ML18026A383
| ML18026A383 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/25/1982 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| ER-100450, PLA-1024, NUDOCS 8203030066 | |
| Download: ML18026A383 (79) | |
Text
REGULATORY IFORHATION DISTRIBUTION S . EH (RIDS)
P ACCESSION NBR: 8203030066 DOC DA'TE: 82/02/25 NOTARIZED: NO DOCKET FACIL:50 387 Susquehanna Steam
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Electric Stations Unit ii Pennsylva 05000387 50-388 Susquehanna 'Steam Electric Stations Unit 2R Pennsylva 05000388 AUTH ~ NAHE AUTHOR AFFILIATION CURTIS E Note 0 'Pennsylvania. Power 8 Light Co ~
RECIP ~ NAHE, RECIPIENT AFFIL'IATION
'SCHNI'ENCEREA ~ Licensing Branch 2
SUBJECT:
Forwards SORT forms fot 'balance of plant equipment in par tial r esponse ito SERE'Item 11.
DISTRISUTION CODE: 0001S COPIES lRECEIVED:L'TR J ENCL J SIZE:, "'H.
TITLE: PSAR/FSAR AHDTS and Related Correspondence NOTES:IKE:3 copies FSAR L all amends.LPDR:2cys 05000387 IH,E:3 copies FSAR 8 all amends.LPDR:2 cys 05000388'ECIPIENT COPIES RECIPIENT iCOP IES, ID CODE/NAHE LTTR ENCI ID CODE/NAHiE LTTR ENCL
ACTION: A/D LICENSNG LIC BR P2 BC LIC BR 0'2 LA PERCHER'1 1 INTERNAL: ELD IE 06 IE/DEP/EPDB 35 IE/DEP/EPLB 36 HPA NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/GB 28 NRR/DE/HGEB 30 NRR/DE/HEB 18 NRR/DE/HTEB 17 NRR/DE/QAB 21 NRR/DE/SAB 2Q NRR/DE/SEB 25 NRR/DHFS/HFEB40 NRR/DHFS/LQB 32 NRR/DHFS/OLB 3Q NRR/DHFS/PTRB20 NRR/DS I/AEB 26 NRR/DS I/ASB 27 NRR/DSI/CPB 10 NRR/DS I/CSB 09 NRR/DSI/ETSB 12 NRR/DSI/I:CSB 16 NRR/DS I/PSB 19 NRR/DS I/RAB 22 N B 23 NRR/DST/LGB 33 REG FILE 00 1 1 EXTERNAL: ACRS 41 16 BNL(AHDTS ONLY) 1 FEHA REP DIV 39 LPDR 03 4'?
NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1
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0 Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215 l7 Norman W. Curtis gt Qp@ ~~0 Vlcc President-Engineering 4 Construction-Nuclear 215 / 770-5381 P g >982 "A:~<<~~a.<< ~+M CXt'atoll tt@gg February 25, 1982 rmc 8 Mr. A. Schwencer, Chief Docket Nos. 50-387 Licensing Branch No. 2 50-388 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION SQRT FORMS BOP EQUIPMENT (SER ITEM 811)
ER 100450 FILE 841-2 PLA-1024
Dear Mr. Schwencer:
In partial response to SER Item 811, attached are the 4-page SQRT forms for the BOP equipment which were not previously transmitted to you.
Also attached are two lists which identify the SQRT forms by their BOP Purchase Order Number. List A identifies those 4-page SQRT forms which were transmitted to you at the time of the Seismic Qualification Audit. List B identifies all of the remaining BOP SQRT forms which are being transmitted to you at this txme.
