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
'pgraded for PSI to be compliant with the 1977 edition to 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.
EXAMINATIONAND INSPECTION (CLASS 1)
COMPONENTS,
- PARTS, HETHOD OF EXAHINATIONAND REMARKS ITEH NO.
EXAMINATION CATEGORY TABLE IWB 2500 COMPONENTS AND PARTS TO BE EXAMINED
- REACTOR VESSEL-METHOD REl1ARKS 81.1 81.4 8-A Pressure-retaining welds
~ in reactor vessel beltline region 8-D Full penetration welds of nozzle in vessel Longitudinal and circumferential shell welds meridional and circumferential head welds vessel-to-flange and head-to-flange circumferential welds Primary nozzle-to-vessel welds and nozzle inside radiused section Volumetric Volumetric (7)
(7) 81.5 81.6 8-E Pressure-retaining partial penetration welds in vessels 8-F Pressure-retaining dissimilar metal welds Vessel penetration, including control rod drive and instrumentation penetration Nozzle-to-safe end welds Visual (IWA-5000)
Volumetric and surface (7)
(7) 81.7 8-G-1 Pressure-retaining bolting greater than 2 inches in diameter Nuts Surface (7) 81.8 8-G-1 Pressure-retaining bolting greater than' inches in diameter Pressure-Retaining bolts and s tuds Volumetric and surface (7) 81.9 8-G-1 Pressure-retaining bolting greater than 2 inches in diameter Ligaments between threaded stud-
'olumetric holes (7) 81.10 8-G-1 Pressure-retaining
- bolting, greater than 2 inches in diameter Closure washers, bushings Visual (7)
'1.
Numbers listed desigrhte applicable relief request.
Page l,of 8, REVISION 0
EXAMINATIONAND INSPECTION (CONT'D)
(CLASS 1)
ITEM NO.
Bl.ll EXAMINATION CATEGORY TABIE IWB - 2500 8-G-2 Pressure-retaining
- bolting, smaller than or equal to 2 inches in diameter COMPONENTS AND PARTS TO BE EXAMINED Pressure-retaining bolting MET1IOD Visual REMARKS (7) 81.12 8-H Vessel supports 81.13 8-I-1 Interior clad surface of reactor vessel 81.14 8-I-1 Interior clad surface of reactor vessel Integrally welded vessel supports Closure head cladding Vessel cladding Volumetric
- 1) Visual and surface or
- 2) Volumetric Visual (7)
(7)
(7) 81.15 8-N-1 Interior of reactor vessel Vessel interior
'isual (7) 81.16 8-N-2 Integrally welded core support structures and interior attachments to reactor vessel 81.18 8-0 Pressure-retaining welds in
'ontrol rod drive housings Interior attachments and core support structures Control rod drive housings Visual Volumetric (7)
(7) 81.19 8-P Components exempted from examination by IWB-1220 Exempted components Visual (IWA-5000)
(7)
-PIPING PRESSURE BOUNDARY-84.1 84.2 8-F Pressure-retaining dissimilar metal welds 8-G-1 Pressure-retaining bolting greater than 2 inches in diameter Safe-end to piping welds and safe-end in branch piping welds Pressure-retaining
- bolting, in place Volumetric Volumetric and surface-(2).
Page 2 of 8, REVISION 0
EXAMINATIONAND INSPECTION (CONT'D)
(CIASS 1)
ITEM NO.
EXAMINATION CATEGORY TABLE IWB - 2500 COMPONENTS AND PARTS TO BE EXAMINED METHOD REMARKS 8-G-1 Pressure-retaining bolting greater than
.2 inches in
. diameter Pressure-retaining
- bolting, when removed Volumetric and surface (2)'4.4 8-G-2 Pressure-retaining
- bolting, smaller than or equal to 2 inches in diameter Pressure-Retaining bolting Visual (2) 84.5 8-J Pressure-retaining welds in piping Circumferential and longitudinal Volumetric piping welds 84.6 84.7 0
8-J Pressure-retaining welds in piping 8-J Pressure-retaining welds 'in Branch pipe connection welds exceeding six inches in diameter branch pipe connection welds six inches diameter and smaller Volumetric Surface 84.8 84.9 8-J Pressure-retaining welds piping 8-K-1 Support members for piping, valves and pumps Socket welds Integrally welded supports Surface Volumetric
-(3) 84.10 8-K-2 Support components for piping, valves and pumps 84.11 8-P Components exempted from examination by IWB-1220 Support components Exempted components Visual Visual (IWA-5000)
Page 3 of 8, REVISION 0
EXAMINATIONAND INSPECTION (CONT'D)
(CLASS 1)
ITEM NO.
EXAMINATION CATEGORY TABLE IWB 2500 COMPONENTS AND PARTS TO BE EXAMINED METHOD REMARKS 85.1 B-G-l Pressure-retaining bolting greater than 2 inches in diameter PUMP PRESSURE BOUNDARY-Pressure-retaining
- bolting, in place Volumetric (2) 85.2 8-G-1 Pressure-retaining bolting greater than 2 inches in diameter Pressure-retaining
- bolting, when removed Volumetric and surface (2) 85.3 8-G-2 Pressure-retaining
- bolting, smaller than or equal to 2 inches in diameter Pressure-retaining bolting Visual (2) 85.4 8-K-1 Support members for piping, valves and pumps Integrally welded supports Volumetric (3) 85.5 8-K-2 Support components for piping, Support components valves and pumps Visual 85.6 85.7 85.8 8-L-1 Pressure-retaining welds in pump cases B-I,-2 Pump casings 8-P Components exempted from examination by IWB-1220 Pump casing welds Pump casings Exempted components Volumetric Visual Visual (IWA-5000)
- VALVE PRESSURE BOUNDARY 86.1 8-G-1 Pressure-retaining bolting greater than 2 inches in diameter Pressure-retaining bolts and studs Volumetric and surface (2)
Page 4 of 8, REVISION 0
EXAMINATION AND INSPECTION (CONT'D)
(CLASS 1)
ITEH NO.
86.2 EXAMINATION CATEGORY TABLE IWB - 2500 8-G-1 Pressure-retaining bolting greater than 2 inches in
~ diameter COMPONENTS AND PARTS TO BE EXAMINED Pressure-retaining bolting METHOD Visual 86.3 8-G-2 Pressure-retaining
- bolting, smaller than or equal to 2 inches in diameter Pressure-retaining bolting Visual 86.4 8-K-1 Support members for piping, valves and pumps Integrally welded supports Volumetric 86.5 8-K-2 Support cog>ponents for piping, Support components valves and pumps Visual 86.6 86.7 8-H-1 Pressure-retaining welds in valve bodies 8-H-2 Valve bodies Valve-body welds 0
Valve bodies Volumetric Visual
'6.8 8-P Components exempted from examination by IWB-1220 Exempted components Visual (IWA-5000)
RP: pd 19-Q Page 5 of 8, REVISION 0
0 EXAHINATION AND INSPECTION (CLASS 2)
(CONr'D)
ITEH NO.
EXAHINATION CATEGORY TABLE IWC-2520 COHPONENTS'ND PARTS TO BE EXAHINED PRESSURE VESSELS HETHOD C1.1 C1.2 C-A Pressure-retaining welds in pressure vessels C-B Pressure-retaining nozzle welds in vessel Circumferential butt welds Nozzle-to-vessel welds Volumetric Volumetric C1.3 C-C Integrally welded support attachments to vessel Integrally-welded supports Surface Cl.4 C-D Pressure-retaining bolting exceeding 1 inch diameter Pressure-retaining bolting Visual and either surface or Volumetric PIPING C2.1 C-F Pressure-retaining welds in piping, pumps and valves in system which circulate reac-tor coolant Circumferential butt welds Volumetric
., (1) (4) (5) (6)
C2.1 C-G Pressure-retaining welds in
'iping, pumps and valves in system which circulate other than reactor coolant Circumferential butt welds Volumetric (1) (4) (5) (6)
C2.2 C-F Pressure-retaining welds in
- piping, pumps and valves in system which circulate
reactor coolant Longitudinal weld joints in fi.ttings Volumetric (1)(4)(5)(6)
C2.2 C-G Pressure-retaining welds in
- piping, pumps.and valves in system which circulate other than reactor coolant Longitudinal weld joints in fittings Volumetric (1) (4) (5) (6)
Page 6 of 8, REVISION 0
EXAMINATIONAND INSPECTION (CLASS 2)
(CONT'D)
ITEM NO.
C2.3 EXAMINATION CATEGORY TABLE IWC-2520 C-F Pressure-retaining welds in piping, pumps'nd valves in system which circulate reactor coolant COMPONENTS'ND PARTS TO BE EXAMINED Branch pipe-to-pipe weld joints METHOD Volumetric (I)(4)(5)(6)
C2.3 C-G Pressure-retaining welds in piping, pumps and valves in system which circulate other than reactor coolant Branch pipe-to-pipe weld joints Volumetric (1) (4) (5) (6)
C2.4 C-D Pressure-retaining bolting Pressure-retaining bolting exceeding li'inch diameter Visual and either surface or volumetric.
(2)
C2.5 C-E-1 Support members for piping valves and pumps Integrally-welded supports Surface (3)
C2.6 C-E-2 Support components for piping valves and pumps Support components Visual
- PE1PS-C3. I C-F Pressure-retaining welds in piping, pumps and valves in systems which circulate reactor coolant'ump casing welds Volumetric C3 1
C-G Pressure-retaining welds in piping, and valves in systems which circulate other than reactor coolant Pump casipg weld Volumetric C3.2 C-D Pressure-retaining bolting Pressure-retaining bolting exceeding 1 inch in diameter Visual and either surface or volumetric
~ (2)
Page 7 of 8, REVISION 0
EXANINATION AND INSPECTION (CLASS 2)
(CONT'D)
ITEH NO.
EKV1INATION CATEGORY TABLE IWC-2520 COHPONENTS'ND..PARTS TO BE EXAllINED HETHOD C3.3 C-E-1 Support members for piping Integrally-welded supports valves and pumps Surface C3.4 C-E-2 Support components for piping valves and pumps Support components Visual
- VALVES C4.1 C-F Pressure-retaining welds in piping, pumps and valves in systems which circulate reactor coolant Valve body welds Volumetric C4.1 C-G Pressure-retaining welds in
- piping, pumps and valves in systems which circulate other than reactor'coolant Valve body welds Volumetric C4.2 C-D Pressure-retaining bolting Pressure-retaining bolting exceeding 1 inch in diameter Visual and either surface volumetric C4.3 C-E-1 Support members for piping Integrally-welded supports valves and pumps Surface C4.4 C-E-2 Support components for.
piping valves and pumps Support components Visual 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 will be used for piping system ultrasonic examination.
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 EXAMINATION CATEGORY 'OMPONENT METHOD B4.2, B5.1, B6.1 B4.3, B5.2, B6.2 B4. 4, B5. 3, B6.3 C1.4, C2.4, C3.2, C4.2 B-G-1 B-G-1 B-G-2 CD Pressure retaining bolting, 2 inches and larger, in place Pressure retaining bolting, 2 inches and larger, when removed.
Pressure retaining bolting, smaller than 2 inches.
Pressure retaining bolting exceeding 1 inch Volumetric Volumetric and Surface.
Visual Visual and 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 NUMBER EXAMINATION CATEGORY COMPONENT METHOD B6.150, B6.180, B6.210 B-G-1 Pressure retaining bolting larger than 2 inches in place Volumetric B6.160, B6.190, B6.220 B-G-1 Pressure retaining bolting larger than 2 inches, when removed.
