7 L2 23. 0 2.0 3.4 50 . 2.7 4.6 9;5 2.4. 2.7 5.0 2.4 2.7 2.9
- 10. 0. 2.6 2,9 85 2.4 2.8 3.3 L 10. 5 2.4 2.7'0 2.4 2.7 2.9 FIGURE 3
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~ ~
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) 60 78C-0255 4
~ ~ ~Q DATE 3 29/78~
=
2 OF 22 PAGE
~ e ~
i ~
~ ~
E.P.
such that. the distance from Search unit wedge design must be weld center line (Dim. A) is less than the enuy point (EP J to
)ndicated beloved,
~
~ g 7'X 0si3 for 45 deg. (43 deg.)
7'X 1A for 60 deg. (58 deg.) ~
7' 2A7 for 70 deg. (6S deg.)
~ ~
MOTE:
This figure may not apply to austenitic materials.'
FIGURE 5
~ ~
~ o
DOCUMENT NO. 30A277O R EV.
NUCLEAR ENERGY SERVICES, INC.
il PAGE ~~. P ULTRASONIC EXAMINATION GENERAL RE UIREMENTS PENNSYLYANIAPOWER AND LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION UNITS I AND II WI:ONTRCLLI-Dyf Project Application 55 Prepared By Frank T. Carr UT Level III
"" /~/
APP RO VA LS TITLE/DEPT. SIGNATURE'.
DATE UT Level III 3ensen M r. Field 0 erations . F. Carr Pro ect Mana er 3. Hobin A Mana er G..Oberndorfer
Q NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE 2 OF REVISION LO 8 REV.
DATE PAGE DE SC R I PT ION APP ROVAL NO. No, 8)0/79 3 Added Para. 2.7 CRA 996 Para. 5.0 Moved parenthesis 'F F107310 Para. 5.6 Mded "Change of transducers, cables, shoes, batteries and couplants".
Added Para. 6.3 Added last sentence to Para. 6.1 Para. S.1.2 added "as setforth below" Para. S.l.2 (1) deleted "after careful consideration" Para. S.1.2. (2) deleted."in your opinion",
"you believe" Para. 8.1.2. (3) deleted "in your opinion" added "do not record it" 10 Para.'.3.1. chan ed "shalP'o "ma "
added "owner" to third line deleted "Bechtel" from fourth line Para. 8.1.2. chan ed "of reference res onse to "DA( "
Para. S.l.2. (2) changed "of reference level" to "DAC" Para. 8.1.2. (3) deleted "of reference level" Correct Project Title 2 (
. 12/12/79 Added paragraph 5.1,1 CRA 1109 9
De'leted "Opinion" from Paragraph 8.2.1(l) 10 Added last sentence to paragraph S.2.3.
DOCUMENT NO.
REYISION LOG NUCLEAR ENERGY SERVICES, INC. PAGE OF REV. PAGE NQ. DATE NO. DESC R IPT I ON APP R'OVAL 6, 26/80 Para. 2.4 revised to HES Procedure Para. 2. 8, 2. 9, added ref erences Para. 5.1 clarified calibration on blocks or simulator.
Para. 5.2 added new para. to incorporate and clarify the use of metal path and
'enumbered accordingly Para. 5.3.1 chan ed to..."Miniature" 6 Para. 5.3.3 changed"Primary Reference"to "Reference Sensitivit "
Para. 5.4 added note 9 'ara 7.7 chan ed Fi ure 2 to 1 t 'P-Para. 8.1.6 added new ara. Fi ures 1 5 deleted and renumbered remainin Fi s:.
Fi ures 2 3 u dated Added Fi ures 4 5 6 7 8.
CRA 1364
AXSF DOCUMENT NO.
PAGE OF NUCLEAR ENERGY SERVICES, INC.
ULTRASONIC EXAMINATION- GENERAL RE UIREMENTS 1.0 SCOPE 1.1 This procedure details the general requirements for ultrasonic exami-nation of welds and base material.
1.2 These requirements, where referenced, shall be considered a part of a specific ultrasonic procedure. All the requirements shall be complied within a specific procedure, unless otherwise specified'erein
~
stated.
1.3 This procedure cannot be used for ultrasonic examination in itself.
Specific procedures are written for each area of examination and are to be used in conjunction with this General Requirement procedure.
2.0 REFEREN CES
'.1 Section V, including Article 5, "Ultrasonic Examination," 1970 Edition, up to and including the Summer of 1975.
2.2 Section XI, "Ultrasonic Examination," 1970 Edition, including the Summer of 1975 Addenda (except for piping examinations which are to be performed in accordance with Appendix III Winter .1975 Addenda For Both Ferritic and Austenitic Materials, including modi-
'ications in paragraph IWA-2232 Summer 1976 Addenda).
2.3 SNT-TC-1A, "Nondestructive Testing Personnel Qualifications and Certification," June 1975, Edition; 2.0 80A'9068 NES "Procedure for Qualif ication and Certif ication .
of Nondestructive Examination Personnel" (Latest Revision).
2;5 80A9053, Revision 0, October, 1978, NES "Procedure for Ultrasonic Instrument Linearity Verification," as modified by Section 0.2.
2.6 80A9035, NES "Procedure for Weld Marking (of) Datum Points and Identification."
2.7 80A9060, "Inservice Inspection Field Change Procedure."
2.8 80A2767 NES Q.A. Program Plan.
2.9 80A2779 NES Program Plan.
3.0 PERSONNEL AND MATERIALREQUIREMENTS 3.1 Personnel shall be certified in accordance with references 2.2, 2.3,
, and 2.0. At least one member of an ultrasonic examination team shall be certified to at least Level II.
DOCUMENT NO PAGE OF NUCLEAR ENERGY SERVICES, INC.
3.2'he couplant shall be'approved by the owner and shall be certified to contain less than 196 by weight of total residual halogens and less than 1% by weight of total sulphur.
0.0 ULTRASONIC INSTRUMENT REQUIREMENTS 0.1 A contractor supplied pulse echo type ultrasonic flaw detection instrument shall be used. The instrument shall be equipped with a stepped gain control calibrated in units of 2 dB or less, or fine adjustments of at least 2 dB or less.
0.2 Complete instrument linearity checks shall be performed in accord-ance with the technique in the procedure referenced in Section 2.5.
When examinations of items other than piping are to be performed, the instrument linearity shall be checked daily. During the examina-tion of piping welds, linearity checks shall be performed at the beginning of each week.