Very truly yours, pool I/ D;sk Vice President-Engineering and Construction-Nuclear 5$ ,re 0
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LIST A M-11 J-03A E-109 P-10B M-30 J-05A E-152 P-14B M-149 J-69 M-159
LIST B M-1 2 J-03C E-112 P-10A M-22 J-05B E-117 P-11A M-55 J-17 E-118 P-12A M-58 J-27 E-119 P-12B M-60 J-31 E-119BC P-14A M-87 J-59 E-120 P-15A M-90 J-65 E-121 P-15BC M-151 J-65B E-135 P-16A M-156 J-69B E-136 P-16BC M-160 J-70 E-151 P-17A M-164 J-92 E-155 P-17B M-192 J-98 P-18A M-302 P-31A M-307 M-308 M-309 M-310 M-315 M-317 M-320 M-321 M-323C M-325 M-327 M-334 M-336 M-362 M-365
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EXAMINATION AND I TION (CLASS 1)
COMPONENTS, PARTS, METHOD OF EXAMINATION AND REMARKS ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD REMARKS NO. TABLE IWB 2500 TO BE EXAMINED
- REACTOR VESSEL-Bl.l B-A Pressure-retaining welds I,ongitudinal and circumferential Volumetric in reactor vessel shell welds meridional and (7) (S) circumferential head welds vessel-to-flange and head-to-flange circumferential welds B1.4 B-D Full penetration welds of Primary nozzle-to-vessel welds Volumetric (7) (9) nozzle in vessel and nozzle inside radiused section Bl.5 B-E Pressure-retaining partial Vessel penetration, including Visual (IWA-5000) (7) penetration welds in control rod drive and vessels instrumentation penetration Bl.6 B-F Pressure-retaining dissimilar Nozzle-to-safe end welds Volumetric (7) metal welds and surface B1.7 B-G-1 Pressure-retaining Nuts Surface . (7) bolting greater than 2 inches in diameter Bl.8 B-G-1 Pressure-retaining Pressure-Retaining bolts and Volumetric and (7) bolting greater than studs surface 2 inches in diameter B1.9 B-G-1 Pressure-retaining bolting Ligaments between threaded stud Volumetric (7) greater than 2 inches in holes diameter B1.10 B-G-1 Pressure-retaining bolting, Closure washers, bushings Visual (7) greater than 2 inches in diameter
- 1. Numbers listed designate applicable relief request.
Page 1 of 8, REVISION l
EXAMINATION AND I ION (CONT'D)
- (CLASS 1)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD NO. TABLE IWB - 2500 TO BE EXAMINED Bl.ll B-G-2 Pressure-retaj.ning bolting, Pressure-retaining bolting Visual smaller than or equal to 2 inches in diameter Bl.12 B-H Vessel supports Integrally welded vessel Volumetric supports Bl.13 B-I-1 Interior clad surface of Closure head cladding 1) Visual and reactor vessel surface or
- 2) Volumetric B1.14 B-I-1 Interior clad surface of Vessel cladding Visual reactor vessel Bl. 15 B-N-1 Interior of reactor vessel Vessel interior Visual B1.16 B-N-2 Integrally welded core support Interior attachments and core Visual structures and interior support structures attachments to reactor vessel Bl.18 B-0 Pressure-retaining welds in Control rod drive housings Volumetric control rod drive housings Bl.19 B-P Components exempted from Exempted components Visual (IWA-5000) examination by IWB-1220
-PIPING PRESSURE .BOUNDARY" B4.1 B-F Pressure-retaining dissimilar Safe-end to piping welds and . Volumetric metal welds safe-end in branch piping welds B4. 2 B-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric and greater than 2 inches in in place surface diameter Page 2 of 8, REVISION 1
EXAMINATION AND I TION (CONT'D)
(CLASS 1)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD NO. TABLE IWB - 2500 TO BE EXAMINED B4.3 B-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric and greater than 2 inches in when removed surface diameter B4.4 B-G-2 Pressure-retaining bolting, Pressure-Retaining bolting Visual smaller than or equal to 2 inches in diameter B4.5 B-J Pressure-retaining welds Circumferential and longitudinal Volumetric and in piping piping welds in nominal pipes surface size 4 inches and greater B4.6 B-J Pressure-retaining welds Branch pipe connection welds Volumetric in piping exceeding six inches in diameter B4.7 B-J Pressure-retaining welds in Branch pipe connection welds six Surface piping inches diameter and smaller B4.8 B-J Pressure-retaining welds Socket welds Surface.