Surface and Volumetric B6.170, B6.200, B-G-1 B6..230 Pressure retaining bolting.*
Visual VT-1
,B7.50, B7.60, B7.70 B-G-2 Pressure retaining bolting 2 inches and smaller Visual VT-1 C4.10, C4.20,
~
~
c4.30, C4.40 C-D Pressure retaining bolting 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 NUMBER EXAMINATION CATEGORY COMPONENT METHOD TEST REQUIREMENTS B4.9. B6.5 B-K-1 Integrally welded support attachments Volumetric Table or Surface*
IWB-2500-1 C3.10, C3.40, C3.70, C3.100 C-E-1 Integrally welded support attachments Surface**
Table IWC-2500-1
- 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 IDENTIFICATION NUMBER'ODE CATEGORY AND ITEM NUMBER SYSTEM CONFIGURATION NATURE OF OBSTRUCTION
%%d OF SCAN OBSTR
"~( TED (APPROXIMATE)
DBB-114-1-9E CF C2.1 HPCI Pipe to Cap Two (2)
Weldolets 16'BB-13 5-1-7F DBB-115-1-5D DBB-115-1-5G CF C2.1 CF C2.1 CF C2.1 RHR RHR Pipe to Cap Pipe to Tee Pipe to Cap one (1)
Weldolet One (1)
Weldolet Three (3)
Weldolets 8%
16%
34%
HBB-110-2-3C CF C2.1 RHR Elbow to Tee Instrumentation Nozzle 3%
DLA-104-1-FW1 BJ B4.5 Feedwater Pipe to Valve Permanent Hanger 50%
DLA-102-1-FW7 HBB-ill-2-3D BJ B4.5 CF C2.1 RHR Pipe to Elbow t
Feedwater Pipe to Valve Permanent Hanger 50'anger Saddle Weld 13%
DBB-3.18-1-1A CF C2.3 Feedwater Sweepolet to Pipe Hanger Lug Attachment 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 will be performed for preservice examination; Class l welds have received surface examination to satisfy ASME Section III 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 IDENTIFXCATION NUMBER CODE CATEGORY AND XTEM NUMBER SYSTEM NATURE OF CONFXGURATXON OBSTRUCTXON OF SCAN OBSTRUCTED HBB-101-.3.-FW-7 CG C2.1 RCIC Pipe to Sparger
-Piping located in the wetwel1
.Totally Obstructed HBB-101-1-lA CG C2.1 RCXC Pipe to reducing elbow HBB-101-1-1B CG C2.1 RCIC Pipe to Elbow HBB-101-1-FW6 CG C2.1 RCXC Flued Head to Pipe Rev.
0 5/15/81
ASME SECTION III EXAMINATION SAFETY IMPACT RT RT 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, 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.
RT Rev.
0 5/15/81
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 IDENTIFICATION NUMBER CODE CATEGORY AND ITEM NUMBER SYSTEM CONFIGURATION
'NATURE OF
% OF SCAN OBSTRUCTION OBSTRUCTED DCA-3.10-.1-FW11 BJ B4.5 RHR.
- 'Valve to Tee Part Geometry Totally DCA-110-2-FW11 BJ B4.5 RHR Valve to Tee Part Geometry Totally DCA-107-1-FW3 BJ B4.5 Core Spray Valve to Valve Part Geometry Totally DCA-107-2-FW7 BJ B4.5 Core Spray Valve to Valve Part Geometry Totally 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 RT and PT RT and PT 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 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 accordance'ith examination nd testing requirements of ASME Section III.
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
I 8I ttE ~g
~r"
)Ott ~],990 u8" g)raCI e
< ~aft ZtOtt
~'~CO9+
cttc TIP r
PQR M'~~ZK~
~WK 122 9
M~w~i6 VENDOR CLIENT FIELD NO.
~I CIVIL ELECT.
PLT. DES.
MECH.
CON. SYS.
ARCH.
PURCH.
EXPED.
INSPECT SCHED.
D ISTR I8 UTION 0
Iz0 IL, O
0
@ Zev.
2 Z/9/V7 Ra+.
3 p
RECORD BECHTEL SAN FRANCISCO Z0 I
O0
/PB
~W~
g <<+~a 7v VENDOR'S DRAWING REVIEW 1 Q Approved-MI9. ntay Proceed.
0 ADproved" subnlrt final dw9.- MI9 may proceed.
0 Aooroved except as noted.-Male chan9es and submil linet ow9.-Mt9. may proceed
'aS approved.
4 0 Not Aoproved~olrect and relUbnsrt.
9 0 Aooroval nol reouired:MI9. may oroceed.
Pg THIS SUBMITTALCOMPLETELY REPLACES THE PREVIOUS SUBMITTAL(S).
Q THIS IS AN AOOITIONTO SUBMITTAL
. THE PAGES SHOULO BE INSERTEO.
Q THIS IS AN ADDENDUM,AN ADDITION,OR A SUPPLEMENT TO SUBMITTAL
. AOO THIS TO THE ABOVE SUBMITTAL AND RETAIN THE TOTAL DOCUMENT.
REVIEWED C l L,
M I
A JOB NO.
8856 BY Bt CrtTEL ADprovar.or lhrs orawm9 poet nol rcireve suppher from full comDliance with contract or Durchase or ~
er re ur<ensen~s
~l e
REVISION NO.
3/29/78 PAGE~ OF PROCEDURAL REQUIREMEHTS PARAGRAPH (a)
Meld type and configurations to be examined, including thickness dimensions, 'materials and product form..............
1.1 (b)
(c)
The surface or surfaces from which the examination shall be performed............................................
S
~ ~
~
urface-Cond>tron.............................................
7.1.9
- 5. 6. 1 (d) ouplanttt ~
>1 ~ ~ ~ ~ ~ ~ ~ t ~ ~ 00 ~ ~ ~ 0 ~ ~ ~ ~ ~ 0000
~
~
~
~
~
~
~
~
~
~
P
~ oe
~
~
~
0
~
~
~
C
- 5. 6. 2 (e)
Technique (Straight beam, angle
- beam, contact and/or zmmersxon)..................-.-...
~ -
~ ---- ~ ~ -- ~ - ~ -- ~- - - - 1; i@7. 1."
Angles and modes of wave propagation in the material......- --- 7.1.6&7.
'I Search unit, type, frequency and transducer sizes...............
- 5. 5 (h)
Special. search units,
- wedges, shoes, or saddles, if used, and type and length of search unit'able......................
- 5. 5. 3..2 (i)
(i)
II
{k)
Ultrasonic.c instrument type(s)....;............................
Description of Calibration................'......-----------.-
~
Directions and extent of scanning.............................
5.1 6.0 7.0 Data to be recorded and method of recording (Manual or automatic)....................................................
8.0
'(m)
(n)
Automatic alarm and recording equipment, if used.....;........
N/A Rotating, revolving, or scanning mechanisms, ifused..........
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 STATUS SHEET REVISION NO.
DATE PAGE Of, 3/29/78'ocument
~iItle'LTRASONIC EK&CNATION OF SIMILAR AND DISSIMILAR METAL WELDS FOR SUSQUEHANNA REVIS tONS Page ii Added Changed Rev.
0 to.Rev.
1 >>
12/8/76
- 6. 2..1. 2 Changed Table I Page 9
Amplitude Limits 16-14 to.16-24 Changed Rev.
2 to Rev. 3 3/29/78 I
General revisions 'throughout procedure 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.
3.2.2 3.2.1.2 Article V, Nondestructive Examination.
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 ADMINISTRATIVERZgrJIREMENTS 4.1 This procedure has been prepared in accordance with the requirements of reference
- 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 OF 3
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 4.4 '
All entries on the forms shall be made in black reproducible ink.
- 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 4.5.2 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.
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).
5 '
SPECIFICATION NO.
REVISION 'NO.
DATE PAGE OF
~ 22" 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 Level III Examiner, cables of other lengths may be used.
The length, type and number of cable shall be documented on the calibration data shee" (Figure lA).
5.4 The calibration blocks used to establish the system calibration shall be those (as applicable) shown in reference 3.1.2.
(Figure 4)'he calibration block used to establish instrument calibration may be the IIN-2 block.
\\
5.5 Transducers 5.5.1 5.5.2 The transducers used for instrument calib""ation should be nominal 2.25
- MHz, 1" diameter, straight.
- beam, ceramic, contact transducers.
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.
oaTE 3/29/78
'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 OF 6
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 6.1.4.6 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.
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 III Examiner.
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
'atio of two to one..
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.)
Initial Amplitude Set of FSH Table dB Control Amplitude Limi of FSH 80 80 40 20 6
-12
+
6
+12 32 - 48 16 24 64-96 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.
REVISION NO..
3 2 9/78 PAGE OF~.
r 7.1.4 7.1.5 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 To the maximum extent practicable the area to be examined shall be the weld,'nd the lesser of 1/2T or 1" of adjacent 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 examina-'ion requirements shall be documented in Figure 2 or other appropriate
.documentation form ~
7.1. 7 Where angle beam is specified in this p-ocedure it shall be interpreted as meaning shear mode 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 Reflecto 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 7.3.2 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.
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')
p weld 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 1itude 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 the search unit entry point, and the weld
.centerline
{Wp) when the signal amplitude decreases to 50 per-cent DAC when moving.
towards the weld from Wm-(1) Distance from refer centerline (Wp).
(2) Indicated metal pat to reflector distan Wm Distance between the search unit entry point and the weld centerline (Hp) when
.the signal amplitude is at maximum.
(1) Distance from refer centerline (Wp).
(2) Indicated metal pat reflector distance.
(3) Signal amplitude ir, at Primary Referenc W2 -.Distance between the search unit entry point and the weld centerline
{Hp) when the signal amplitude decreased to 50 per-.
cent DAC when moving away from the weld and Hm (1) Distance from refez centerline (Wp).
(2) Indicated metal pa) reflector distance,
8.2.4 8.2.5 SPECIFICATIOH NO I REVISION NO.
DATE PAGE OF 15 22 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).
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:
Examination 2:
For reflectors parallel to weld for full Vee Path or for.l/2Vee path in the direction of flow.
For ~flectors parallel to weld R
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 OF 16 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 SYSTEM PROCEDURE HO DATE EXAKrHER DATA TAKER
. REU.
COUPLANT Q/Preoperational g~I.S.X.
CALIBRATXOH'LOCK NO.
CALIBRATXOH SHEET HO.
XXN-2 BLOCK HO.
ASNT LEVEL ASHT LEVEL XHSTRUMEHT MODEL HO.
CABLE HO.
SERIAL HO.
IDENTITY FREQUENCY SIZE h
ANGLE BEAM CABLE TYPE RAHSDUCER DATA STRAIGHT BEAt1 XHSTRUMENT SERIAL NO.
CABLE LEHGTH SHOE TYPE SHOE HO.
SHOE ANGLE MODE PARALLEL REFLECTORS ORIENTED or TRANSVERSE COUPLtQK
'O HELD SEAM (Cross Out One)
XHSTRUPDHT Sr TTXHGS:
Start 1\\
.P I
~
~
~
~
50 10 0
0 OAC Curve 2
3 4
1 5
6 7
3 8
9 10' 6
. Uncalibrated Gaia Coarse Sweep'ine Sweep Coarse Range Fine Range Scanning Gaia Attenuation (in)
Evaluating Gain Attenuation.(in)
Filter Position Rep Rate Damping Reject FIGHT 1A SAMPLE CALIBRATION SHEET
'DATE PAGE OF 18 3/29/76--
22 Peale. Depth
".:"."nct2cs Gain 8 IX 1X
.1X Max.
Amp.
"W" Inch Oor MP Inch SDI<
or FDH Last Doto Shoot Time Valve initial Calibrar on Time Pef Iodic Checks:
3/4 TX
-,,iJ.O.
nt ci~
'/cO.O.
!otch N/A.
N/A
~'inal'Checks
.Colibrolionin Depth(O) Q or Melal Poth (MP) C3
~
~
Amplitude Linearity Check (Made Daily)
Control Linearity (Made Daily)
SGX "
t 80 70%%d "
40
100%FSH 6 FSH 40% "
~ 4 3(65 "
50'FSH H FSH 80%%dFSH BO%%d "
4!O%%d "
-6db (32-481 12db (16-24) o 6db (64;.961
+(2db (64-96(.
6004 ee ill/-2 Equip.'ata -Straight Beam For Linearity Checks
~ r Chocks on Iiy/-2 Block on I/8 SOH for Field Calib.
Transducer Data:
Serial No.
'eam Angl(r Size Shoe Ho Cable Ho Check Made By:
I/8 SOH Max.
Amp.
Metol Poth Near Far Chocks Q Max Amp.for Both Nec 8 For, Positions in % Screen Height R evievret I by SNT.TC Level
~
~
~
FZG.
1s s~Lz mz.zsmrzoN SHzzT
~ ~
ULTRASONIC EXAtQNATION DATA FORM REVISION NO..
gATp 3 29 78 PAGE OF Exam.