0.3 During the 'examination of piping welds, a ~dail check of the instrument amplitude control linearity shall be performed as follows:
A) . Obtain a 8096 FSH indication from a reflector in a calibra-
'tion standard. Decrease the gain by.6 dB. The resultant indication should drop to nominally 00%-Full Screen Height (FSH) (the allowed range is 32% FSH to 08% FSH).
B) Obtain a 2096 FSH indication from a reflector in a calibra-tion standard. Increase the gain by 12 dB.. The resultant indication should increase to nominally 8096 FSH (the' allowed range is 609'SH to 96% FSH).
0.0,Should the instrument prove to be non-linear, it shall be tagged and not used. 'All examinations which were performed with that instru-ment since the previous valid linearity check shall be identified in writing to a NES Level III for disposition. The Level IG disposition shall become a part of the permanent PSI records.
5.0 'XAMINATIONSYSTEM CALIBRATION.
5.1 Calibration shall include the complete ultrasonic examination system. Any change in search units, shoes, couplants, cables, ultrasonic instruments, Level II Personnel, recording devices, or any other parts of the examination system shall be cause for calibration check.
The original calibration and final calibration must be performed
- on 'the basic calibration block. Intermediate calibration checks may be performed on a basic calibration block simulator, but must include a check of the entire examination system.
5.1,1 The temperature of the calibration standard shall be within 25 F of the component temperature. Calibration standard and component temperatures shall be recorded on the Cali-bration Data Sheet.
DOCUMENT NO.
PAGg 6 PF 20 NUCLEAR ENERGY SERVICES, INC.
52 Ultrasonic instrument calibration consists of two basic steps, range and sensitivity.
horizontal'inear Horizontal linear range may be established in inches'f metal path. Refer to Figure 0 for appropriate metal path calibration that coincides vg~'th the examination requirements; such as examination angle, .material thickness, and vee
. path..
- 2. Vertical instrument sensitivity is established by obtaining reflections from the side drilled holes or notches, or both, located in the code Calibration Block.
5.3. Basic Calibration Techni ue (Pi in -Full Vee) 5.3.1 The instrument linear range, as displayed on the CRT, will be calibrated in inches by use of a "Miniature Angle Beam Verification Block".
4'he P.3.2 search unit is then positioned on the appropriate piping calibration standard to obtain maximized responses from the
'otches. The 1/2 vee path to the ID notch js set at 8096 FSH, the CRT is marked to record the position and ampli-tude of this primary reference response. --
5.3.3 Without changing the instrument gain, the search unit is then positioned to successively maximize responses from the OD notch and the ID notch (at. the 1 1/2 vee position).
These responses are marked on the screen to establish a Distance Amplitude Cor'rection (DAC) curve. This is the ref erence sensitivity level.
5A Basic Calibration Techni ue (Pi in - 1/2 Vee)
NOTE If half vee calibration becomes necessary on a Calibration Block that is < 1", stop and report to the supervisor for disposition.
"5.0.1 When the examination technique is limited to a thickness oi T (1/2 V-path), side drilled holes shall be used to obtain the slope and shape of the DAC. A minimum of two holes, each of the same diameter, located at I/OT and 3/OT, shall be placed in the end surfaces of the calibration standards. The holes shall be parallel to the length axis of the pipe calibration standard. The minimum hole length shall be 1-1/2 in.
5.0.2 Calibration shall be accomplished by constructing a DAC from the side drilled holes so'hat the maximum amplitude point is at 8096 FSH.. Once the shape and slope are determined and marked on the screen, the'urve shall be extrapolated I/0T to cover the full examination thickness.
DOCUMENT NO, 20 PAGE OF NUCLEAR ENERGY SERVICES, INC.
5.0.3 The ID notch'esponse is then maximized and the instrument gain control is adjusted to bring this signal to the level of the DAC curve. This is the reference level sensitivity for I/2 vee examinations.
5.5 Basic Calibration Techni ue (Yessels and similar com onents) 5.5.1 Calibration shall generally be accomplished by maximizing responses from side drilled holes. The maximum amplitude point is set at 8096.,FSH.. The response amplitudes and positions of the other holes within the examination range are marked on the instrument CRT.
5.5.2 After the CRT is marked, the points are connected by a continuous line to cover the full examination volume. This DAC curve is the reference level sensitivity.
'.6 Basic Calibration Techni ue (Boltin Material)
Calibration shall generally be accomplished by maximizing responses from flat bottomed holes. The calibration stan-
'ard is designed to provide reference responses within the near zone and far zone of each examination item.
5.6.2 Distance amplitude correction f or the f ull examination volume may be accomplished with one calibration on a
'single calibration. standard, on two calibration standards, or it may be divided into two calibration zones in order to.
accommodate exceptionally long sound paths; i.e. RPY
'Closure Head Studs.
5.7 Calibration Checks 5.7.1 A system calibration check shall verif y the Distance-Amplitude Correction curve and the sweep range calibration at the start and finish, and at least every. It hours during each examination. It shall include, any change in Level II examination personnel, Transducers, cables, shoes, batteries, or couplants.
5.7.2 If any point on the Distance-Amplitude Correction (DAC) curve has changed by more than 20% (2 dB) of its amplitude, all data. sheets since the last calibration or calibration check, shall be marked void. A new calibration shall be made and recorded and the voided examination areas 'shall be re-examined.
5.7.3 If any point on the DAC curve has moved on the sweep line more than 596 of the sweep division reading, correct the sweep range calibration and note the correction in the examination record. If recordable reflectors are noted on the data sheets, those data sheets shall be voided, a new calibration recorded, and'the voided examination repeated.
DOCUMENT NO OA 770 PAGE 8 pF 20
.NUCLEAR ENERGY SERVICES, INC.
5.8 Specific details for the system calibration are included in the specific application procedures.
5.9 Requirements for the calibration blocks are included in the specific application procedures.
6.0 SURFACE PREPARATION 6.1 The examination surface shall be free of irregularities, loose foreign matter, or coatings which interfer with ultrasonic wave transmission.
The surfaces to be examined shall be wiped or brushed with a clean rag, brush, or wire brush. For stainless steel surfaces, only stainless steel brushes shall 'be used and these brushes shall not have been previously used on any other material.
6.2 The weld crown shall be sufficiently smooth to permit proper transmission of the sound beam s determined by the examiner.
6.3 'Unacceptable surface conditions shall be referred to the owner for disposition.