piping B4.9 B-K-1 Support members for piping, Integrally welded supports Volumetric valves and pumps B4.10 B-K-2 Support components for Support components Visual piping, valves and pumps B4.11 B-P Components exempted from Exempted components Visual (IWA-5000) examination by IWB-1220 Page 3 of 8, REVISION l
EXAMINATION AND I TION (CONT'D)
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(CIASS 1)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD NO. TABLE IWB - 2500 TO BE EXAMINED
- PUMP PRESSURE BOUNDARY-B5.1 B-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric greater than 2 inches in in. place diameter B5.2 B-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric and greater than 2 inches in when removed surface diameter B5.3 B-G-2 Pressure-retaining bolting, Pressure-retaining bolting Visual smaller than or equal to 2 inches in diameter B5.4 B-K-1 Support members for piping, Integrally welded supports Volumetric valves and pumps B5.5 B-K-2 Support components for piping, Support components Visual valves and pumps B5.7 B-L-2 Pump casings Pump casings Visual B5.8 B-P Components exempted from Exempted components Visual (IWA-5000) examination by IWB-1220
- VALVE PRESSURE BOUNDARY-B6.1 B-G-1 Pressure-retaining bolting Pressure-retaining bolts and Volumetric and greater than 2 inches in studs surface diameter Page 4 of 8, REVISION l
EXAMINATION AND I TION (CONT'D)
~
(CLASS 1)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD NO. TABLE IWB " 2500 TO BE EXAMINED B6.2 B-G-1 Pressure-retaining bolting Pressure-retaining bolting Visual greater than 2 inches in diameter B6.3 B-G-2 Pressure-retaining bolting, Pressure-retaining bolting Visual smaller than or equal to 2 inches in diameter B6.4 B-K-1 Support members for piping, Integrally welded supports Volumetric valves and pumps B6.5 B-K-2 Support components for piping, Support components Visual valves and pumps B6.7 B-M-2 Valve bodies Valve bodies Visual B6.8 B-P Components exempted from Exempted components Visual (IWA-5000) examination by IWB-1220 RP:pd 19-Q Page 5 of 8, REVISION l
EXAMINATION AND INS ON "(CLASS 2)
(CONT'D)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD NO. TABLE IWC-2520 TO BE EXAMINED
- PRESSURE VESSELS-C1.1 C-A Pressure-retaining welds Circumferential butt welds Volumetric in pressure vessels C1.2 C-B Pressure-retaining nozzle 'ozzle-to-vessel welds Volumetric welds in vessel C1.3 C-C Integrally welded support Integrally-welded supports Surface attachments to vessel C1.4 C-D Pressure-retaining bolting : Pressure-retaining bolting Visual and either exceeding 1 inch diameter surface or Volumetric
" PIPING-C2.1 C-F Pressure-retaining welds in Circumferential butt welds Volumetric (1)(4)(5)(6) piping, pumps and valves in system which circulate reac-tor coolant C2.1 C-G Pressure-retaining welds in Circumferential butt welds Volumetric (1)(4)(5)(6) piping, pumps and valves in system which circulate other than reactor coolant C2.2 C-F Pressure-retaining welds in- Longitudinal weld joints in Volumetric (1) (4) (5) (6) piping, pumps and valves in fittings system which circulate reactor coolant C2.2 C-G Pressure-retaining welds in Longitudinal weld joints in Volumetric (1) (4) (5) (6) piping, pumps and valves in fittings system which circulate other than reactor coolant Page 6 of 8, REVISION l
0 EXAMINATION AND INSP (CONT'D)
ON (CLASS 2)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD NO. TABLE IWC-2520 TO BE EXAMINED C2.3 C-F Pressure-retaining welds in Branch pipe-to-pipe weld joints Volumetric (1) (4) (5) (6) piping, pumps and valves in system which circulate reactor coolant C2.3 C-G Pressure-retaining welds Branch pipe-to-pipe weld joints Volumetric (1) (4) (5) (6) in piping, pumps and valves in system which circulate other than reactor coolant C2.4 C-D Pressure-retaining bolting Pressure-retaining bolting Visual and (2) exceeding 1 inch diameter either surface or volumetric C2.5 C-E-1 Support members for piping Integrally-welded supports Surface (3) valves and pumps C2.6 C-E-2 Support components for Support components Visual piping valves and pumps
- PUMPS "
C3.2 C-D Pressure-retaining bolting Pressure-retaining bolting Visual and (2) exceeding 1 inch in diameter either surface or volumetric Page 7 of 8, REVISION l
EXAMINATION AND INSP ON (CLASS 2)
(CONT'D)
ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS METHOD NO. TABLE IWC-2520 TO BE EXAMINED C3.3 C-E-1 Support members for piping Integrally-welded supports Surface valves and pumps C3.4 C-E-2 Support components for Support components Visual piping valves and pumps
- VALVES-C4.2 C-D Pressure-retaining bolting Pressure-retaining bolting Visual and exceeding 1 inch in diameter either surface volumetric C4.3 C-E-1 Support members for piping Integrally-.welded supports Surface valves and pumps C4.4 C-E-2 Support components for Support components Visual piping valves and pumps RP:pd 19-(}
Page 8 of 8, REVISION 1
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PRE-SERVICE INSPECTION RELIEF REQUEST ffl 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 Nl 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 cod'e edition and addenda;in lieu of this requirement, PP6L proposes to use Appendix III, "Ultrasonic Examination Method for Class 1 and 2 plplng systems made from Ferritic Steels" from the Winter 1975 Addenda.
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 '75 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 ¹2 I. IDENTIFICATION OF COMPONENTS:
All Class 1 and Class 2 bolting in piping, pumps, and valves.