Form Cal.
Form Ho.
SYSTEM DATA TAKER SEARCH'NGLE SCAN SEHS:
X2=
COUPLANT
~Preoperational ~I.S.I.
DATE WELD NO.
ASNT LEVEL ASHT LEVEL U.T.
PROCEDURE EVALUATION SENS: Xl COMP TEMP EXAMINATIONS 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:
Perzorwed Indzcatxon Yes Ho Wo EI Inches From Ref.
Wt Inches Wm Inches w 'OAC IX Amp.
Inches Wm WI Metal Path Wm Exam A
s.5.'6 Sunning Mode fk Remarks ACCEPTABLE +
UNACCEPTABLE +
PER ASME SECTION XI FIGURE 2
~ ~
REVISION PATE 3/29/78'AGE 20.
OF 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 Ref Vl Inches Inches V
Xnckes XDAC Metal Path Exam Ho ~
Scanning Mode 6 Remarks Ll
'L 22'2;5 2.0 2.0 2.7 2.6 3.6 3.5.
50 85
- 2. 7,3.5 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
QQZ0 QQL.09i
')Iaiuli'. 'o,
~
4ovt A j)le"<<43 4>>I~<<>>c.. )'Isl
~.
I
~teeth) I<<v) 4
~ Iree t>>rlvteelJ
) C)sT C Cilssn
~
)sOCCTCC )ITIS'll)leTCCS Tto>>Iel ihhIhI
~ ets ))<<rt)%I ~
I
~ i
~ 11 CC
~I~
ole I
~s
~s
>> ~eto Ia<<o s4 <<seN t)e t)<<st el l)tttes>>l
>>)ss<<so4) st lr Iw))t e)l
')sess)osl tt Ivte)se)) 114 lo e
~ <<se lve eelv>>) ~ se>>) ~ se le le<<1
~ )esv ~ t)s)so
<<<<seNsl ) <<4<<)t)o ts ls<<4se I roe<<eN I t <<1 >eN>>tse)
N teal<<clues)e e)
~ e>><<o la I 1 tt4es)rl 1<<as ~)4v arts I) vet lttee
's>>>><<l oil <<o)l lv<<test ~ <<1>> lsseur<< ~sl >>1 soever) ls <<t ~) ~1st+tttAt
<<)11 ~I
'lt ~ lst>>
srN e4 t<<1 ~ 'lo 114 Io<<
over ICII"II'CTs
~I ~el)e) re I oo<<) 'I)eels ~ sl ae to<<<<11
))e s4 te)oee
'%ass 4 )t)vs) ls <<)>>4'svast<<vssv evoctato )>>
~ )~)seto)>>
~
~ ls
~ s>> <<eu
~Ittt l
I Ii I
~0
)act)s)roe<<)>> )ee la41 4)v>>rl>>, ~ s<<>>
a) 4
~4'lit
>> /
I
-3C r.
h, 14)u&rt 4 $4.)W I
PC'(
4 ls I:
Ila<<etio I~ i)s
~
lt)4.4
~
)ee) V4'le ee to)e<<r>>)4
,....5 C~.,
II)D l ~ v Y4:
~ ~
44 ~
~I ~
~tl
~te
~SI
~11 Cs) ')4 ih'l>
I<<
~ le jl' 4
I'l4 14 ~
~ Io I i
'ss)<<I
'l)T<<
IsC<<t
~SC v t)1 v le ols'ls
'4 I)
~eue
~So 11 I Ii@t)
~tlI~
oilTel 41st )v)te I
ltC)sIT)l)JJf I)tl 4
tiles )es))4
~
I I..l.
I Ii I
I I
I r
spelt
.1
~" CM IIIrt>>t )os) It>>)I I+X IC lol>>)lth~N4.5
~e C
I
~ 14ll)
I
~4gu>
l
~eg)C ~
J Q
a I
(COO3 3A'Sl OUTO)lnt NOllCCUQ)i@I LWL JCNOSVlll'NJ.
i'=.:.:4))itiL".-~ -.i.-' -, l.l"-'-'"-~i-
~ ~
~
NZO DBL 09l 0c ~ C)illQJ 11 ~ )Nl~
I I >
)
I 60 78C-0255 4
~
~
~ Q DATE 3 29/78~
2 22 =
PAGE OF
~
~
~ e
~
i
~
E.P.
~
g
~
~
~
Search unit wedge design must be such that.the distance from the enuy point (EP J to weld center line (Dim. A) is less than
)ndicated beloved, 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
NUCLEAR ENERGY SERVICES, INC.
il DOCUMENT NO.
30A277O R EV.
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 TITLE/DEPT.
UT Level III M r. Field 0 erations Pro ect Mana er A Mana er Prepared By Frank T. Carr UT Level III APP RO VA LS SIGNATURE'.
3ensen F. Carr
- 3. Hobin G..Oberndorfer
"" /~/
DATE
Q NUCLEAR ENERGY SERVICES, INC.
REVISION LO 8 DOCUMENT NO.
PAGE 2
OF REV.
NO.
DATE PAGE No, DE SC R I PT ION APP ROVAL 8)0/79 3
Added Para. 2.7 CRA 996 Para. 5.0 Moved parenthesis Para. 5.6 Mded "Change of transducers,
'FF107310 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" 2
(. 12/12/79 CRA 1109 Para. 8.1.2. (3) deleted "of reference level" Correct Project Title Added paragraph 5.1,1 9
De'leted "Opinion" from Paragraph 8.2.1(l) 10 Added last sentence to paragraph S.2.3.
REYISION LOG NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE OF REV.
NQ.
DATE PAGE 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 references 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 NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE OF 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 specified'erein shall be complied within a specific procedure, unless otherwise
~
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 Qualification and Certification of Nondestructive Examination Personnel" (Latest Revision).
2;5 2.6 80A9053, Revision 0, October,
- 1978, NES "Procedure for Ultrasonic Instrument Linearity Verification," as modified by Section 0.2.
- 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 NUCLEAR ENERGY SERVICES, INC.
PAGE OF 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 0.3 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.
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.
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGg 6
PF 20 52 Ultrasonic instrument calibration consists of two basic steps, horizontal'inear range and sensitivity.
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 P.3.2 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 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 reference sensitivity level.
5A Basic Calibration Techni ue (Pi in - 1/2 Vee)
NOTE "5.0.1 5.0.2 If half vee calibration becomes necessary on a Calibration Block that is
< 1", stop and report to the supervisor for disposition.
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.
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.
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO, PAGE OF 20 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.
'.6 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.
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 for the full 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 Asystem calibration check shall verifythe 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 IIexamination 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
.NUCLEAR ENERGY SERVICES, INC.
PAGE 8
pF 20 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 7.0 7.5 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 distance of two support thicknesses.
K-Th '*l I
hill ld I
I h*
length of each part.
The examination technique will consist. of an axial scan 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 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.
s NUCLEAR ENERGY SERVICES, INC.
DQCLIMENTNO, 80A2770 PAGE 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 7.3 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.
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 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.
The appropriate weld maps in 'the Program Plan shall be used to locate and identify each weld.
7.9.1 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.
DOCUMENT NO 80A2770 NUCLEAR ENERGY SERVICES, INC.
PAGE~OF~
(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%
. shall be
. investigated to the extent that the examiner can determine their true nature, as set forth below:
Qi (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):
(2)
(3)
"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".
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.
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 reference
- response, shall be recorded on the appropriate data sheet at the time of weld examination.
(2)
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.
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 Allangle 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,.ArticleIWB-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 the referenced ASME Boiler and Pressure Vessel
- Code, Section Xl, Article IWA-6000. 'll 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,
'oting applicable SNT-TC-1A levels.
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.
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO 80A2770 pAgp 12 gF 20 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> ~
NUCLEAR ENERGY SERVICES, INC."
DOCUMENT NO.
I'ACE 80A2770
. pF 20 Drawing No.: Bechtel No.: 00008 Cal. Std.
See Table below Too;ing:
.Manual Application of Search Units Drawing List:See Paragraph 2.2.2 SAMPLE,ONLY SAMPLE ONLY I
S - The larger of 1/2T or 1/2" E'- Volume of metal to be scanned; i.e. the weld plus S on either side.
P Length of Path Scan Limit Qo SAMPLE ONLY I
Counter bore length:, Piping = 2T
'ittings"=
1/2"., Elbows = 1T or 1/2", '
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 Pi e Dia.
Pipe S'chedule IISl I I 1El1 l-l/2 Vee 11Ltl Calibration Standard 2" Dia.
6" Dia,.
8" Dia.
10" Dia.
160 10 20
~.20'.'130"
.250" 25Qll 500" 50011 500" 5QQII 1.70011 I 7 QQII
.1 700" 1 700"
.7.86"::.
SES-XXX 1,000"'ES-XXX 1.000" SES-XXX
.1.186" 'ES-XXX 10" Dia.
12" Dia.
10" Dia.
16" Dia.
18" Dia.
2" Dia.
160 20 20 20
. 20 CEDM Std.
'1.125" 250
.312"
.312"
.312"
- 250" 5675" 5QQ" 5 0Q11 5Q 011
.500"
.500" 1.825 1.700" 1 700" I 700" 1 700" 1.700" 2;8125" 1.000"
, 1.120" 1.124'.120" 1.000" S~~XXX SES-XXX SES-XXX SES-XXX SES-XXX SES-XXX
'IGURE
.1 ULTRASONIC EXAMINATIONSCAN PATH DISTANCES TABLE ULTRASONIC EXAMINATIONPROCEDURES FOR CLASS I AND II PIPING SAMPLE ONLY
Document No. 80A2770 Plant/Unit Comp/System ISO Loop INSTRUMENT SETTINGS g/Model No.:
erial No.
ween Len th weep Delay L.lse Length/Damping:
-req.:
Rep.
Rate:.
-ilter:
Video:
Jack:
EC/Gate. Switch:
.Range lode Select:
Reject:
ain (coarse)
(fine):
Scan Sensitivity H~4 SEARCH UNIT Calibration Block. No.
Surface Block Temp Comp.
Temp Thickness CRT Calibrated in Mode:
Scan Angle:
Fixturing (i any):
St le or oe No.
Size
& Shan e:
Frequency Serial No/Brand:
Measured Angle Cable Type G Length; Couplant Brand:
Coupla'nt Batch:
CALIBRATION DATA SHEET Procedure No.
FIGURE 2
Sub ject:
Rev/Change No oF oF High Low High Low.
INSTR LZN=ARITY CAL Amplitude 100 90 80 70 60 50 40 30 20 50 DAC PLOT
'I
'I'" IIII t>
SCAN AREA 00 To Held M
C'"libration Axial Circ AMPL.
CON ROL LINEARITY 0
1 2
3 4
5 6
7 8
9 10 Initial iAI aB Result 80 80 40 20
-12
+12 EXAMINATION HELD/AREA Recordable Indications Geom No Yes COMMENTS/REASON FOR INCOMPLETED SCAN(S)
CALIBRATION CHECKS Initial Cal.
Intermediate Intermedia te Intermediate Final Cal.
l
~F CCEPTABLE.
ADDITIONAL SHEETS? (CHECK BOX)
EXAMINERS 1 Date Level ontinuatiorJ Supplements Beam'lot None Date Level Date NUCLEAR ENERCY SERViCES. INC.
INDICATIONREPORT SHEET PIGURE 3 Document No. 80A2770 Page 15 of 20 Project No.
Site L Location 0
Date: (Day/Mo/Yr)
I tern Iden tification hV 'Location 0
Page of
.'kl Wr Examiner:
TC-lA Level Angle 00 O5i rr5 II Attached Cal. Data Sheet Thicl<ness'xaminer:
TC-IA Level Ind.
of FND 50%
DAC MP Metal Path RBR Remaining Bacl< Reflection L
Distance from Datum 0 Scanning dB Diameter (nom.)
~ MAX BACKllVARD 50%
DAC L
L 2
. RBR EVmax Distance from Q~ to S.U. at maximum response.
Distance from weld Q at 50% of DAC (fwd)
Distance from weld <t at 50% of Wmax; (bacl<ward)
S. U.
I ~
I J Weld Q OalIIm 0 lV
'~'o.
DAC max 50%
DAC amp Loc.