7.0 EXAMINATIONVOLUME AND COVERAGE 7.1 .. Vessel %'eids - The examination volume shall include the weld metal and the adjoining base material for one-half plate thickness beyond the edge of the weld.
7.2 ~dpi ld Th I I I h ~ I ld h d and -the adjoining base material for one wall thickness beyond the edge of the weld; 10096 of each longitudinal. weld Class 1 piping; 12" for Class 2 piping intersecting the circumferential weld. selected for examination.
7.3 Inte rail %'elded Su orts - The examination volume shall include the weld to the pressure boundary, plus the base metal of the
,component beneath the weld and along the support attachment for a 7.0 length of axial scan K-Th '*l distance of two support thicknesses.
I hill ld I % I h*
each part. The examination technique will consist. of an from one end through the full length or an axial scan from both ends through over 5096 of the part length. The scan(s) shall cover the full end surface(s).
I'o 7.5 assure complete coverage of the material, each pass of the search unit shall'overlap a minimum of 25% of the transducer piezoelectric element dimension perpendicular to the direction of scan. The rate of search unit movement shall not exceed 6 in/sec.
DQCLIMENT NO, 80A2770 s
PAGE NUCLEAR ENERGY SERVICES, INC.
7.6 During the examination of butt welds, wherever feasible, the scan-ning of the examination volume shall be carried out from both sides of the weld. Where configuration or adjacent parts of the component are such that scanning from both sides is not practical, a full vee technique'from one side shall be considered acceptable. Any areas not scanned shall be described in detail 'on the data sheet. The examination volume shall be scanned by angle beams, both directed at right angles to the weld axis and along )he weld axis in two directions.
7.7 The examination volume is defined in Sections 7.1 through'.0, and in
=each. specific examination procedure. Figure 1 of this procedure presents a tyyical sketch of scan distances, from the edge of the examination volume, for fully scanning that volume with the speci-fied angle and "Vee" path. Detailed sketches will be included within each specific procedure covering each unique examination.
7.3 Manual scanning shall be performed at a gain setting at least two times (+6 dB) the reference level (except when an electronic dis-tance-amplitude correction is used, then scanning shall be performed at reference level). Recording of indications shall be carried out with the gain setting at the reference level.
7.9 Weld Identification and Datum Points The appropriate weld maps in 'the Program Plan shall be used to locate and identify each weld.
7.9.1 Prior to examination, the examiner shall determine whether a reference datum point and reference marking system, to which all examination data and recorded indications may be referenced, have been permanently marked for each weld.
7.9e2 If a suitable permanent radiographic marking system. exists, it may be used in lieu of an additional set of marks.
7.9.3 If no marking exists, then the procedure referenced in Section 2.6 shall be used to provide permanent marking.
8.0, EVALUATIONCRITERIA S. 1 Recordin of Indications S.l. 1 For straight beam examinations of base metal for lamina-tions, all areas giving 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.
80A2770
~OF~
DOCUMENT NO PAGE NUCLEAR ENERGY SERVICES, INC.
(2) Pertinent recorded data shall be taken on each paral-lel scan pass at increments not to .exceed that permitted by the 25% overlap of transducer element diameter (width).
During angle beam exan.ination, all indications showing .
signal amplitudes in excess of 20% DAC . shall be Qi
. investigated to the extent that the examiner can determine their true nature, as set forth below:
(1) If, the indication is determined to be of geometric origin, locate the maximum signal strength area, record the required information for that location on the appropriate form and add the following or similar
. notation (if over 50% DAC):
"Determined to be (ID) geometry caused by (one side is thicker). This has been verified by~a review of the radio ra h), (UT thickness). 'This indication exists for degrees around the pipe".
(2) If the signal is over 20% of DAC and it is a crack,.
incomplete fusion, or incomplete penetration, it shall be plotted and recorded over its full length.
(3) If the signal is slag or porosity or another spherical reflector you may ignore its presence; if it does not exceed 5GEo DAC,'do not record it.
8.1.3 For straight beam examinations of weld and/or required volume and angle beam examinations, all non-geometric indications showing a signal amplitude response equal to or greater than 50% of the ref erence response, shall be recorded on the appropriate data sheet at the time of weld examination.
Each recorded indication shall be identified as to depth (as a percent of thickness), distance from surface, length, signal amplitude and location rela-tive 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 deter-mined by 50% DAC amplitude points.
DOCUMENT NO, SOA2770 NUCLEAR ENERGY SERVlCES, INC. PAGE ~OP~.
8.1.0 Indications from all circumferential welds shall be recorded in inches from the weld centerline up stream or down stream and in inches CW or CCW from the weld datum point when looking toward the direction of flow.
8.1.5 Indications for all longitudinal welds shall be recorded in inches up stream or down stream from the datum point and in inches CW or CCW from the weld datum point when looking towards the direction of flow.
8.1.6 All angle beam indications shall be plotted full-scale.
8.2 Evaluation of Indications 8.2.1 Evaluation of all. indications shall be made at the reference sensitivity and in accordance with the requirements of the referenced ASME Boiler and Pressure Vessel Code,Section XI,.Article IWB-3000.
8.2.2 Cracks, incomplete fusion, and incomplete penetration are un-acceptable regardless of size or amplitude.
8.2.3 The results of this evaluation shall be reported to the Plant Owner, or his'Agent, in accordance with the requirements of Section Xl, Article IWA-6000. 'll the ref erenced ASME Boiler and Pressure Vessel Code, evaluations will be
'performed by a Level II or Level III SNT-TC-1A Examiner.
If evaluatIon is done by a Level II, a Level III shall review.
the evaluation.
9.0 EXAMINATIONRECORDS 9.1 Certification of Records The examiner shall complete and sign the appropriate weld scan data sheet(s) immediately upon the completion of each weld examination, applicable SNT-TC-1A levels. 'oting 9.2 Filin of Records The Examination contractor shall be responsible for submitting to the Plant Owner, or his Agent, a completely documented set-of examina-tion records including certification of personnel qualifications with a current eye test report in accordance with SNT-TC-1A.
'.3 Procedure Corrections and Additions 9.3.1 All procedure corrections and/or additions required during the preservice and/or 'inservice examinations may be initi-ated by either BECHTEL, the owner or the senior NES site representative. All such changes shall have the approval of the owner and.an NES Level III.
DOCUMENT NO 80A2770 pAgp 12 gF 20 NUCLEAR ENERGY SERVICES, INC.