II- CODE RE UIREMENTS:
ASME Section XI, 1974 Edition to the Summer 1975 Addenda requires the following examinations be performed:
ITEM EXAMINATION COMPONENT METHOD NUMBER CATEGORY B4. 2, B5. 1, Pressure retaining bolting, Volumetric B6.1 B-G-1 2 inches and larger, in place B4.3, B5.2, Pressure retaining bolting, Volumetric and B6.2 B-G-1 2 inches and larger, when Surface removed.
B4.4, B5.3, Pressure retaining bolting, Visual B6.3 B-G-2 smaller than 2 inches.
C1.4, C2.4, CD Pressure retaining bolting Visual and C3.2, C4.2 exceeding 1 inch either surface or volumetric These exam'inations must be performed completely as a preservice examination requirement prior to initial plant start-up.
Rev. 0 5/15/81
0 III. BASIS FOR RELIEF:
PP&L requests relief from the examination requirements of ASME Section XI 1974 Edition to Summer 1975 Addenda; examinations shall be performed in accordance with the more current requirements of ASME Section XI 1977 Edition to Summer 1978 Addenda as follows:
ITEM EXAMINATION COMPONENT METHOD NUMBER CATEGORY B6.150, B6.18Q, Pressure retaining bolting B6.210 B-'G-1 larger than 2 inches in place Volumetric B6.160, B6.190, Pressure retaining bolting Surface and B6.220 B-G-1 larger than 2 inches, when Volumetric removed.
B6.170, B6.20Q, B-G-1 Pressure retaining bolting.* Visual VT-1 B6.230 B7.50, B7.60, B-G-2 Pressure retaining bolting Visual VT-1 B7.70 2 inches and smaller C4.10, C4.20, C-D Pressure retaining bolting C4.30, C4.40 exceeding 2 inches Volumetric
- Nuts, bushings, washers, threads, in base material and flange ligaments between threaded stud holes.
Rev. 0 5/15/81
IV. JUSTIFICATION:
The justification for upgrading the 1977 Edition to Summer 1978 Addenda of ASME Section XI for piping system bolting examination, in lieu of the governing code edition and addenda, is to make the Class 2 requirements more closely parallel Class 1 requirements. It impractical to inspect Class 2 components more stringently than is Class 1 components and presents no adverse affect on the integrity of the component or. upon overall plant safety.
V. ALTERNATE 'PROVIS'IONS:
The requirements of ASME Section XI 1977 Edition to the Summer 1978 Addenda will be used.
Rev. 0 5/15/81
REL'IEF RE UEST 03 I. IDENTIFICATjON 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:
I PPGL requests relief from the examination requirements of ASME Section XI 1974 Edition to'ummer 1975 Addenda; examinations shall be performed in accordance with the more current requirements of ASME Section XI 1977 Edition to Summer 1978 Addenda as follows:
ITEM EXAMINATION COMPONENT METHOD TEST NUMBER CATEGORY REQUIREMENTS B4.9, B6.5 B-K-1 Integrally welded . Volumetric Table support attachments or Surface* IWB-2500-1 C3.10, C3.40, Integrally welded Surface**. Table C3.70, C-E-1 support attachments 'XWC-2500-1 C3.100
- See Figures IWB-2500-13, 14, 15.
- See Figure: IWC-2520-5.
Rev. 0 5/15/Sl
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 l978 are as follows:
- 1) The weld geometries involved make a meaningful ultrasonic 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.
Rev. 0 5/15/Sl
RELIEF RE UEST N4 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 BZ 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 br'anch 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. BASIS 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 CODE NATURE OF % OF SCAN IDENTIFICATION CATEGORY AND SYSTEM CONFIGURATION OBSTRUCTION 'OBSTRUCTED NUMBER ITEM NUMBER (APPROXIMATE)
DBB-114-1-9E . CF HPCI Pipe to Cap Two (2) 16%
C2.1 Weldolets DBB-13 5-1-7F CF RHR Pipe to Cap One (1) 8<
C2. 1 Weldolet DBB-115-1-5D CF RHR Pipe to Tee One (1) 16%
C2.1 Weldolet DBB-115-1-5G CF Pipe to Cap Three (3)
C2.1 Weldolets 34%
HBB-110-2-3C CF RHR Elbow to Tee Instrumentation 3%
- C2.1 Nozzle DLA-104-1-FWl BJ Feedwater Pipe to Valve Permanent Hanger 50%
B4.5 DLA-102-1-FW7 BJ Feedwater Pipe to Valve Permanent Hanger 50%
B4.5 HBB-ill-2-3D CF RHR Pipe to Elbow Hanger Saddle Weld 13%
C2. 1 DBB-118-1-lA CF Feedwater Sweepolet to Pipe Hanger Lug Attachment C2.3 Weld 6%
GBB-106-1-FW6 CF RHR Pipe to Elbow Welded Hanger 20%
C2.1 GBB-109-1-2A CG RHR Pipe to Elebow Hanger Saddle C2.1 Rev. 2 1/29/82
W CODE CATEGORY IDENTIFICATION AND ITEM NATURE OF %%d OF SCAN NUMBER NUMBER SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED VRR-831-2-9G BJ Recirculation Longitudinal Pipe Whi;p 7%
B4.5 Weld Res traint Rev. 2 1/29/82
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.Quring normal system operation weld is under a maximum pressure of 345psig.