REMARKS r
MIL Ul ETt ES
-AT-l NA 8
RlC CBE lkernarl<s:
Lirnithtion (Describe, i.e., valve, hanger in'scan'path 3" from weldI L position 2, etc.)
r ~
IIMI NUCLEAR ENERGY YICI=S, INC.
NUCLEAR ENERGY SERV1CES, 1NC.
DOCUMENT NO.
'AGE~OF~
METAL PATH CALIBRATION TABLE IRI/2 YEE SCAN PATH EXAMINATIOH hletal Path Calibration R
red 5 ll 05
> Material Thickness Kan e 60
0.5" - < 1;0" > 1-0" < 2. p" Q 5ll P 5ll 2.0"- < 0.5 1.6" - < 3.3" P'll ~( 2ll FULL YEE SCAN P ATH EXAMINATION Metal Path CaUbration ~'equired 0 2 5 ll 05 material Thickness Range 60 ~, 70 ( Q rill 0 ll 10.0 " > 0.8" - < l.?" > 1.7" - < 3.5" > 0.6" <<< 3.2" > 1.2" - < 2.5" >0.3"- <1.6" 20.0 " > 3.5"- < 7.0" > 2.5" - < 5.0". > 1.6" - < 3 3" '/2, YEE SCAN 'PATH EXAMINATION Metal Path Calibration Required Q5 Material Thickness Range 60 70 ~ 2.5" 5 P ll 10.0 " 20.0 ". I 711 > 1.7"- < 3.5" > 3.5" - < 7.0" > 7.0" - < Irr.p" 21' 1.2" - < 2.5" > 2.5" - < 5.0" o'5.0" - <,'}0.0" > 0.3 < I.6" >1.6"- < 3.3" > 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 Left is the Metal Path Calibration to be utilized. FIGURE 4 NUCLEAR ENERGY SERVICES, INC. DOCUMENT NO 80A2770 PAGE > 7 OF ANGL" BED Vr.RI ICATION BLOCK R-1 1 in. 30o N 45o 60o 0 0 2 coo 7oo 3.00%, 90 80'0 60 50 40. 30 20 10 1 2 3 4 5 6 7 8 9 10 TM PATH CPZ'IBRATION FOR A 2. 5" CRT 'PR SENTATION '2-Obtain a maximized indication from &e short radius (R-1) reflection surface of the "Y~iature ogle Beam Uerification Block" (1".metal path). Using the material calibration control and.the delay control, align this signal at CRT position 4.'evolve the search unit around and obtain a maximized indication fr'om the long '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 1 in. 30o~~45o po ~ '0o p '2 inch P 6po 70o R-2 100 90 80 70 60 50 40 30 20 10 2 3 4 5 10 MTAL PATH CALXBRATZON 5" CRT PR=SENTATION 'I 1'- .Obtain a maximized indication from Me"short radius -(R-1) reflection surface of 'e "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 NUCLEAR ENERGY SERVICES, INC. ppCUMENT Np 80A2770 19 20 PAGE OF G>~ B:PA 9:"RIPICATION BLOCK r 1 in 450 600 Oo 30o Q 2 in. 60 70 100% 90 80 70 60 50 40 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 NUCLEAR ENERGY SERVICES, INC. OOCUMENT NO 80A2770 PAGE pF 20 'NGLE B~~i V.RIFICATION BLOCK R-1 R-2 100% 1 30 0 60o 70o 90 80 7Q, 60 50 40 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. NUCLEAR ENERGY SERVICES, INC. DOCUMENT NO SOA2771 REV. 'AGE ~1P ULTRASONIC EXAMINATIONPROCEDURES FOR PIPING WELDS SUSQUEHANNA STEAM ELECTRIC STATION UNITS I AND II PENNSYLVANIAPOWER AND LIGHT COMPANY HNCONTROLLED COPY Project Application 5553 TITLE/DEPT. Prepared By P. T. Carr, UT Level'II APPRGVALS SIGNATURE J. Jensen J. Hobin DateVV DATE F 17/7'f'. A. Manager G. Oberndorfer NUCLEAR ENERGY SERVICES, INC. REVISION LOG PAGE OF DOCUMENT NO 30A2771
- REV, NQ, DATE 11/19/79 PAGE NO.
D ES C R I PT I ON Added paragraph 1.2 (3) JJH APPROVAL Paragraph 4.1, Added last sentence Paragraph 5.1, Added item (7) FF107310~ / Paragraph 6.2.5, changed "figure 12" Paragraph 6.2.2, changed "figures 1 through 3" to "figures 1 through 2" 10 Paragraph 7.3,deleted "full" from title 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 REVISION LOG NUCLEAR ENERGY SERVICES, INC. DOCUMENT NO. OA2771 PAGE ~OP= 1 RE V. NO. DATE PAGE 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" REVISION LOG NUCLEAR ENERGY SERVICES, INC. DOCUMENT NO. PAGE OF 17 REv. @ATE NO, 5/12/81 PAGE NO. 13 DESCRIPTION Deleted Note, -7.3.2 (2) deleted parenthetical statement 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 APPROVAL and 41 ~'( NUCLEAR ENERGY SERVICES, INC. DOCUMENT No 80A2771 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 1.0.2 The pipe and safeend weld configurations covered by this procedure are shown in Figures 1 and 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 NUCLEAR ENERGY SERVICES, INC. OF PPCLIMENT NP 80A2771 PAGE
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 shall be ultrasonically examined using 05 angle beam 0
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.
If the use of 05 angle beam technique is not effective, 60 0
~
~
0 angle beam techniques shall be applied in the same manner.
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
80A2771 PAGE 7
OF-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.
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE OF (2)
%edges:
05 and 60 angle beam (shear wave and refracted longitudinal) to accommodate search units (I/O'r 1/2" aerotech only) for 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.
For 1-1/2 Vee techniques, wedges 05 and 60 angle 0
0 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 finishing).
(7).
Drawings of each Examination Area.
(3)
Post-Examination Cleanup.
6.0 CALIBRATIONREQUIREMENTS 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.
/
NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
17 PAGE OF 6.2 Calibration Standards 6.2.1 6.2.2 The Miniature Angle Beam Verification Block shall be used for basic instrument horizontal linear range calibration.
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.
7.0
+NOTE:
The examiner may refer to the individual weld "T".
maps for 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.
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 reflecton 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 follows:
(1)
Adjust the instrument sweep controls so that the examination area is displayed on the CRT screen.
Mark the horizontal screen positions selected for the hole or holes directly on the CRT screen and on the chart on the Calibration Data Sheet.
(2)
Position search unit to obtain maximum response from the side drilled (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
V I~'A'UCLEARENERGY SERVICES, INC.
DOCUMENT Np 80A2771 PAGE 10 pF (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 follows:
(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 7.3.2 Calibration shall consist of two basic steps:
Metal path for horizontal linear range and sensitivity.
Refer to Procedure 80A2770 for the appropriate horizontal linear range calibration (metal path).
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.
t NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
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 full examination thickness.
NUCLEAR ENERGY SERVICES, INC.
DpCUMEMTNp 80A2771 PAGP
. 12 PF 17 (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 for Interferin 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.
'.2.2 8.2.3 The search unit shall be swivelled (if possible) as it is moved along at a rectilinear scan pattern to ensure a minimum of 2596 overlap of the transducer width.
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.
NUCLEAR ENERGY SERVICES, INC.
DpCUMENT Np SOA2771 Pcs F 1~
OF 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)
(c)
Record search unit position with respect to weld centerline.
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.
,V NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO 80A2771 PAGE 14 oF A
B A
60 45 45 60 Y K Wield Width A 45 Scan Paths B~60 Scan Paths 0
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.
I NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
PAGE OF 15 SCAN PATH TABLE 1/2 VEE THE ESS SURFACE DISTANCE 45 SURFACE DISTANCE 60
.2 0" W+
0"
.251" to.375"
.376" to.500" W +
75" W +
75" W + 1.00" 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.
1.751" to 1.875" W +
2 W + F 00" W + 4.00" 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 ~ &A 1CC ACt
NucLEAR ENERGY SERVICES, INC.
DpCUMENT gp 80A2771 pAGE~GF SCAN PATH TABLE FOR FULL VEE THICKNESS SURFACE DISTANCE 45 SURFACE DISTANCE 60
.125" 'to.25" W +.625" W + 1.00"
.251" to.375"
+ 1.00" W + 1.50" 7
II o
0 II
.501" to.625" W + 1.75" W +
W + 2.50"
.626" to.750" W + 2.00" W +
3 00"
.751" to
~ 875" W + 2.25" W + 2.50" V +
3 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" 1.751" to 1.875" V + 4.50" W +
4 75" V + 7.00" 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 205 2/RA
F NIL NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
80A2771 PAGE 17 OF SCAN PATH TABLE 1 1/2 VEE THICKNESS SURFACE D ISTANCE 45 SURFACE DISTANCE 60
.125" to.250" W + 1.0" W +
1 50"
.251" to'375" W + 1.5" W + 2.25" 7 6lt tt
.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" W + 6.75"
+
.2 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
HCCO IOCHlllT eo OSS III I t
I C
L 0
8 C
0 C
0 C
A A
4 5
0 A
0 0
C F
H C
5 4
P 4
0 0
C F
0 H
J 5
4 0
0 C
0 H
J 5
0 N
0 4
5 T
0 0
0 0
0 C
NII 4
S IllI IIII I 4 C 5 4
5 5
5 5
5 5
5 5
5 5
SC 5
57 1
7 P
7 7
7 7
1 ~
0 5
0 0
~-5 5
5 5
5 S
S S
'5 5
5 5
5 N
'N 5llC ITPC 0
0 4
F F
F F
0 5
0 0
0 F
F F
F F
F F
0 Ie F
F F
0 F
F F
F F
Ff 0
F F
F F
F 0
0 0
0 0
0 HP IO'O'O'OOO'ITPC OF HOC VOL SA SA SA See See See AA SA KL SA SA SA AA See Aa
~A IIA An VIIL ISl ACOO SCAPI 088 ll4 I~I DBB II4'I FW II4-I~I ~ 0 D
.II.I.I 0 DBA402 SEE ISO DBA-l02-I ll4.I FW IEB'II4 I 5 8 Q
IO 088 II4I 5 A
-II4.I.FW 6 1$4 LSe N
.IN.I~'I C SI4'I'I II&.I~ FWH ll4 I +0 ll41 2
088 ll4 I FW IS
~ULIII~FW cQ 5$a
.r
~ 0 a~~CI 88-II&-I FW 3 CR ll4 I~
ll4-I FW 4
~
5 ~
WP. L 694 CEB-II&.I~
A iS II4.l 5 A
-II4-I FW.
088-ll4 OBB-II4-I-7-A II4-I I A
~~-uS~.
SEE ISO II4.l FW 093.IIS l RHR STST9l 088 ll& I IO fl4'I FW'
~ I~
-8 088-IN-I~
0 YlP. EL66l-0
~
088 II4 I
.I7
-II4-I
~ll4 IW
~ll&.IWA
'oc yQQ i
~
88II&I C
088-0&-I 0
lURBSIE STOP VANE C88 I& I FW 8
~II4-I~'T-REF EREIICE ORRHIIIGS OOS-u&-I ACT. 4F9
~ Oh' e
~ CH III PA 4 /Z re ee eeeeeeveeeie va
~eerree rer cnr1I'
~.el.b-ne e tfXXCTLVAXIAPOWEA 5 UGXI COQPAXY aaaeasaa eewe aenae eeaeeeee.em a wee
~eeeeeei.
Ien 111vosco INSERVICE INSPECTION ISOIMETRC VIELO IOENTIFICATION ISI-DB8-114-1 Qiig 4
I Si.
85s5 ISI-088-1141 eeeH
% eeee
MELO IOENTITT 044 IIS-I.
ts
~
IO'
~
IO'
~
lo'
~
N'
~
~
N
~
~
Ir C
~
N' 4
4 Ir
~
4 Ir C
~
IO'
~
4' s
4 r
4 4
r L
SIZE AO.