C 9.3.2 The Plant Owner, or his Agent, and the authorized inspector shall be notified of such changes and their approval obtained as required.
o> ~
DOCUMENT NO. 80A2770 NUCLEAR ENERGY SERVICES, INC."
I'ACE . pF 20 Drawing No.: Bechtel No.: 00008 SAMPLE,ONLY Cal. Std. See Table below Too;ing: .Manual Application of Search Units Drawing List:See Paragraph 2.2.2 SAMPLE ONLY E'- Volume of metal to be scanned; i.e. the weld plus S on either side.
P I
S - The larger of 1/2T or 1/2" Length of Path Scan Limit Qo I
Counter bore length:, Piping = 2T SAMPLE ONLY 1/2"., Elbows = 1T or 1/2", 'ittings"=
whichever is less. (Greater than .250")
Note: Perpendicular scan paths should extend beyond the outer edge of S by the length of the Vee Path used.
t Note: Parallel scan paths'should cover as much of E as possible Nominal Pipe l-l/2 Vee Calibration Pi e Dia. S'chedule I I Sl I I1 El 1 11Ltl Standard 2" Dia. 160 500" 1.70011 .1.186" 'ES-XXX 6" Dia,. 10 50011 I 7 QQII .7.86"::. SES-XXX 8" Dia. .20'.'130" 20 .250" 500" .1 700" 1,000" 'ES-XXX 10" Dia. ~ 25Qll 5QQII 1 700" 1.000" SES-XXX 10" Dia. 160 '1.125" 5675" 1.825 2;8125" S ~~XXX 12" Dia. 20 250 5QQ" 1.700" 1.000" SES-XXX 10" Dia. 20 .312" 5 0Q11 1 700" , 1.120" SES-XXX 16" Dia. 20 .312" 5Q 011 I 700" SES-XXX 1.124'.120" 18" Dia. . 20 .312" .500" 1 700" SES-XXX 2" Dia. CEDM Std. ;250" .500" 1.700" 1.000" SES-XXX
.1 ULTRASONIC EXAMINATIONSCAN PATH DISTANCES TABLE
'IGURE ULTRASONIC EXAMINATIONPROCEDURES FOR CLASS I AND II PIPING SAMPLE ONLY
Document No. 80A2770 Plant/Unit Comp/System H~4 CALIBRATION DATA SHEET Procedure No.
Sub ject:
ISO Loop FIGURE 2 Rev/Change No INSTRUMENT SETTINGS SEARCH UNIT Calibration Block. No.
g/Model No.: Scan Angle: Mode: Surface erial No. Fixturing (i any): Block Temp oF Comp. Temp oF ween Len th St le or oe No. Thickness weep Delay Size & Shan e: CRT Calibrated in L.lse Length/Damping: Frequency
-req.: Rep. Rate:. Serial No/Brand:
-ilter: Video: Jack: Measured Angle EC/Gate. Switch: .Range Cable Type G Length; lode Select: Reject: Couplant Brand:
ain (coarse) (fine): Coupla'nt Batch:
Scan Sensitivity 100 DAC PLOT INSTR LZN=ARITY CAL SCAN AREA 90 Amplitude 80 High Low High Low. 70 00 60 To Held 50 M
40 30 C'"libration 20 Axial AMPL. CON ROL LINEARITY 50 0 1
'I2
'I'"
3 IIII t>
4 5 6 7 8 9 10 Circ Initial iAI aB Result 80 80 -12 Recordable COMMENTS/REASON FOR EXAMINATION HELD/AREA Indications INCOMPLETED SCAN(S) 40 Yes No Geom 20 +12 CALIBRATION CHECKS Initial Cal.
Intermediate I n termedia te Intermediate l ~F CCEPTABLE.
Final Cal.
EXAMINERS 1 Date Level ADDITIONAL SHEETS? (CHECK BOX) ontinuatiorJ Beam'lot Date Level Supplements None Date NUCLEAR ENERCY SERViCES. INC.
Document No. 80A2770 INDICATION REPORT SHEET Page 15 of 20 PIGURE 3 Project No. Site L0 Location Date: (Day/Mo/Yr)
I tern Iden ti fication hV 'Location Page of .'kl 0 Wr Examiner: TC- l A Level Angle 00 O5i rr5 II Attached Cal. Data Sheet TC- I A Level Scanning Thicl<ness'xaminer:
dB Diameter (nom.)
Weld Q
MP Metal Path EVmax Distance from Q~ to S.U. at maximum response. -
- RBR Remaining Bacl< Reflection OalIIm 0 L Distance from Datum 0 Distance from weld Q at 50% of DAC (fwd)
Distance from weld <t at 50% of Wmax; (bacl<ward)
J I I
~
FND BACKllVARD Ind. L 50% DAC ~ MAX 50% DAC L 2 . RBR S. U. lV of '~'o.
llV MP MP 50% max 50% amp Loc.
MIL 8 RlC Ul ETt ES
-AT-l N A CBE lk ernarl<s:
I Lirnithtion (Describe, i.e., valve, hanger in'scan'path 3" from weld r ~
L position 2, etc.)
IIMI NUCLEAR ENERGY YICI=S, INC.
DOCUMENT NO.
NUCLEAR ENERGY SERV1CES, 1NC.