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.
RT During normal plant power operation, welds are not under pressure. During normal system operation, significant leakage is detectable by leak detection system. Plant can be safely cooled down by unaffected RHR loop or main condenser.
RT Rev. 2 1/29/82
A SECTION III EXAMINATION SAFETY IMPACT RT and PT Reactor coolant pressure boundary leak detection system detect leakage. Plant technical specification require plant shutdown with leakage greater than 5 gpm.
Rev. 2 1/29/82
IV. JUSTIFICATION:
The justification for requesting relief from ASME Section XI examination requirements is as follows:
- 1) 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 1 welds have received surface examination to satisfy ASME Section at this time is unnecessary. IlI'etesting 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 VEST 05 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 BZ 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 TWC-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.1975 Addenda, requires an angle beam examination of the weld and required voltage (the lesser of
~qt or 1"}. be performed scanning both normal and parallel to the weld.
III. BASIS FOR'EL'IEF:
Relief is required from the ASME Section XI examination requirements on the basis of., complete inaccessibility'f the weld and required volume 'due 'to plant design.
Rev. 0 5/15/81
WELD CODE CATEGORY NATURE OF OF SCAN XDENTIFXCATXON AND ITEM OBSTRUCTED NUMBER NUMBER SYSTEM CONFIGURATXON OBSTRUCTXON HBB-101-1-FW-7 CG RCIC Pipe to Sparger Piping located Totally C2. 1 in the wetwel1 Obstructed HBB-101-1-lA CG C2.
1'RCXC Pipe to reducing elbow HBB-101-1-1B CG RCXC Pipe to Elbow C2,1 HBB-101-1-FW6 - CG RCXC Flued Head to Pipe C2.1 I HBB-1 08-2-3A CG HPCI Pipe to Elbow C2.1 HBB-108-2-FW10 CG HPCI Elbow to Reducer C2-1 HBB-10&-2-FW7 CG HPCI Reducer to C2. 1 Penetration HBB-108-2-FW1 CG HPCI Pipe to Elbow C2. 1 DCA-108-1-3.B BJ RHR Longitudinal Weld Welded Hanger Totally B4.5 Obstructed DCA-108-1-1C BJ RHR Longitudinal Weld Welded Hanger Totally B4.5 Obstructed DCA-108-1-FW2 BJ RHR Valve to Pipe Welded Hanger Totally B4. 5 Obstructed Rev. 1 1/29/82
ASME SECTION III EXAMINATION SAFETY IMPACT RT Weld is inaccessible and belov approximately 20 feet of suppression pool water.
Adequate steam condensation of any leakage is expected. System is not pressur-ized during power plant operation. During system operation, maximum pressure is less than 25 psig. System is not required for normal shutdown and backed up by either HPCI or feedwater.
RT Leakage vould 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 pover operation.
Maximum pressure the veld could be subjected to is 25 psig.
RT RT Leakage would be detected by wetwpll temperature/pressure increase. Upon such signals HPCI system operation could be terminated. HPCI operation is backed up by the auto-depressurization system and RHR. Weld is not normally pressur-ized during plant power operation.
RT RT RT Leak detection systems detect weld leakage, resulting in manual or automatic isolation of the leak. Line is not required for normal safe shutdowns. Al-ternate shutdown methods are available.
RT and PT Reactor coolant leakage detection systems will detect leakage. Plant technical specifications require plan shutdown with leakage greater than. 5 gpm.
RT and PT RT and PT Rev. 1 1/29/82
IV. JUSTIFICATION:
The justification for requesting relief from ASME Section XI examination requirements is as follows:
l) 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 PROVI'SIONS:
Welds are inaccessible to all methods of NDE.
Rev. 0 5/15/81
V. ALTERNATE PROVISIONS:
The structural integrity of all Class 1 welds covered has been rified 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 more meaningful at that time.
Class 2 piping welds will receive a supplemental surface examintion.
Nelds 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 ¹l,and implemented as required.