TTPE I
4 IO'J TTPE OF NOE TSI Rf00 (TEARS I F DBBRI
~
.A 088 HI5+4-8 88'I I5'I 4 f
r Ideee-44 SEE IS0 oee-ll4.I
~II5 I
~
D
~IIS(. -A
~ll5<-5.
lo OBB.IIS IIS'I-FW4
~
r 0
4 r
c 4
~
c 4
r 4
~
4'
~
088.!I5R.FW-
-II5-I-
~I 8
IISR+
EH qp topi~II ~A
~
~e<<- I-20-088-I05
%0 SEE ISO 088905 2 r (
-II I-FW-I C'~WI~A. F'y-g2 088
- -Fw-REFERENCE DRAWINGS Iws-IIs-I RET. BF6 L5J lCC NO I 4-7
~
~
r 4
~
4'
~
4 c
4 r
F 4
4'
~
4 N
4 r
TI
~
C'z 4
r Io
~
r
'IIOL 088 11.I 88
~I 86
-FW-I HI5.I.7 88 45-I 7-F
-FW DBB IIS I-FW 7
'05%
05~
088-II5-I-FW-8 20 GBBHOS SEE 150 Iree IDS I SC. CSJ II-ISI TPIWN: ~ P CHkp:
/-w/z ISs VASSS'SEPSIS Ir SS Wsrrr ~rrrrr. S~I ~ r
~ p s>>
s>>s
~
mss ~ ~Q,Q. s>>>>CA.sT. I PENNSTLVNNA POWER 5 IICNT COMPANT
~sssrs>>>>>>>>s>>
s s
~owwlwlssssr sLsssss ssatsr>>>>s Ls>>s ~
HOIIIL ISS IlkAOKO INSERVICE INSPECTION ISOMETRIC
'IljtELD IDENTIFICATION DBB-II5-I fg/17 ~ f, O~P IS I 4
AC RL C
Rss
~
s I
~
>>s l55$
ISl-EBB-115-1 I~ 0 VPR
MELO IOEIIIITY rc L
~
TYPE ISO INR IIR I R
IYPE ISI SIRE OP RECTO NOE tEARS)
VOL r
II IFW 30'OBD-I0 I SEE ISO DBO-I0 1.2 (EXEIAPj) r~
r A
410?A ABB 121 SEE.
ISO OBB-121%
24'OLA-IOI SEE ISO OLA-I0 I I I I 8-I REFER~A OCLwurre5 OOO IIS'I aatc9F2 t51 IXa roo.I SIC.E5t Mill H
~
P.
w rl'?I-Tf CACQlttl+tjtt 1 K j)
+ ccckrtc
)
Atl 1
~ cc rt lcArcil ROc ccraktc
~0 P M ~
MO
~C AP tfNNSTETANIAtOWER N UGNT COMPANT CCC~raaeme~
04OCWaalflkeCLCCf&PLllee Wf1,Q 1 ~
KCNltl tillICCKCCCO INSEIMCE INSPECTION ISOMETRIC SELO IDENTIFICATION 1SI"GBB-11B-1 I
saweww se
'1 NITS 1SE-DBB-1IB-I NIR <%$4
~ r MELO I0OITITY ISO Rs ELO TYPE as.I07 I I I
H TYPE ISI SIZE OF REDO AOE IYKARS F
SUR ga II
. ft 0
1 C
1 A
F t
A 4
2 E
2 F
lts IO srL ASS SCL SUR VOL SUR VOL SUR VOL SUR VOL SLYI VOL SUA VOL SUR 2ICCA GT IF006 I2 OCA I07 QCA IC7 I F Wa4 A I 7 I FWQ 07 I F I2.0 CA% 09 7-
~
CA I 7
C.
OCA 107 I CA.I07 I 2 9 OCA I07 I.FW-S NSB IIO 0 IA)
OCA 107.>FW.
/
OCA I
-IFVH A I07 IAAF 0 CA IOZI OCTO%.l.
I2 OCA I09 SEE ISO OCA.109.1 REFEREIICE ORAlllRGS Ntl-I07-1 RSY.I IFI Z5J LtC 100 1 SC LSL S ISt OWHr 7
ca'arr l2480 ClK4AfI~R s cc.
fssass wC cps 4*
~ ~ ~AIL~CAa
~ENRSTNAIIIAPOWER 5 USIIT COMPNN
~ ssssrssaaaa
~eaaaaaa srsass sascrsc carcass.asar 1 sass ~
~Ssrrrls ISSS rcklsOSCO INSERVICE INSPECTION ISOMETRIC WELD IDENTIFICATION ISI-OCR-107-1 WO ttSS'ST-OCR-107-1 I
USA Casse
LO TYPE SIZE Nl I07-2 J
F I
t
~
12' 4
lt' L
It L
I2' 4
A 4
lt' L
H L
lt' 4
12 0
I.
It' L
lt 4
~
S 0
10'IELO IOEHTITT ISO TYPE OF HOE
~CL TCL TTL SUR TOL SIR VOL SM lOL SVR VOL SUR VOL RE00 TEARS
~3 IIOOIA)
OCA 107:kF'.
It%CA l07 CA407.2-2 GCA 107.2 M)
OCA'107 2+W4 Al 7-0 C A.107 2.2-4 2'-OCA.I09 SEE ISO O CA l09.2 IO LA N
E F
F F
OCA407 FW-2 OC A407-2 A REFERENCE ORRMINGS OCA 107 2-I.
aR-107-2 aET.I IFI TILLISC l00 I ae'O.-
Rk IRIT4d Kkrrk rKrrrkR *4 ff P
~kkk~ ~ 4.0.
~
C 44 PENNSTLVANIA POYTEN N UGNT COMPANY
>WHYKWtlku&
MEMWVrNkkkka Rkkkkk kkkkkk kkk1 LI&II KOrtTL TANtkkKklCO INSEIMCE INSPECTION ISOMETRIC WELD IDENTIFICATION ISI-OCR-107-2 QTR C'TkR
7 ta MELO IOEIIIITT lac.
~
TTPE Nl IIO I lTPE SIZE OF MOE tc ISI REITO TONS)
I I I.v I
IOt L F N
tla
~
tla 4
tie tea tie M'N A
I I
lg +/r OSO A II a-I I-4a-MAX A-IIO.I~-P la aa
~
tl'la le 4
.tla LlI N A-4 I-4
- I'.0 I-v TI A
~
-U -I~
MAX
. 24-DCb-I IO MIII OCA IIO I I A II I
I MAX 4A Seal VOI.
SUR VOL SUR VOL SUR VOI.
SIIR Vba.
SUR VOL 5UR VOL SUR VOL SCAl VOL 5lN VOL SUR VOL 5UII VOL SUR VOL SUR VOL SUR VOL SUR VOL MIN A
I 9 I
A. I I
A MAX XHSA A II
-I SEE ISO DBB.GT-I r ILEFtkKLICE OkLWIlaIOa%
DCA.IIO-I REv.gg 5l LOOa IOO.I SK ISE IS I ERIVII:
aavo ORXb.
A9.4g
/- 9 /Z re lv a
ae aLT CVel a
ncvco aac c.naca R.
ae vaa n
~CAP vea PEXNSTLVAXIAPOWEII ta USE COMPASS aaaeaavv aaeenaaava
~Jeeevvv naacp aaanee aaaaaea.aeea ice ~
aaoacl c Caa IJJeaaaaa INSERNCE INSPECTION ISOIIIETRIC VIELO IOENTIFICATION ISI-OCR-110" 1 I ~ee QiiQ 5 I 4
i D
t!SI 1SI-DCR-IID;5 ala jacal
OCII 110 S oo ol.
SIIE IVPE IIELD IOENIII'I IVPE OF NOE ISI RED'EIIAS II d
~
d C
S S
d S
d S
h 0
F to'or It S
tV
'LL
<<EI 60 OCA-IIO- -Af.
-I
.FW MAX OA OA 0
L 0
L E
L 0
L E
L F
L 0
L II L
L A
d L
F C
L 0
L C
L 0
S t<r h
F 10 VSL C
SVII SOS Sgl SOA VOL SOR VOL 5IJA VOL Sl'll VOL S~W SU A vOL SOS VOL Sdi VOL SV4 VOI.
VOL SU4 MAX A II A II
~
~ I
~ - -
MIN A II
~ I MIN A-OCA-110-2 I-A OCA I
IH 0 4>>
- -FVI-4 A
.:S'5:
X<<SB kit c <II ISe OCA-II
~
FVI-OCA IIO.t FIV I eD @a oee.
~op QiiQ I
I MAX MIN II 44 A
MIN a-u 4.
OCA IIO 2 6
II.
-A Al FWY RRFERBLIEB DRAWIHCsto DCA IIQ 2 AI~IIF6 ZSE LECa IOO.I SE.ISS M ISI CRStN: '
S>>Pi 4
cnr o o sss0carto
~
n P.>>
.ttooo ooc cow\\I Ja ~
r I' I
QI ~ )
IV\\
~awe ~ ~tr.
~C.A.R PENNSYLVANIAPOWER 6 EICHY COMPANY
~ NepsTlr~
asAAAavlwI~Kit ac ITOHA IsrtAto KOITtl KO ttusOICO INSERVlCE lNSPECTION l5OMETRC WELD lDENTIFICATION ISI-0CR"110" El et ssss isE-Oca-IIO-al I
8@4 VLl
FO L
IRL ITPE MELO IDENIITT SIZE Rta TYPE ISI DF REDO NDE 1 YEARS I ~av II
~
0 C
~
0
~
0 0
0
~
0
~
0 h
~
0
~
0 0
C
~
0
~
E
~
F 0
0 1
~
11 0
0
~
C 0
0 0
E 0
F 0
0 5
0
~
0 0
~
~
~
C
~
0 0
fl
~
0 0
C 0
0 0
E
~
F IO
~
Zta Eta 2ta Ia LA 1021 W I CLAIC I Ok
'llO L AI aT IO LA ICZ I 4C
. L A-Io""I-0 AIDE I 5
OL Aw0 2-1 F T)
I.A OL A 1021.7 E
Q A I If 0
AHO I FW I v C A-IG I 5 A (p
QLAIQ 'I FBI F)
Pp PO lq OLA-I0 2.168 0
A40 -I-0 LA-102-1-F.W-aa O'OL" QLA IO2 I 7 8 NO A
Sl FW DL s 102.H~
eZI 0 I I' i 102 i
I LA 102 I IC Dt01 f
OLAHO2-110 240L ANOI
~ SEE ISO
.F. ~
QLA-lol~I
.F AO9 M'A 1021'FW 3 OLA-102 I 2-A OL ANO2.1 ~
EEFERENCE FRAY>>IN4 FLA 102 I RSV SF9AI EST L14 IDO.I SIOXSE.M III 0
A 102 I BA
>>aa>>
ISZSVI A-102 M A A-I.F W a ~ aft>>>>>>ONvt AC I F Jv vv>>a ab wvavta
~
sfv
- ttolo a t tov>>ft v
va vaa
~vv~
avvv Cs. ~ C.A.P.
FEEESTLvAEIA FQYYER a ucer CQMFATIr
~aa~
aaaa>>aaaaaaa vvvaaaaavaaaaaav>>avvaaaa v>>tvaf ~
~>>Oaftt faV>>aaaaOSCO INSERVICE INSPECTION ISOhKTRC WELD IDENTIFICATION ISI-DLR-102-1 4'SSE ISI-OLA-10Z-I 2 D>>Lt %oft Oig 1$
1 RIOC OLOC CONf
MELO IOENZII5 re'4 MO.
C4PC IAA 101 I g
I 5
I" II
~
1.
5 F
1 5
~
1 C
5 I t
~
I 0
1-2 3
~
t 5
~
t A
5 TCPE 151 SIZE OF REOO MOC ircen DLA 104 I I C 0 A404 I-I.B A 104 I FW 5 4
FW'I V
821 FOII 12'DLA 104 SEE 150 D L A-104 2 0
-I F'4 2-3 4
5 II 5
0 A 104'I I DLA 104 I-I-E A I 4110 LA I 048 ~ FWO J
A 104-1 9
OLA IO4 I 4
4 I FW.
12-DLA-104 SEE 150 DLA-104 3 I?DLA-104 OLA 104 I-3A 4~ I 220 LA-I04 SEE 150 OLA-104-4
) ~IH04 eSQ IS I ac AC eCCS
-Car REFEREIlC't ORA WICICsS FLA.IO4 ~ I RLV.SF5 ESE LEO 100.I 44 ESE-I4.141
<I-IS 29 II'a ~
~ P.