~OF~
'AGE METAL PATH CALIBRATION TABLE IRI/2 YEE SCAN PATH EXAMINATIOH hletal Path Calibration Material Thickness Kan e R red 05 60 70 5 ll
>
0.5" - < 1;0" Q 5ll lp 0 > 1-0" < 2. p" P 5ll 2.0"- < 0.5 1.6" - < 3.3" P'll ~( 2ll FULL YEE SCAN P ATH EXAMINATION Metal Path CaUbration material Thickness Range ~ 'equired . 05 60 ~, 70 0 2 5 ll (Q rill 0 ll > 0.8" - < l.?" > 0.6" <<< 3.2" 10.0 " > 1.7" - < 3.5" > 1.2" - < 2.5" >0.3"- <1.6" 20.0 " > 3.5"- < 7.0" > 2.5" - < 5.0". > 1.6" - < 3 3" YEE SCAN 'PATH EXAMINATION '/2, Metal Path Calibration Material Thickness Range Required Q5 60 70 21' ~ 2.5" I 711 5 P ll > 1.7"- < 3.5" 1.2" - < 2.5" > 0.3 < I.6" 10.0 " > 3.5" - < 7.0" > 2.5" - < 5.0" >1.6"- < 3.3" 20.0 ". > 7.0" - < Irr.p" o'5.0" - <,'}0.0" > 3.3" - '< 6.6" INSTRUCTIONS: Th Vee Path and the examination angle are giveri in th specifio procedure. Usirig the a 'ropriate Vee Path Examination Chart (I/2 Vee, Full Yee, and l-l(2 Yee Patla) and the appropriate rninaticn an~pe column, find th= thickness range that encompasses. the thickness of th material eing examined. To the extreme Lef t is the Metal Path Calibration to be utilized. FIGURE 4 DOCUMENT NO 80A2770 NUCLEAR ENERGY SERVICES, INC. PAGE > 7 OF ANGL" BED Vr.RI ICATION BLOCK R-1 3.00%, 90 1 in. 30o N 45o 60o 80'0 0 0 2 60 50 coo 40. 7oo 30 20 10 1 2 3 4 5 6 7 8 9 10 TM PATH CPZ'IBRATION FOR A 2. 5" CRT 'PR SENTATION Obtain a maximized indication from &e short radius (R-1) reflection surface of the "Y~iature ogle Beam Uerification Block" (1".metal path) . '2- Using the material calibration control and.the delay control, align this signal at CRT position the search unit around and obtain a maximized indication fr'om the long 4.'evolve 'adius (R-2) reflection sur ace (2" metal path) . 4- Using the ma erial'calibration control align this signal at CRT position 8. Repeat steps 1 through 4 until'o fu th'er adjustments need to be accomplished. \ The CRT is now calibrated in inches of metal path, (each major division equaling 1/4 inch)., Nake no further adjustments to the sweep range or delay controls. FIGURE 5 NUCLEAR ENERGY SERV(CES, INC. DOCUMENT NO. PAGE 18 Qf 20 INGLE BEAYi V:RTFlCATION BLOCK R-1 R-2 100 90 80 1 in. po 30o~~45o '2 ~ '0o 70 60 p P inch 50 6po 40 70o 30 20 10 2 3 4 5 10 MTAL PATH CALXBRATZON 5" CRT PR=SENTATION 'I 1'- 'e .Obtain a maximized indication from Me"short radius -(R-1) reflection surface of "Hiniature Angle Beam Verification Block" (1" metal path) o'- Using the material'alibration control and the delay c'ontrol, align this signal at CRT position 2. 3- . Xncrease the instrument gain until a secondary echo occurs. 4- Align the secondary signal at CRT position 8. / 5- For reference check the primary signal from the long radius (2"). This signal should pea3c at CRT position 4. 6- The CRT is now calibrated in inches of metal path, (each major'ivision equaling 1/2 inch). lhke no further adjustments to the sweep'range or delay controls. FIGURE 6 ppCUMENT Np 80A2770 NUCLEAR ENERGY SERVICES, INC. 19 20 PAGE . OF G>~ B:PA 9:"RIPICATION BLOCK r 100% 90 80 1 in 450 600 Oo 30o 70 2 in. 60 Q 50 60 40 70 30 20 10 . 1 2 3 4 ..5 6 7 8, 9 10 ~TAL PATH CALIBRATION 10" CRT PRESENTATION 1- Obtain a maximize'd 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, al'ign 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. F 5- The CRT is.now calibrated in inches of metal paN (each major division eaualing 1 inch). Yake no further adjustments to the sweep range or delay controls. 6- ~ 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. FIGURE 7 OOCUMENT NO 80A2770 NUCLEAR ENERGY SERVICES, INC. PAGE pF 20 'NGLE B~~i V.RIFICATION BLOCK R-1 R-2 100% 90 1 80 30 7Q, 60 0 50 60o 40 70o 30 20 10 .1 2'. 3 4. 5 6 7 8 . 9 10 ~TAL PATH'CALIBRATION FOR A 20" CRT PRESENTATION Obtain a maximized indication from the long radius (R-2) reflection surface ~ of the ."Miniature Angle Beam Verification Block" (2" metal path). t Using-the material calibration control and the delay control, align this signal at CRT position l. "3- Increase the instrument gain until secondary echos occur. 4 Secondary echos shall be aligned at CRT position 2.5 and 4. 5- Tne CRT should now be claibrated in inches of metal path (each majo division equaling 2 inches). Make no further adjustments to the sweep range or delay 'controls. 6- 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 8. DOCUMENT NO SOA2771 REV. NUCLEAR ENERGY SERVICES, INC. ~1P 'AGE ULTRASONIC EXAMINATIONPROCEDURES FOR PIPING WELDS SUSQUEHANNA STEAM ELECTRIC STATION UNITS I AND II PENNSYLVANIA POWER AND LIGHT COMPANY HNCONTROLLED COPY Project Application Prepared By Date 5553 P. T. Carr, UT Level'II VV APPRGVALS TITLE/DEPT. SIGNATURE DATE J. Jensen F 17/7'f'. J. Hobin A. Manager G. Oberndorfer DOCUMENT NO 30A2771 NUCLEAR ENERGY SERVICES, INC. PAGE OF REVISION LOG REV, PAGE NQ, DATE NO. D ES C R I PT I ON APPROVAL 11/19/79 Added paragraph 1.2 (3) JJH Paragraph 4.1, Added last sentence FF107310~ / Paragraph 5.1, Added item (7) Paragraph 6.2.5, changed "figure 12" Paragraph 6.2.2, changed "figures 1 through 3" to "figures 1 through 2" Paragraph 7.3,deleted "full" from title 10 Re-wrote Paragraph 7.3.1 Changed Paragraph 7.3.2 to 7.3.3 Added new paragraph 7.3.2 Changed paragraph 7.3.3 (4) to 7.3.3 (5) Added new paragraph 7.3.3 (4) 13 Paragraph 9.2, added "owner" f') Wr-3 6/25/80 Para. 1.4.2 changed 1.812" to 2.344" Para. 4.1 chan ed Ultra el II to Ultra el Para. 4.2 (A) added last sentence Para. 4.3.4 revised ara. Para 4.3.5 delete (see fi ure 8 Para. 5.1 added item 8 Para. 5.2 added item 35 and renumbered accordin 1 Para. 6.1 added note Para. 6.2.1 clarified Para. 6.'2.2 chan e Para. 6.2.5 revised note DOCUMENT NO. OA2771 REVISION LOG NUCLEAR ENERGY SERVICES, INC. PAGE ~OP= 1 RE V. PAGE NO. DATE NO. D E SC R I PT I ON APP ROYAL 3 6/25/80 Para. 7.1 added note Para. 7.2 deleted.."as shown in.." 10 Para. 7. 