Rev. 0 5/15/81
RELIEF RE VEST Q6 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 BZ 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::.loQ%* 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 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.
- excluding those exempt per,.INB-1220,, IWC-1220.
ASME Appendix III, Ninter 1975 Addenda, requires an angle beam examination of the weld and required volume (the lesser of
.iqt or 1"} be perfomred scanning both normal and parallel to the weld.
III. BASIS 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 CODE CATEGORY NATURE OF OF SCAN NUMBER AND ITEM NUMBER SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED DCA-110-1-FW11 BJ RHR Valve to Tee Part Geometry Totally B4.5 DCA-110-2-FW11 BJ RHR Valve to Tee Part Geometry Totally B4.5 DCA-107-1-FW3 BJ Core Spray Valve to Valve Part Geometry Totally B4. 5 DCA-107-2-FW7 BJ Core Spray Valve to Valve Part Geometry Totally B4.5 DBB-115-1-FW13 CF Valve to Valve Part Geometry Totally C2.1 GBB-105-1-FW1 CF Valve to Reducer Part Geometry Totally C2. 1 DCA-110-1-FW2 BJ RHR Valve to Flued Part Geometry Totally B4.5 Head DCA-ll0-2-FW2 BJ RHR Valve to Flued Part Geometry Totally B4.5 Head DCA-3.08-1-FW10 BJ Valve to Reducer Part Geometry Totally B4.5 GBB-108-1-FW4 BJ RHR Valve to Reducer Part Geometry Totally B4.5 VRR-B31-1-FWA24 BJ Recirculation Valve to Pipe Part Geometry Totally B4. 5 VRR-B31-2-FWB24 BJ Recirculation Valve to Pipe Part Geometry Totally B4. 5 Rev. 1 1/29/82
ASME SECTION III EXAMINATION SAFETY IMPACT RT and PT Reactor coolant pressure boundary leak detection system will detect weld leakage:
Technical specifications require plant shutdown with unidentified leakage greater than 5 gpm.
RT and PT RT and PT RT and PT RT During noxmal plant 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 RT and PT Inside containment isolation valve perform reactor coolant pressure boundary inside function. Any significant leakage would be detected by leak detection system.
RT and PT RT and PT During power plant operation, weld is not pressurized. During normal system operation, significant leakage detected by leak detection system. Alternate shutdown cooling is unaffected and condenser is also available for cool down.
RT During normal plant 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 and PT Reactor coolant pressure boundary leak detection system will detect weld leakage. Technical specifications require plant shutdown with unidentified leakage greater than 5 gpm.
IV. JUSTIFICATION:
The justification for requesting relief from ASME Section XI examination requirements is as follows:
- 1) The structural integrity of the piping pressure boundary is not in question. The subject welds were inspected in accordance with 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.
I
- 4) Incomplete examination will not impact plant safety.
Rev. 0 5/15/Sl
REL'IEF RE UEST 'N7 I. IDENTIFICATION OF COMPONENTS:
Class 1 reactor pressure vessel examinations.
II. CODE RE UIREMENT:
The construction permit for SSES Unit Ql was issued on November 2, 1973. In accordance with the requirements set forth by 10 CFR 50.55a, SSES gl 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/Sl
IV. JUSTIFICATION:
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 Nl RPV preservice examination.
Rev. 0 5/15/81
V. ALTERNATE PROVISIONS:
ASME Section XI 1974 Edition to the Winter 1975 Addenda will be used for the SSES Nl reactor pressure vessel preservice examina-tions.
Rev. 0 5/15/81
RELIEF RE UEST Ii~8 I. IDENTIFICATION OF COMPONENTS:
Class 1 bottom head meridional weld seams (DA, DB, DC, DD, DE, DF).
II. CODE RE UIREMENTS:
Category B-A of ASME Section XI, 1974 Edition to Winter 193'5 Addenda requires volumetric examination of essentially 100% of the accessible length of each, meridional weld in vessel heads.
Appendix I, Article I-5000, requires the examinations be conducted using two beam angles from each direction (nominal angles of 45 degrees and 60 degrees.
These examinations must be performed completely as a preservice examina-.
tion requirement prior to initial plant start-.up, III. BASIS FOR RELIEF'elief is required from the ASME Section XI examination requirements on the basis of partial coverage of, the weld and required volume due to vessel configuration. Interference from the vessel skirt attachment weld buildup results in the .unexamined volumes as follows:
0 Base Metal Exam 12% Missed 0 Weld Metal Exam. 12% Missed 45 Exam 4% Missed 0
60 Exam 2% Missed IV. JUSTIFICATION:
The justification for requesting relief from ASME Section XI examinate'on requirements is as I follows;
- 1) A composite of all examination angles show .that a volume equal to two (2} percent of the required examination volumes. for. weld DA, DE, DC, DD, DE and DF are completely. unexamined, All other areas haye.
been covered by any or all of the 0 , 45o, and 60
- 2) The integrity of the welds have been verified by ultrasonic and magnetic particle testing during fabrication.