Iul II2O ~
awsems sa nC, m r AA Il
~ A s4KÃlO 41 HQII SOC CON!TC Cc tw Wl P
~C AF FEAAETLVAAIAPOWEA 4 EIGHT CGIHPAAT sea~ rvweva vasas
~04alaaa RIAANKIACifksO>> lail\\VLCC
~CC4CC QBCIRRO INSERVlCE INSPECTION ISOERIC WELD IDENTIFICATION ISI-DLR-104-1~a 2IEE ESE-ON-104-E
5j tx Xl Sg ig ff ga fa R)
II~
g) ji gi IIECO IOENIIIY ct C.L x NO IYPE I
I
~
II R
l C
R l
F t
I O
R II t
l L
~
lt A
R t
II t
t t
~
t P
~
t 5
R t
R SIZE tco lYPE ISI OF RCOYI NOE IYCRRS VOL QBIOS I FW5 gRNR IE-205 A
-QS.I FW.
I H
e5 PI I~.F GBB-IO -I-G88 805 1.2-A
~/FV Oglr 20 GBB 65 GERS-I I<
GB-I.I-O I~I-C
- 65. I-I.B G
IO5-I Pe 2AS 04 5EE ISO GBB.IO4-2 r
GBR.CS-I FW-GEB-CS-I-PJf.3 Ir ~0'HBBM 5EK I50 HBB.I20.$
Ll~all
~ IO5 I.I A 6IXBHIS 5EE I50 tea II5-I REFERENCE BRRRINGS N-IOS-l RCY,SA I Cfd LCO gO-'I NC LSr II ISI EFFRE OCa 22@
F I w-rr.rt CL.~ CCCCCCX XX CCC wX CCCcCX JNC X~II AIL
~ N
~dA ~CA.O.
tERRSYEVNIIA tOWER 5 UGIIY COLLPAIIY
~ cf~rawa
~ Ctlka CLCCCaCclaaoaCLlew C
~CCCCCCL CCCc ILAleccxco INSERVlCE INSPECTION ISOMETRC WELD IDENTIFICATION is?-BBB-105-1 QQiiQ SI RIACI L
4 N SSSS 151-GBB-105-1 Ncxx VxcCL
1SO HSt lPl I SSELO NO.
ZYPE QKLO IOEHIIYV SIYE TVPE SI OP ta 0
IIOE S124tS VOL VSSL H
IOI'I FW 3 H
.IOI.I FW 4 H
-IOI.I FW-2 H
I.I FW I VOI.
~a III IO'H88-IOI I
SEE ISO H88-IOI.2 I
X 2IS
~ REFERENCE ORRRIHGS sa-e-1 tcv. YF3 LSJ Llt @XI-I SSC. L5J IS Ht
/t as QQiiQ SS r
aaaaassaco sac asswss aisv caasv p.
AN
~ M
~aaa ~
aMaaP.P ~ g.A.P.
PENNSYLVANIAPOWER N UCNY COMPANY
~aaaaaaaa aaaaassaaaaa alalaaaa lalaa laallwas alNa laallaaal a wpassL sais IaaaNsco INSEIÃICE INSPECTION ISOSVETRC WELO IOENTIFICATION ISI-HB8-101-1 AE 1
S!SS 151-H88-101-.1
?.
~S ~ N WSal
ISO IIELD
'tYPE MELO IDENTITY TYPE ISI SIZE OF REOD Iec IYEhtS
%g'a tr Ir
)I
~
mi
)m'j
.Ij 1
j>>r 2
h 23 4
0 0
0 C
4 0
0 tV VCL tV 2V 2V 2V 2V VOL VOL HBB IIQ FW I II
>>A H
-Il.
~
HBB II I
~
4 4 H
~ I H
- I
~ -FW.
4'O' 24 H88 IIO 2Q fEIB.III-2 SEE ISO HBB III-2 RHR Furtp suorloH IFL2028 PgiV HBB IIO.2-4 F REFERENCE ORRRIRGS Ihh IID 2 hEY>>BF2 Lar. LEO IDD-I SC LKLh-LTI CAIIII I 9 BI YA>>>>>>W>>AAAO>>ll Y\\
ctao
/M E r s gz
~
ll>>C) foA coKAYA
~ rrll
~r e%
>>>> ~
$ I RE R
~dD.
CAD FxltasnvhRIh PBVTIR 8 IIOBT COMFhar
~>>>>r>>>>>>A~>>~
Mhowet >>r>>rr>>>>>>>>>>>>>>>>>>11$ >>>> wrLwl~
~AO>>ill IAAIAAAOLCD INSERWCE INSPECTION ISOVZTRIC WELO IOENTIFICATION rsr-HSa-sm-a
~rr tITC JSI-IIBB-110-2 J D>>4 O'SO
l l
Lt R
x0 I7PE RELO IOExrllf 5!rE rrFE OF HOE lsr SEC'0 IYERRS 24 HBB-II0 SK ISO HR-IIOIL II-2 SW HM I II~ 2-FW.IB H
II FW-le
, l55 tJ'>>
I
~
5 4
4 5
5 5
5 5
5 5
5 II 0
c 0
E F
R C
5 5
II 7
0 0
C 0
C 9
0 0
0 0
0 0
0 0
0 0
0 0
tO'O'Ir RV RO'V 26 HBB-II0 II-FBI HB -al-FW-6 HBB III-2 34 H
-III 2 III9
~ III III 2
-III-r
~ g>>O Y
BO~SB.III H99 III~ 2 S.E
~
HSB.III 2.8.
Q~ll.
~Ca I%B III2'~
@8~II 2-F'W I3~
II I
.FW-l2 HI 2 A
ff III 24-A HSB IH.2.FW H
.HI~
~4C x e-Iw- -Fw e H
III 4 A K
4 II-FW-IS I
~
A
.HBB-III
~.
III FW-IS HBS-III 2 x III 29A 88 III 2 FW I K
-III '2 6 E BB-III 2 6.
III 2
~
K lll 2 C
K III 2'64 SEE ISO HBB.III I XBS-III 2 FW.4 REFERENCE DRRMENGS 5
C CS 7
7 1
~ '
IO Q
ll R
It II S
C 0
E
,f IC II IS lr 4
0 0
0 4
5 0
0 0
0 RI>>
RO'O'O'O'O'O'O'O'O'O' 8 IH I'A Hee->>H-
~ FR ~ I
- 24. HBS-II0 SEE 150 HSHI0 I K
III 2 FW 4 HBB-IH-2 2 A H B. I I I FW 2
H III FW 3 H
-I
~ FW.
tEgll3 I S I R
0
>>I HBBH124 H
III 2 FW5 III 3A K
~III 2-3 9
~83..;I I-2-3-F L
I
~I INS-III-R REr. 3R4 LLLLEC NN I CC, LLLII l51 0
.RLrT IO>>>>>>>>I>>Pro>>c>>
o c. r
~de ~cA.o.
CCCC EST-HBB-ill-2 I O>>S C'OOL PERRSTLVAR IA POWER 6 EICllT COIEPAMT
>>l>>>>>>>>>>r>>>>>>>>>>>>l>>>>>>>>>>
IASlwaQ>>>>>>>>>> >>Kf>>c>>>>>>M>>>>>>>>>> Sl>>>>>> )
~IO>>rrl IJO SO>>>>OICO INSERVlCE-INSPECTION ISOMETRIC WELD IDENTIFICATION ISI-HBB-111-L
MELO IOPNTITY ISO 00 MELO SIZE Or TYPE TYPE OF=
NOE ISI REQ'0 YERR5) 088-I 14-1 QBB-II4-I-FW-I 088-1 I4-I-5-8 088-11+ 1 1
1 1
1 1
1 1
1 1
1-2 2
2-3 3
3-4 5
5 5
5 5
5 5
5 5
5 5
5-6 6
6-7 7
7 7
7*
7=
7 7
7 7
7 7
7-8 8
8 8
8 8
8 8
8 e
8-9 9
9 9
9 9
9 9
9 9
9 9
9 9
9 10 10 10 1
E L
6 H
J 8
C 0
2 R
3 R
R 5
8 R
C 0
E F
G H
Jr 6
R 7
R 8
C 0
E F
G H
J L
e R
8 C
0 E
F 6
H J
9 K
P 0
R 5
T U
R 8
C 0
E 10 11 8
8 8
8 F
F F
F 8
8 8
8 8
8 8
8 8
8 8
8 F
F F
F F
F F
F 8
8 8
8 8
8 F
F F
F F
F FF.
8 8
F F
F F
F F
F F
8 F
F F
F F
F F
F 8
8 e
8 e
8 8
B 8
10'0'0'0'0'0't7'0'0'0 10'0'0'0 10'0'0'0~
10'0'0'0'0'0'OL b44OL QN QQ QR QX QX QQ Qlt VoL.
QLT SUR QR SUT4 QR QR SQt SW VO4 VOL
,DBA-IQ2 SEE ISO DBA-t02-I DES-II4-I-PN+
088-I 14-'I I L DBS-114-I-I - 0 083 "II4-1-5 -A D 8-II4-I-R4/-6 BB-Il4-I-4-A 088-I 14-I-FW-2 D88-f14-I - RV-IB S
114-I-FVH5 DES-I I4-I-FW-f gO W.P. B= 694-3Q DEB-II4-I-3-A
-II4-I-I-C 088.1 I4-I-I-8
. gp/I4..r-
~o BEI-II4-I 4 033-I t4-I-RV-te fd-DBS-ll4 098-I 14-I-FW-tf 033-1 t4-I-FIV-3
- OEB-II4.1 98-II4-I-I-'2-A 1
Id- 0544.115 SE ISO DBB-IIS-I RHR SYSTEM DEB-Il4-I-IO.
I -I-9-8 DEB-l14-I-9-C
-I14-I-RV-QB3-1 t4-I-FW-I QBB-I 14-I "7-A Y/.P. EL 661-0 D88-II4'- I-FW-17 8 - I14-I-RV-I3 I
0 Tl 14-1 <8-9
-f14-I-RiY-IZ 4veL
-II4-1-IQ-B
@yP
'0
" o+
cP Of&ll+Ir9E 081-1 14-1-9.0 TURBIfbtE STOP VANE DEB-II4-1-FW-8 088-Il4-I C 0 8-II4-I-8-A REFERENCE ORRMINGS 088-11+-1 REV. 4F9 L5L LEG Sr, LS.L K-155
- DMt
~0.:Z-I tf0 O0.~~ %
~4,'SSucQ mw csun.
Nor
~IIrr.
~ bOA Ter
~~ ~~ 'eC.LO.
tHINSYLYANIAPOSER db UGHT COMPANY ALLTTTTTTrrb4.TCbbrTTLVATIIA RROVEIIAJWA5TTA44 545CTAIC TTAT141rl 4WIT4,TIbblT T G
1 1$ I RERCTOR BLOG H
Cl I
4
'.8 ICWXL-SATT $44AT4dSCO INSERVICE INSPECTION ISOMETRIC MELO IOENTIFICATION ISI-DS8-114-1 WSa WOet OE
~EV.
8 85d ISI"088-114-1
4
~'I
ISO o
NO.
TYPE 1
8 FyG HeJ SeC OiE iIELO IOENTITY SIZE 10'YPE OF NOE VOL ISI REQ'0 iYEARS I(f-DBB-ll4 SEE ISO DBB-II4pl N
1-2 A
8 2
8 A
8 8
8 C
8 3
8 A
8 b
8 C
8 10'OL VOL 4g~ ~a~,
OB B.l t
OBB-II - -F 5
G 8
C 8
8o 7
8 8
8 A
8 C
8 F
8 8
8 10 8
11 8
12 8
13 S
8-
10 h
8 8
8 C
8 0
8 E
F 5
8 A
8 8
8 0
8 8
VOL VOL vOL vpl.