2. (2), (4), (5) revised and Para. 7.2(6) added note Para. 7.3.1 revised Para. 7.3.2 deleted Para. 7.3.3 chan ed to 7.3.2 12 Para. 7. 4 deleted .. "as shown in .." 12:Para. 7.4 'added note 12 Para 7.4(2) revised ara. 14 Para. 9.4 new ara. Pi ure 3 3a deleted. Remainin fi ures renumber ed Table 1 revised 5/UJ8 1.2 reworded to include essentiall all welds 5.'1 2 added'for 1/2 Vee examinations 5.1 add 9 5.2 5 - 35 chan ed to read "calibra-tion standards as listed in the PSI Pro>> a P an" DOCUMENT NO. REVISION LOG 17 NUCLEAR ENERGY SERVICES, INC. PAGE OF REv. PAGE APPROVAL NO, @ATE NO. DESCRIPTION 5/12/81 Deleted Note, -7.3.2 (2) deleted parenthetical statement 13 8.1.1 added; "at least>>; 8 2 4 changed to read "...Figures 2 through 4)>>Fi ures Fi res 1 & 2 + table 1 deleted Fi s. 1-4 added Incor orated Field Chan es' 2 4 6 15 and 41 ~ '( DOCUMENT No 80A2771 NUCLEAR ENERGY SERVICES, INC. PAGE ~OF ULTRASONIC EXAMINATIONPROCEDURE FOR PIPING WELDS 1.0 SCOPE 1.1 Intent This procedure shall be used in conjunction with NES Procedure 80A2770 unless otherwise specified. 80A2770 contains all of the general requirements applicable to this examination procedure. This procedure contains all of the specific application requirements for the examination of areas specified in Section 1.2. 1.2 Area of Examination This document covers the ultrasonic examination procedures for: (l) Austen(tie Stainless Steel and Carbon Steel, butt and longitudinal w'elds in piping systems.. (2) Special procedures for special we'Id configurations shall be Qj generated as required. 1.3 T e of Examination Volumetric examination .shall be contact, "A" scan. presentation, ultrasonic pulse echo as designated in NES, Inc., Ultrasonic Examina-tion Procedure 80A2770. IA Weld Confi uration The pipe and safeend weld configurations covered by this procedure are shown in Figures 1 and 2. 1.0.2 Nominal weld thicknesses range from'0.280" to 2.300" and are specified in the Tables accompanying Figures 1 and 2. 1 e5 Materials The piping, safeends, and fittings are constructed of austenitic stainless steel or carbon steel. 0 80A2771 PPCLIMEN T NP PAGE OF NUCLEAR ENERGY SERVICES, INC.
2.0 REFERENCES
2.1 SOA2770 NES Procedure; "Ultrasonic Examination General Require-ments" 2.2 30A2779 NES; "Preservice Inspection Program Plan."
3.0 PERSONNEL CERTIFICATION 3.1 Each person performing ultrasonic examination governed by this procedure shall be certified in accordance with the documents ref erenced in Procedure 30A2770.
3.2 Examination crews shall have one or more members as necessary.
4.0 EXAMINATIONREQUIREMENTS
.1 ~lid C 4 The ultrasonic liquid couplant to be used for examinations using this procedure shall be either Sonotrace or Ultragel (Echo Laboratories).
Certified test reports for each batch will be maintained on site.
V 0'.
0.2 Examination Fre uenc The ultrasonic examination frequency for examinations using this procedure shall be:
(a) Nominal 2.25MHz or 5.0 MHz for all 0 Straight Beam Examinations. A 5.0MHz is generally used to improve resolution.
(b) Nominal 2.25MHz for all angle beam examination of
'carbon steel.
(c) Nominal 2.25MHz or 1.6MHz for all angle beam examination of stainless steel.
0.3 Examination An les 0.3.1 Each weld and the required volume ('NRV) of metal for I/2T
~
or 1 inch, whichever is smaller, on each side of the weld 0
shall be ultrasonically examined using 05 angle beam techniques applied in two directions towards the weld and in two directions .parallel with the weld, except where res-tricted by part geometry or access.
0 . ~ 0 If the use of 05 angle beam technique is not effective, 60
~
angle beam techniques shall be applied in the same manner.
DOCUMENT NO. 80A2771 PAGE 7 OF-NUCLEAR ENERGY SERVICES, INC.
0.3.2 Straight beam techniques shall be applied, where part geo-metry permits, to all base material through which the angle beams will pass during angle beam examinations. Indica-tions detected are to be recorded in accordance with Section 9.0 of this procedure, except in areas where no back echo can be obtained. Indications detected shall be, re-corded'nd data used during evaluation of angle beam examination results.
0.3.3 Other beam angles may be used as determined necessary; i.e., for evaluation of reflectors, to compensate for geo-metric constraints, etc. All information shall be recorded on the data sheets.
0.3A In addition, calibrated straight beam techniques (as de-scribed in Paragraph 7.2) shall ge applied to the weld'and required volume (WRV) where part geometry permits. This calibration shall also be used where no back 'echo can be obtained. Indications shall be recorded in accordance with Section 3 of Procedure 30A2770..
0.3.5 Where surface conditions do not permit a meaningful ultra-sonic examination, the examiner'hall record the location, and the particular interfering condition in the space pro-vided on the Weld Scan Data Sheet. In addition, he shall make a sketch of the weld and adjacent pipe and fitting conditions on a separate sheet and attach to the Calibration Data Sheet. Photos may be taken and incorporated as part of the report.
0.3.6 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 so noted on the Data Sheet.
0.3.7 Coverage for the welds specified in this procedure is shown in Figures 1 and 2.
5.0 EQUIPMENT REQUIREMENTS 5.1 Examination Contractor's E ui ment The following test equipment, or its equivalent, shall be provided by the Examination Contractor (as a minimum) for examination of welds specified in this procedure.
(1) Pulse echo ultrasonic instruments.
DOCUMENT NO.
PAGE OF NUCLEAR ENERGY SERVICES, INC.
(2) %edges: 05 and 60 angle beam (shear wave and refracted longitudinal) to accommodate search units (I/O'r 1/2" aerotech only) f or 1/2 Vee examinations. ~4 (3) Search Units: 0; I/O" through 1.0" dia.; 2.25MHz and 5.0 MHz when requi'red.