V. ALTERNATE PROVISIONS:
Alternate NDE methods are not feasihle for this. examination,
RELIEF RE VEST 99 I. IDENTIFICATION OF COMPONENTS:
Class 1 feedwater inlet nozzles N4A and N4D.
II. CODE RE UIREMENTS:
Category B-D of ASME Section XI, 1974 Edition to-Winter 1975 Addenda requires 100% volumetric examination of the nozzle to vessel weld and adjacent areas, of nozzle and vessel. (Figure IWB-3512,1(a}),
These examinations must be performed completely as a preservice examination requirement prior to initial plant start-up.
III. BASIS FOR RELIEF:
Relief is required from ASME Section XI examination requirements on the basis of incomplete coverage of the weld and required volume due to vessel configuration. The proximity of nozzles NllA and B to the subject feedwater nozzles precludes complete examination of weld seams N4A and N4D as follows:
N4A 300 completely examined (automatic}
60o not examined due to interference from nozzle N11A, N4D 30ao completely examined (automatic}
60o not examined due to interference from nozzle N11B.
Spacing of only 4,5" hetween the nozzles allows only a best effort manual examination of the affected areas.
IV. JUSTIFICATION:
The justification for requesting relief from ASME Section Xl examination requirements .is as follows:
- 1) The excluded area is 16.67 percent of the weld seam; 83.33 percent
'as,been completely examined.
- 2) Four (4) nozzles of the same configuration and service (N4B., N4C; N4E, N4F) have been completely examined.
- 3) The integrity of welds have been verified by ultrasonic and magnetic.
particle examination during fabrication.
- 4) All N4 nozzle to vessel welds were liquid penetrant testing following RPV hydroteat and accepted.
V. ALTERNATE PROVISIONS:
Due to extensive testing already performed during fabrication, no additional NDE is required to establish integrity of the welds.
RELIEF RE UEST 010 I. IDENTIFICATION OF COMPONENTS:
Bodies of Class 1 valves exceeding 4 inch nominal pipe size.
II. CODE REQUIREMENTS:
Category B-M-2 of ASME Section XI, 1974 Edition to Summer 1975 Addenda requires Visual Examination of the internal pressure boundary surfaces on valves exceeding 4 inches nominal pipe size.
III. BASIS FOR RELIEF:
Relief is requested from the ASME Section XI examination re-quirements on the basis of inaccessibility of the valve internal pressure boundary surfaces.
IV. JUSTIFICATION:
The justification for requesting relief from ASME Section XI Preservice Examination requirements is as follows:
1, The structural integrity of the piping pressure boundary has been verified by Construction Code testing require-ments; therefore, the intent of ASME Section XI has been met.
- 2. Shop Surface Examinations, liquid penetrant and/or mag-netic particle, have been performed on the body, bonnet, and disc. Radiography was also performed on the body.
- 3. All valve pressure retaining materials have met ASME Section II Specifications which require Visual Examin-ation of the casting or forging, and surfaces free of injurious defects.
V. ALTERNATE PROVISIONS:
Should any of the subject valve internal surfaces become accessible during maintenance activities, a Visual Examination will be per-formed at that time.
Rev. 0 2/8/82
SUMMARY
. OF THE MANUA'L AND REMOTE AUTOMATIC PRESERVICE EXAMINATIONS FOR SUSQUEHANNA UNIT ¹1
CATEGORY BA PRESSURE RETAINING WELDS IN REACTOR VESSEL CIRCUMFERENTIAL SHELL WELDS WELD SEAM AA AA TOP SIDE Remote Automatic Examination Covera e There were five (5) interferences on weld seam AA top that caused missed areas during the remote automatic examination. These were:
Nozzle NIA 66" Missed Nozzle NIB 66" Missed Nozzle N8A 36" Missed Nozzle N8B 36" Missed Surface Gou e 4" Missed*
TOTAL 208" Missed The circumference of weld seam AA is 837".
The interferences caused 24.85 percent of weld seam AA top to be missed during the remote automatic examination. *The 4" missed due to the surface gouge will be examined during the first ISI. The surface has been conditioned to allow examination. The missed area will at that time become 24.37 percent.