VOL VOL 088-II5-I-FW 5
-I I5-I-
- I
- -FW-I 0 BB-II5-I BB-II5-I 8-II5-I II -I-F 3
DBB-II -I-3-C 0 BB-II5+4-A OBB -II58-4-B OBB I I5 I-4-0 0 B-II54-2-A P
- I5--
0 B-II59-3-A 0
I -I-IO- 0BB-ll5
'II5-I-FW4
.Et-I -- w-0 BB-IIS.I-7-A q4 qO ZO-DBB-IO5
%0 SEE ISO BBB-I05-Z DBB-II5-I.5 OBS-I I5-I-7-B DB -II5-I-FW-I r
0
-fl=-I-F'.V-l2 OB B-I I5-I-FW-I I DBB-II5-I-FW"8 2O-GBBTI05 SEE ISO GBB-IOS-I 0BB-II5-I-FW-I 0 BBHI5-I-7-G 0BB-II5-I-7-F OBB-I
-I-i.W-6 OE 8-I I 5-I-FW-7 REFERENCE ORRIIINGS 088-uS-1 REV. BF6 LLL LEG-IM-1 5K L5J h-151 fRWM:
~o P, CHK'0:
~S-.~-o~s:c i o h5ucO AA CArsT I4ii ~ gr s
w I on.~~~~
ave ~
eawcs(3,P. ww C A.a).
DJS o
E 40 PENNSYLVANIA POWER 5 VGHT COMPANY JLLCNTOwLtCwSYL'rLvl SJKQOllJWAZTCAJI~kSTJT CW ~LWtI,Uwf1 4ECHTEL. SAPI FlWeCLKQ INSERVICE INSPECTICN ISOMETRIC WELD IDENTIFICATION DBB-II5-I i f~ l7 p rz Di.j;i~
G1
~
~
8856 ISI-CBf3-($5-g QSZ? ~ Qgg,
MELO IOENTITY ISO OB8-i)8-1
~o0 MELO I
SIZE 0.
TYPE TYPE OF NOE ISI RM'0 YERRS)
~'4LF a4e VOL 8 B-I I 8-I-F W-2 30'-DBD-I0 I SEE ISO 9 BD-I 0 I-2 (EX EM PT) r r
HY B 2,I-F052 A I
N l
l l
I l
V 4 IO7A 6% 8 B-I 2 I SE E ISO DBB-I2I-3
~ e II -I FW-DBB-II8 I-I-A 24-0 LA-lOl SEE ISO DLA-I OI-I r
~
REFERRER,E PtAWWr 5 DSO-IIS-I REvs9F2 Z5I-LEt -IOO-l 5K-l5I-M-I4l OWN I CHK2 OhCIMht.Th)Of. TO I)8 eel ~
HAJJ RTTI'JCO AJJ IIr;CA-.LD 5
g~y, J
l5svEIT cot. co~a 2T-T~A
/
. li
~
seTT
~Tesssee I CN'A De'2 sees Iee ~
TAJeC~
2TaeeD Q Jesee Ir A P PBlNSYLVANIAPOSER aI UGIIT COMPANY AllJJTOessl JQJJJTTLV AJslA SACIJDIAJJJIASTTAJJ TTTCTAN'STATIOJI IJNTT ~,IANT2 hhCTTTXL IANTRAJKTTCO INSERVICE INSPECTION ISOMETRIC WELD IDENTIFICATION ISI-DBB-118-1 pGGI]
ESE T
R 8L 8
Jee ee Deeae ee
~ee.
aass IsI"DBB-118-1 ",
2228
!V 2J2h e
t lt
ISQ PO0
.MELD NO.
TYPE MELO IJENIITY SIZE TYPE ISI OF REO'O NQE (YEARS oca-IL -1 I 2
0 8
1 C
L E
L 1
8 8
1 A
8 1
F L
1 G
~3 8
2 8
8 2
E F
2 F
F 2
4 8
2 A
8 2
C L
2 0
L 2
8 8
l 2'2 l2 l2 12'a'UR SUR VOL
,SUR VOL SUR VOL SUR VOL SUR VOL SUR VOL SUR SUR 2-CCA GT V
E21 I F006 I2 OCA 107 OCA-IC7 I.F W-4 0 CA-IC7-I-FW-3 107-1-F W.
12 OC4909 OCA-
-I--
OCA-I 7-1-2-C OCA-107-1-2<
OCA-l07-I 2 9 OCA-107-I-F W-5 0 CA-107. I-I-G N 5 B
( 10"OI 4)
A-l 7-1--
TV OCA-107-I-FW-2 1 2-OCA 109 SEE ISO OCA-I09.1 REFERENCE ORRIIINGS 0
307.1 F OCA-107 I I-A OCA 107.1+VH I/
~\\
PCA-107-I-I<
OC A-107 H-E acR-1L -1 REV.IIFI LS L LEG 100-1
$4 LS I ll-152 DWN:
12-4-80 OC AH07+1-B C H K:( ~c
~/i</+IT 5.1RSAP zZE9 To HH ISSIICS >IIC CuuST iag ~
Wee ('g P.
TC ~'
IWC.
~COL
~ aC ~
S 1
RERC LOG c
P tENNSYLVANIAPOWER & LIGHT COMPANY ALLITOTOtcLSTNIISTLVAIII*
sscvowIIIASTCAM TLTcTAIcTTATIDII IIIIIT1 vNITT SCCNZEL SAN FRAIIOSCO 1NSERVlCE lNSPECTION ISOMETRIC WELD IDENTIFICATION ISI-OCR-107-1
~CISeal W
~IT.
3555 ISI-OCR"107-1 I
0 6
Jf
!OCa-1O7-2
'o NO.
TYPE
'MELO IDENTITY MELO TYPE SIZE OF NDE iver REQ'0 (YERRS gs B
gJ 8I By
?
Ig P~
gy aeg B~j~
g
[ I Sa 7
masa~no ace c
8 B
I2 f2'70 QJt St&
SUR VDL SUR VOL SUR
'K)L 5UR VOL SUR VOL SUR VOL yJ (IGDIA3 OCA-107-2RV-I~CA-I07 DCAH07-2 D C A-107-2-2-A DC A-f07-2.2-0 DCA-l07-H'W4 DCA.I07-2-RV DCAf07- +$ 6///I I
DCA-l07-2-I-A DCA-I07 I-B Sl ER LOG IBOCA-I09, SEE lso DCA I09 2 QC AAO7-2-FW-2 I
AH07-2.I-D REFERENCE ORRMINGS ocR-uu-2 mv.f IFI LS L LEG. 100-1 CHK D.
/- P
.~$ $1CAO0 ass/rs
/sC c/mr-Sa
%11 El%sOas d.P.
5's'~
massa df,g.
oases 4. A O tENNSYLVANIAPOWER 5 UGHT COMPANY ALLtlITCNIN,tfN~VAllIA RSCLC)~IA5TXAllCLRCTRIC STATl<W IWItg tealrI SKOCTXL SAR /RANCSCO INSERVICE INSPECTION ISOMETRIC MELD IDENTIFICATION ISI-OCR-107-2 Jg&
~
WFHN 1555 ISI-OCR-107-2 g st ~ Sgt
0
. A
jil-~
ISO OCR-110-1 0
TYPE
~2 8
MELO IDENTITY SIZE 24>>
A-110"I-r>N-11 IOZL F 2-3 6
3-I 7
8 4
R S
C F
-4R 12 4R 8
5 s
8 S
R F
S IO 8
8 1
A 8
1 8
8 1-2 5
8 Zest 24'4'4t Zgt Zqt Zest Z4'4' Zest SNt VQ.
SU%
VQ.
SVR VQ.
SU%
VQ.
SUR VQ QN VQ.
SLQ VQ VQ 3 A-I IO-I -PJY.9 0 A-II -I--iV-M:N A-II -I-4A-A MlN DCA-IIO I"4 CA-I'.0-1-."N-OCA-IIO-I- FW-10 3CA-I 0-I-4A-8 MAX DCa-11 4-A-11 4-MAX 24-OCb-I IO A-I 0-. FW.6 DCA-IIO-I--H. 5 MIN OCA-IIO-I-I E MIN a-IIO-I I
C A-Il - - -
MAX DCA-IIO-I-I-B a-O- - -
.MAX I
0 2.
2 A
L B
L 3
B L
4 F
4 G
5 e
4A a
L 4A 8
4 D
L 4
E L
I E
L 1
F L
C L
SUR VOL SUR VOL SUR VOL SUR VOL SABIR Vbl.
SUR VOL SUR VOL SUR VO'L 5UR VOL SUR
, VOL SUR VOL SUR VOL SUR VOL SUR VOL SUR VOL SUR VOL CA-II -I-I a A.II -I-FW-4 XH3A CA-IIO- -PH-OCA-IIO-I REv.PPZ SI-LECi-IOD-I 5K I%I-
-151 DAY/N.
aalu D
/-9-8/
/'- s. Pr
~ttt
- h. ASw'R~
WS RC. Nf
%V+0 A5 vCQ,4) lSSUED Cat C"mTK. 4
~caeato ~
onset CA P.
~lice tttt MA Sv&t teC4 PENNSYLVANIA POWER 5 UGRT COMPANY ALLOITCWN,tflllH5YLVANI4 SACQcHWwAVflJwtLfCTACVTATlos VwTt,tMfR XCHTEl.5' RAJOgO INSERVICE INSPECTION ISOMETRIC WELD IDENTIFICATION ISI-OCR-110-1 g4 C A-IIO-I-FH-I qO 24-DBB-(07~
5EE ISO OBB I r 0
11 EFEILEhJCE OR.AWIIhIGS Gt]
IS I RERGIOR SLOG R
D
!858 ISI-OCR-110-1 3
QA JE V'QZL
ll
ISO OCR-110 2
~o0 e c.L 0.
TYPE IIELO IDENTITY SIZE 24e TYPE ISI DF REOeD NOE YERRS) 101 l F.
1 R
8 1
8 8
1 C
8 1-2 5
24e 24e 24'4T 24e
-II - -FS-Il DCA-I 10.2-FW-IQ 2-3 S
8 3-4 7
8 4
R 8
4 C
F 4R li?
8 8
5 8
5 8
F 5
10 8
240 24'4e 24A 24T MAX OCA-I I 2 OCA-110 I-C A-)!0-2-RN-2+QCA-IIO 080 MIN DCA-IIO-2-4A-A A-
- MIN 0 A-110-2-4.E
- I -.FW.9
-IIO-2-FW+
4A MAX A-IO-"-FZ-:
DCA-llo-2-4-C
-110-
-A u A-IIO-4.
MAX OCA IIO 2-FW-7 4A A
4A 8
4 0
4 E
L I
0 I
E L
I F
L I
G 2
A 2
8 3
A 8
4 F
4 G
5 8
5 C
5 0
F SUR VOL SUR VOL SUR VOL SUR VOI SUR AVQL SUR VQI.
SUR VOL SUR VOL SUR VOL SUR VOL SUR VOL SUR VOL SUR VOL SUR VOL SUR VOI.
SUR VOL SUR VOL SUR VOL SUR 4
~T MIN OCA-Iro I-B MlN A-II0.2. -G A-IIO-2-I-F MAX Dca-110 I-A OCA-110 I-H OCA-110-2-FW-DCA-110 FVf-I e
~.o
~~g ~e.,
o ~oP oat
~op Oca-110-2-FW-4 g
.)i:
X-GB 0CA-I IO-2-FW-6 REFERELICE PRAVflNG5 DCA,~ IIO-2 RA~IIF6 ISI-I Eh-IOO-I 5K-Ifl-M-IGI mew..
~. P, CHK'D:
To eeCt gcv( cD A5 eNOCATED
/- wP' eet e5fUEP SOC COIJST
~$
~e eAe eeee
~'Pfe bc'ec
~
~ei a Ace~( A P PENNSYLVANIA POWER 5 UG}lT COMPANy ALLteeTOeeeL rteeeeTTLTAAeA
$BQÃelAeeeeA cTcue 1 L ccT ActfAeeoee LeeeeT 1, eeeeeT 1 IECTTTEL EAH NANOCCO
~aaeeeee, I eee INSERVICE INSPECTION ISOMETRC WELD IDENTIFICATION ISI-DCR-110-2 e
Ieelp IS I RERCTOR BLOB R
R 8856 ISI-OCR-110-2 I
CTtl! MLK
4
~
~
~ ~
~o0 M L NO.