(0) Search Units: 2.25MHz/1.6MHz (all sizes) for angle beam wedges.
(5) Couplant.
(6) Thermometer.
(7) Cleaning cloths.
Miniature Angle Beam Verification Block.
0 0 For 1-1/2 Vee techniques, wedges 05 and 60 angle beam of a suitable size.
5.2 Plant Owner's E ui ment The Plant Owner or his Agent, shall provide the following service facilities and equipment as required.
(1) Scaff olding.
(2) Vlater, Air, and Electricity.
(3) Adequate Temporary Lighting.
(0) Moving or Lifting Devices.
(5) Calibration Standards as listed in the PSI Program Plan (6) Test Surf ace Preparation (cleaning and f inishing).
(7). Drawings of each Examination Area.
(3) Post-Examination Cleanup.
6.0 CALIBRATION REQUIREMENTS 6.1 Calibration Data Sheets Calibration Data sheets may be numbered 2771-1, 2771-2, 2771-3, etc., and shall be signed by the examiner(s) upon completion, noting.
applicable SNT-TC-lA levels. As an alternate, data sheets may be numbered sequentially by system.
/
DOCUMENT NO.
17 PAGE OF NUCLEAR ENERGY SERVICES, INC.
6.2 Calibration Standards 6.2.1 The Miniature Angle Beam Verification Block shall be used for basic instrument horizontal linear range calibration.
6.2.2 The calibration standards designated in the Program Plan shall be used for establishing reference sensitivity levels for examin'ation of the piping welds specified in this procedure.
6.2.3 The appropriate calibration standard corresponding to each respective weld thickness shall be recorded on each Calibration Data Sheet.
6.2.0 +Spot thickness checks of the Piping Weids and the areas of examination shall be made during preservice examination to ensure that the proper calibration standard is used and to establish locations of counter bore areas.
6.2.5 Calibration procedures'shall be performed using the O.D.
surface of the calibration standard.
+NOTE: The examiner may refer to the individual weld "T".
maps f or each weld when scanning, and shall observe reflectors on the CRT which may be the weld prep taper, counter-bore, weld root and shrinkage, and also any other condition noted during the 0 examination of the WRV.
7.0 EXAMINATIONSYSTEM CALIBRATION
'.1 Strai ht Beam Calibration for Interferin Conditions 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 ref lecton signal amplitude from the piping being examined of at least 8096 Full Screen Height (FSH).
7.2 Strai ht Beam Calibration Straight beam calibration shall be performed as f ollows:
(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 f rom the side drilled (I/0T 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.
4 DOCUMENT Np 80A2771 I~
'A'UCLEARENERGY SERVICES, V
PAGE 10 pF INC.
(3) This is the reference sensitivity level. Record all sensitivity control settings on the appropriate Calib-ration Data Sheet.
(0) This completes calibration for thicknesses < 1". (No DAC is necessary for weld thicknesses < I".7 (5) For weld thicknesses > 1", a Distance Amplitude Correction (DAC) curve shall be established as f ollows:
(a) %'ithout changing the sensitivity obtained in (2) above, position the search unit for maximum response from the 3/0T hole and mark amplitude on the CRT screen.
(b) If an electronic DAC is used, the ref erence response shall be equalized at 8096 of FSH over the distance range to be employed in the exami-nation.
(c) 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 Calib-ration Data Sheet. The examiner(s) shall sign the completed data sheet, noting applicable SNT-TC-1A level.
7.3 An le Beam Calibration One and One-Half Vee Techni e.
One and one-half vee path calibration shall be the prefered method of calibration for the examinations described in this procedure and shall be accomplished as follows:
7.3.1 Calibration shall consist of two basic steps: Metal path for horizontal linear range and sensitivity. Refer to Procedure 80A2770 f or the appropriate horizontal linear range calibration (metal path).
7.3.2 Sensitivity Calibration (1) Using the appropriate piping calibration standard, maximize the signal from the first notch in the vee path and set its amplitude to 8096 FSH.
DOCUMENT NO.
t NUCLEAR ENERGY SERVICES, INC.
PAGE OF 1
(2) Without changing sensitivity settings, maximize suc-cessive notch indications and mark their peak ampli-tudes on the CRT screen, and on the Calibration Data Sheet.
(3) This is the reference sensitivity level. Record all sensitivity control settings on the appropriate Calibration Data Sheet.
Reject may be utilized by the examiner, provided the amplitude linearity of the instrument is varified at the desired level. This verification shall be docum ented.
(5) Upon completion of calibration, ensure that all data and instrument settings are recorded on the Calibra-tion Data Sheet. The examiner(s) shall sign the completed data sheet, noting applicable SNT-TC-lA levels.
7.$ An e Beam Calibration - 1/2 Vee Techni 'e 1/2 Vee calibration shall be used if conditions prevent the use of full vee and shall be accomplished as follows:
NOTE: If half vee calibration becomes necessary on a calibration block that is < 1", stop and report to the supervisor for disposition.
(1) Select a search unit of such size and angle for the examination in order to examine the root of the weld within the 1/2 vee path.
(2) "Ref er to Procedure 30A2770 for the appropriate horizontal linear range calibration (metal path).
Obtain maximized responses from side drilled holes within the 1/2 vee path.
(3) Set the highest amplitude signal at 80% FSH and mark its amplitude and position on the CRT'screen.
Without changing sensitivity, maximize the signal(s) from the remaining hole(s) and mark the amplitude(s) at the appropriate position(s) on the CRT. Note signal response amplitudes, positions, and the sensi-tivity settings on the Calibration Data Sheet. When the shape and slope of the DAC curve is determined and marked on the CRT screen, the curve shall be extrapolated I/OT to. cover the f ull examination thickness.
DpCUMEMT Np 80A2771 PAGP . 12 PF 17 NUCLEAR ENERGY SERVICES, INC.
(0) Obtain a maximized signal from the ID notch and adjust the instrument sensitivity to bring its peak to the DAC curve line and mark this location on the CRT.
(5) This is the reference sensitivity level. Record all sensitivity control settings on the appropriate Calib-ration Data Sheet.
(6) Upon completion of 'calibration, ensure that all data and instrument setting are recorded on the Calibra-tion Data Sheet. The examiner(s) shall sign the completed data sheet, noting applicable SNT-TC-1A levels.
8.0 EXAMINATIONPROCEDURES 8.1 Examination f or Interf erin Conditions 8.1.1 Straight beam examinations to detect laminar reflectors which might affect the. interpretation of angle'beam results shall be performed at a sensitivity level giving a back reflection from the piping. being examined of at least 80%
FSH as noted in Section 7.1.
8.1.2 A rectilinear scan pattern shall be used.
8.2 Strai ht and An le Beam Examination of WRV 8.2.1 All straight and angle beam examinations of the Weld and Required Volume shall be performed at a scanning sensi-tivity level, a minimum of 2X (6dB) greater but no more than 10 dB greater than the calibrated reference sensitivity level.
The search unit shall be swivelled (if possible) as it is moved
'.2.2 along at a rectilinear scan pattern to ensure a minimum of 2596 overlap of the transducer width.
8.2.3 The rate of search unit movement shall not exceed 6 inches/second.
8.2.0 See Figures 2 through .0 for scan path distances of the weld examination.
8.2.5 For the locations and the numbers of the welds, refer to the Program Plan. Examinations shall not be considered com-plete until all recordable indications have been evaluated.
DpCUMENT Np SOA2771 Pcs F 1~ OF NUCLEAR ENERGY SERVICES, INC.
9;0 EYALUATION 9.1 All Geometric Reflections which originate on an ID surface shall be recorded in the following manner.
(a) Record position coordinates relative to the datum point for a single strongest amplitude position only.
(b) Record search unit position with respect to weld centerline.
(c) Determine if the indication is detectable from the opposite side+
(d) Clearly mark the data sheet; "Geometric Reflector" and s'pecify "Counterbore", "Rbot Concavity", etc.
9.2 All Geometric Reflections which originate on an OD surface shall be reported to the Bechtel site representative and Owner for corrective action daily.
9.3 All Non-Geometric Indications shall be recorded in accordance with NES Procedure Number 30A2770. The disposition of all such indica-tions shall be performed by an NES Level III; 9.0 . For all straight beam examinations record indications which may cause a loss of back reflection and/or secondary indications that have an amplitude equal to or exceeding the remaining back reflection.
DOCUMENT NO
. 80A2771
,V PAGE 14 oF NUCLEAR ENERGY SERVICES, INC.
B A
A 45 45 60 60 Y K Wield Width A 45 Scan Paths 0
B~60 Scan Paths T~Thickness NOTE' ALL SCAN PATHS MUST INCLUDE THE WELD WIDTH.
REFER TO FIGURES 2 THROUGH 4 FOR SCAN PATHS.
FIGURE 1. TYPICAL WELD CONFIGURATION.
DOCUMENT NO.
I 15 PAGE OF NUCLEAR ENERGY SERVICES, INC.
SCAN PATH TABLE 1/2 VEE SURFACE DISTANCE . SURFACE DISTANCE THE ESS 45 60
.2 0" W+ 0"
.251" to .375" W + 75" W + 1.00"
.376" to .500" W + 75" W +.,1P25"
. 501" to . 625" W + 1 50"
.626" to .750" W + 1.25" W + 1;75"
.751" to .875" W + 1.50" W + 2.00"
.876" to 1.000" W + 1.50" W + 2.2 "
W + 2.75" 1.126" to 1.250" W + 2.00" W + 3.PP" 1 ' 1'o 1.375" W + 2.25" W + 3.50" 1.376" to 1.500" W + 2.25" W + 3 50"
- 1. 501" to 1. 625'-' + 2 50" W + 3.75" 26" 1. W + 2 W + 4.00" 1.751" to 1.875" W + F 00" W + 4.25" 1.876" to 2.000" W + 3.00" W + 4.50" FORifULA'5 ~ W + 1/2T + T 60 W + 1/2T + (1.75 x T)
W = Weld Width T Thickness ALL SCAN PATHS ROUNDED-UP TO THE NEAREST .25" FxgURZ 2 WCII ~ & 1CC
DpCUMENT gp 80A2771
~GF pAGE NucLEAR ENERGY SERVICES, INC.
SCAN PATH TABLE FOR FULL VEE SURFACE DISTANCE SURFACE DISTANCE THICKNESS 45 60
.125" 'to .25" W + .625" W + 1.00"
.251" to .375" + 1.00" W + 1.50" 7 II o 0 II W +
.501" to .625" W + 1.75" W + 2.50"
.626" to .750" W + 2.00" W + 3 00"
.751" to ~ 875" W + 2.25" V + 3 50" W + 2.50" V + 4.00" 1.001" to 1.125" W + 3 00" W + 4.50"
- 1. 126" to 1. 250" W + 3.25" W + 5.00" 1.376" to 1.500" W + 3.75" + 6.00" 1 501" to 1.625" W + 4.25" W + 6.50" 1.626" to 1.750" V + 4.50" V + 7.00" 1.751" to 1.875" W + 4 75" W + 7 50" 1.876" to 2.000" V + 5 00" + 8.00" FORMULA'5 = W + 1/2T + 2T 60 = W + 1/2T + 2 (1.75 x T)
W = Veld Width T = Thickness ALL SCAN PATHS ROUNDED-UP TO THE NEAREST .25" FIGURE 3 FORM>>NEB
F 80A2771 DOCUMENT NO.
NIL 17 PAGE OF NUCLEAR ENERGY SERVICES, INC.
SCAN PATH TABLE 1 1/2 VEE SURFACE D ISTANCE SURFACE DISTANCE THICKNESS 45 60
.125" to .250" W + 1.0" W + 1 50"
.251" to'375" W + 1.5" W + 2.25" 6lt tt 7
.501" CQ .625" W + 2.25" 'W + 3.75"
.626" co .750" W + 2.75" W + 4..5O" 751" .co .875" W + .25" W+ 00 W + 3.50" W + 5 75" 1.001" Co 1.125" W + 4 00" w + 6.50" 1.126" to 1.250" W + 4 5P" W + 8.00" 1.376" to 1.500" W + 5.25" W + 8.75" 1.501" to 1.625" W + 5.75" W + 9.50"
- 1. 626" to 1. 750" W + '6. 25" + .2 W + 6.75" W + 11.00" 1.876" to 2.0" W + 7.00" W + 11.5P" FORMULA: 45 = W + 1/2T + 3T 60 = W + 1/2T + 3 (1.75 x T)
W = Weld Width T ~ Thickness ALL SCAN PATHS ROUNDED-UP TO THE NEAREST .25" FIGURE 4 FORM-"NES 205 2/80
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