TYPE MELO IOENTITY TYPE ISI SIZE OF REa 0 NOE ITEARS 115 L.F r
1 A
8 II F
1 8
8 C
8 1
0 8
1-2 6
2 A
S 2
8 8
2-3 3
8 3
A 8
2 8
A 8
8 C
8 0
8 E
8 4
F 8
4 G
F 1
8 8
5 A
8 5
0 8
5 C
8 5
0 8
5 E
8 5
F 8
5 G
F 5
5 8
24'4'a'4'%
YO QÃt YO Sly YO.
Q%
YO Slà YO QQ YO QQ YO YO QQ YO QR YO QR YO QAl YO QQ YO QW YO Q%
SUR YlL YO.
DLA-102 I F W-I C L 4-I C 2-I-4-F n'-102-I-4-E C LA-102-F W-13 0LA-IC 2-1-4.C 0 L A-I 02 5-F 0 LA-I0 2-1-F Yf 0 LA-I02-I-7-0 0 L A-102-I-7-E A-
~ -F DLA-102-I-F W-12 A-I0 2-I-5-C
/
N4 D LA-102-1-6-8 D LA-I02-1.7.8 A-
- -A A-I 0 2-I-r-8 D L A-I0 2 F W-15
~ L A I u2-1." L A-IC > I-FW+
D LA-I0 2-I-6-A OLA-ICZ.I-I e
~OLA-IO 2 DLA-lorI-I-C 0 L A-IG 2-I-5-A OL >102-ld-A eZI 0 I I'A 0 LA-I02-I-F.W-8 l02 2 OSP I 24'0 L A-IOI
~ ~ ~ SEE ISO A-I
-Fw-7~
0LA I Ol I
-pgPp
<D OL A-I02-I-I-D A-10 -I c W-
,o~M
~O DL4 1021 F W-3 DLA 102 I 2 A I'L A-102 I-2-B REFERENCE PRAYVINC PCA-IOt-I REV5F9RI ISI LKi 100-1 SC Z5I-M-141 WH
< ~ p OLA-102 I-F W-l 0 D~ /g, 1M 8
8
. L A-I0"--I-+
.OLA 102-I-3-A 6
A S
6 8
8 6
C 8
6-7 9
8 7
A S
7 8
8 7
C 8
7 0
8 E
8 7
F F
7 10 8
12'2'LA-102-I-4-A D LA-I02-I.F W-2 QGGIQ ISI RE AC SLOG ll.-CONTI
',pv 10 4C Clap A$ iaprCA.CD I oSUIIr
<<C CONST C p
g
~f On 7P r
~
JN W NkO~~
~CT.
S85 6 ISI-OLR-102-1 0 P Cl,W ClCC C.A.a.
PENMSYI.VA.'IIA POWER 5 I.IGHT COMPANY ALl~,rtH~LVAPIIA RRCRJ~ CTCALICLCCYhrC STATICW UrrrY 1, VklY1 SCOYYXL-SANFIWtOSCO INSERVICE INSPECTION ISOMETRIC WELD IDENTIFICATION ISI-DLR-102-1
Ih k
k=
~
~
~
~
~ ~
l
~
~
~
~
~
l
~
4 I
~
~
~
~
~
~
~
I
~
~
~
~
~
~
~
g
~
~
l I
~
~
~
l 0
l
ISO Stpp NO TYPE
'MELO IOENTITY SIZE TYPE ISI OF REQ'0 NOE IYEARS 088-105-1
'1 1
8 1
A 8
1 8
8 1
E 8
1 F
8 1
8 8
e 20'00ZO'oL VOL GBB-I05-I-FW-5 G BB-I05-I-2-F GBB-I05-I-2-B N
1 L
8 1
3 8
1-Z h
Z A
8 8
8 8
z F
e Z
5 8
2 8
Zh+
ZV Z0 VOL VOL VOL VOL VO (m
RHR HT. EXCH.
IE-205 A EBB-I05-I-FW-GBB-l05-I-2-A
- JyI, O~I]
20 GBB-l05 CE&ICG I-I 6 20-GBB-I04 I
SEE ISO GBB;l04-2 GBB-l05-I-FVI-2 GBB-I05-I-RV-3
-l05-I I-H (23.l05.I.I.F v Q HUB l20 SEE ISO HB8-I20-Q GBB-l05-I-I-E GBB-l05-IR-L GE8-t05-I-I-0 GBB-l05-I-I-C GBB-65-I-I-B GBB-I05-I-FW.I EBB-l05-I-I-A 6 OBB-II5 SEE ISO OEB-I I5-I REFERENCE ORFIIIINGS e88-105-1 Rev.5FI I LS I LEL 100-'1 SK LS L 8-151 p~ NM~s-lAs 3"T5 (QA-f.'ur t-sr'lstssslt..tssstttt Tp sst5 ItEss/4 IdC AHSf-d.D.
A'a
~<sos sllsT.
tss ~'
a+0 s sscs ai 1S
(
RE.ACTOR SLOG RHR a
t gP w~gA y.
PEIINSYLYANN POWER 5 UGHT COMPANY AtlSXTTSSWS ttSuctTLVASSIA
%%XASSASsAA ETEASS tttCTASC tTATSOH ~ SSHST
'S, SSSSST t
~tCStttL tASE NANCISCO INSERVICE INSPECTION ISOMETRIC WELD IDENTIFICATION ISI-GBB-105-1 Ass oa WeWSa
~ST.
385$
ISI-GBB-105-1
~A
~
QtQ wtstt.
4
~ I'
'l
%S-101-1
'4ELO ND.
TYPE 2
2 8
2 3
B liELO lOENT1TY.
SIZE TYPE Of Ic= 'D NOE I>=RII5 VOL VO<
~ 4 HBB-IOI.I - FN-3 HBB-IQI-I -FW-4 HBB-IQI-I-FN-2 HBB.IQI-I - FW-I N
1 4 8
I VOL 0
0 lII IQ-H88-IQI E
ISO HB8 IQI.2 I
X-2I5 1ZA
. REFERENCE ORRWINGB m-101-1 aV. 7F3 Lab LEr SOO-1 S4 LS.L II"1%9 CHK:
Dr JZ.
o SS
~ASC ICIO.TICAAIsrLLCNfa <C g. SC, IWVCO fOR COIIS-.
)
DC't
~ 5LS
~SSICa srtt
~sw'cap.{) w~ r.A.O-ftCHTEL~ CAIIIRA!IOICCO PENMSYLVANIAPOWER 5 UGHT COMPANY ALLOITDssLtCN ssCYLV AMIA QJNUOIASSSsA CTCASI CLCCTAICCTATIOsI IAsITI,LSSIT 1 INSERVlCE INSPECTION ISOMETRlC V/ELD lOENTIFlCATlON ISI-HBB-101-1 E 8 8 L JAA Oa i
. - S856 ISI-HBB-101"1
) 7 DDASSDSSSSSA CSD
0 I
MELO IOENTITY 5
~a lea-QQ-2I, MELO SIZE TYPE NO.
TYPE OF NOE IS[
REQ'0 IYERRS SS LSe N
8 2v VOL HBB-IIO-FW-7
-203 8
2v VOL VOL riB -II
- -FW-8 2v VOL 8
2v VOL 8
2v VOL 8
2v VOL HBB-IIO-FW-8 HBB-I IO "2-FW-I HBB-II - -FW-24 HBB-IIO 8
8 2v VOL 2v VOL 8
2v VOL
- FW.
H
-II -
-FW 4 HBB-IIO-2-3rA.
HBB-IIO B 20-HBB-III-2 ME ISO HBB-III-2 RHR PUMP SUCTION IP-2028 8
2v 8
2v VOL VOL HBB-IIO- - -"
HB&I IO-2 0 HBB-IIO-A REFERENCE ORRMINGS 8
xr VOL HBB-. IIO-2-FW-l2 HBB-IIO- -FW-I3 HBB-IIO-2 F INB-u0-2 RCY.&F2 LS.L LEG. 100-[
SC-LS.L II-ISI twas:, P; CHK0.
I-$'-8I
~~8~'ygsg ISQ/ED Fok CONSTR.
~4sOo I 4O su<
+~'~ u ai l~
tea>
IS I RERCTOR BLOC R
R PEMMSYLVAMIAPOWER & UGHT COMPAMY Atoll'ttkel,ttJINSYLVANIL SSRICNAJvaA CXAAlLtCfNC STATlOf OCT
'l IPQT 2 SKCK1XL SAPI /RAACSCO
~~50. ~-
C>.0.
Wrawl~
~ET, RS56 ISI-HBB-110-2 Ds12 MSGR INSERVICE INSPECTION ISOMETRIC WELD IDENTIFICATION ISI-HBB-11D-2
IIELO IOENTITY ISO TYPE SIZE TYPE I51 OF REQ'0 NOE (YEARS IS8 LFo HBS 111 2 1
2 2
2 2-3 h
3 8
3 C
3 0
6 F
S h
A 8
h C
8 h-6 9
5 5
5 6
A 6
8 6
C 6
6 6
6 10 6
13 6-8 lh 7
11 7
A 7
12 8
A 8
8 8
0 8
F 8-9 15 9
A 9
8 9
16 10 0'0 A
10 18 l
cssaaxasse ss>>3 8
8 8
8 8
'8 8
8 8
8 8
2D' 20'D'0'0'h~
Zhs Zho Zhi Zhi VOL VOL MEL VCL VCL
. VOL vCL VOL VCL VCL VOL VOL V3L VOL VCL VCL VGL VGL VCL VOL VOL VCL Zhs 20'0'0'0'D'0>>
VOL VCL VOL VOL VCL WCL VCL VCL VCL VGL VCL VGL VOL VCL VCL 20'CL N
24-HBB+IO SEE 150 HBB-110-3 24-HBB-II0
~
ISO HBB-IIO-4 HBB-lll-2 E HBB III 280 H
-t tt-2-8.Ci 24 HBB-ItO 5EE ISO KBB-I10-2 H83-Ill-2-Rrr-17.
HBB-I II-2-FVI-t9 HBB-Itl-2-FW-IB HBB-IIt-2-PJY-t6
'-:33-t tt-2-9>>8 H83-s I-2-9-A 20-HBB-II I r33-I I 1 FW-I5 HBB-III-2-8-F H88-I II-2-8-A 88-llI FW-14 HBB-111-2 E HBB-II1-2.FW-6 H88-I I I"2-H HBB-III-2-3-O HBB III 2 g.c
-:BB-ItI
-2PsV-2C'/BB-II I -
I
'.6
~
~a~ >/
H88 - I I I-2-I A HBB-s ll-2-FW.I 24-HB8-I tO 5EE ISO HB8-IIO-I a0-138-'ll I HBB-I11.2-FW-4 HBB-III-2-2;A HBB-II1 FMt 22 HB -~II-2-FW-3 HB8-III-2-6-A HBB-III-2-FW-9 HBB-III-2 4-. C HBB-III 2-FW-8 HBB-t II-2-4-A HBB-III-2-4-8 HBB-III-2-Ptv>>5 HBS-' l-2-3-A HBB-I I I-2-3-8 H83: st I-2-3-F HBB-111 6-O HBB-III 6-F HBB-III-2-6-0 HBB-I I 1-2-6-8 SEE 150 HBB.III-I HBB-111 FVt-.O REFERENCE DRRMINGS WS-m-2 REV. 3FI4 LSD LE4 1M-1 SK. LS L II-ISI o~
+~
CHK-~~F- ~
ggl-rg lcwtssLCCfOTo ms ss c.
l55 AD FoE WAIST.
tLD.
HBB-III-2-FW2 aaa ~
eawsogg wee g g g s 4. ~
s>>>>>>
~>>>>L s>>c>>
[GGI j
TS I REACTOR Sl-IG RIIR PENNSYLVANIA POWER 5 UGHT COMPANY ALLtÃTowE.stslksYLvssss 4 NAGUsscsswA ssssss CLscTiKsTAsloN sass s, wls s
&CHTEL-SANlRANQSCO INSERVICE. INSPECTION ISOMETRIC VIELO IDENTIFICATION ISL-HB8-111-2 Jss>>>>
wale>>>>.
~ss 8858 ISI-HBB-111-2 I
Sass M MAL H88-III-24-8 HBB-III-2-F'H-6~
HBB-II I-2-FW-12 HBB-tl1-2-7-A Cr HBB-I11 FVI-II s
HBB-III-2-FVl-7 HBB-III-2-5-A
11