Manual Examination Covera e The nozzle interferences listed for the automatic examination do not exist for the manual examination. The nozzles Nl's and N8's are far enough from the weld centerline to allow a complete examination in accordance with Paragraph I-5121 of Section XI, Appendix I.
AA BOTTOM SIDE Remote Automatic Examination Not Performed Manual Examination Covera e No interferences. One hundred percent coverage.
SUMMARY
WELD SEAM AA One hundred percent of weld seam AA was manually examined in accordance with Appendix I of ASME Section XI. In addition, 75.15 percent of the top side of weld seam AA was examined using remote automatic equipment. Manual data exists for the 12.42 percent of the weld seam missed by the remote scanner and when combined with the remote examination data provides 100 percent coverage.
WELD SEAM AB Remote Automatic Examination Covera e Weld seam AB was examined 100 percent by the remote automatic equipment.
WELD SEAM AC Remote Automatic Examination Covera e Weld seam AC was examined 100 percent by the remote automatic equipment.
AD TOP SIDE Remote Automatic Examination Not performed.
Manual Examination Covera e No interferences 100 percent coverage.
AD BOTTOM SIDE Remote Automatic Examination Covers e There were two (2) interferences on weld seam AD bottom that caused missed areas during the remote automatic examination. These were:
Nozzle N11A 47" Missed Nozzle NllB 41" Missed TOTAL 88" Missed
The circumference of weld seam AD is 838". The interferences caused 10.5 percent of weld seam AD bottom to be missed during the remote automatic examination.
Manual Examination Covera e No interferences 100 percent coverage.
SUMMARY
FOR WELD SEAM AD One hundred percent of weld seam AD was manually examined in accordance with Appendix I of ASME Section XI. In addition, 89.5 percent of the bottom side of weld seam AD was examined using remote automatic equipment. Manual data exists for the 5.25 percent of the weld seam missed by the remote scanner and when combined with the remote examination data provides 100 percent coverage.
WELD SEAM AE Manual Examination Covera e Weld seam AE was examined 100 pere'ent by manual techniques.
WELD SEAM AF Manual Examination'Covera e Weld seam AF was examined 100 percent from one side in accordance with Paragraph I-5121 of ASME Section XI, Appendix I. In addition, a 0- only examination of weld AF was performed from the top surface of the vessel flange.
EXCLUSIONS No exclusions are required for the reactor pressure vessel circumferential welds AA, AB, AC, AD, AE and AF.
CATEGORY BA PRESSURE RETAINING WELDS IN REACTOR VESSEL LONGITUDINAL SHELL WELDS WELD SEAM BA BA LEFT SIDE CW Remote Automatic Examination Covera e There was one (1) interference on weld seam BA left side that caused a missed area during the remote automatic examination. This was:
Nozzle N2K 43" Missed The length of weld seam BA is 137".
The interference caused 31.38 percent of weld seam BA left side to be missed during the remote automatic examination.
Manual Examination Covera e No interference. One hundred percent coverage.
SUMMARY
WELD SEAM BA Eighty-four and three-tenth percent of weld seam BA was examined in accordance with Appendix I of ASME Section XI using remote automatic techniques. Manual data exists for the 15 ' percent of the weld seam missed by the remote scanner and when combined with the remote examination data provides 100 percent coverage.
WELD SEAM BB Remote Automatic Examination Covera e There was one (1) interference on weld seam BB left side that caused a missed area during the remote automatic examination. This was:
Nozzle N2C 46" Missed The length of weld seam BB is 137".
The interference caused 33.57 percent of weld seam BB left side to be missed during the remote automatic examination.
Manual Examination Covera e No interference. One hundred percent coverage.
BB RIGHT SIDE (CCW Remote Automatic Examination'Covera e No interference. One hundred percent coverage.
SUMMARY
WELD SEAM BB Eighty-three and two-tenth percent of weld seam BB was examined in accordance with Appendix I of ASME Section XI using remote automatic techniques. Manual data exists for the 16.8 percent of the weld seam missed by the remote scanner and when combined with the remote examination, data provides 100 percent coverage.
BC LEFT SIDE (CW)
Remote Automatic Examination Covera e There was one (1) interference on weld seam BC left side that caused a missed area during the remote automatic examination. This was:
Nozzle N2F 44" Missed The length of weld seam BC is 137".
The interference caused 32.12 percent of weld seam BC to be missed during the remote automatic examination.
Manual Examination Covers e No interference. One hundred percent coverage.
Remote Automatic Examination Covera e There was (1) interference on weld seam BC right side that caused a missed area during the remote automatic exami'nation. This was:
Nozzle N1B 69" Missed The interference caused 50.36 percent of weld seam BC right side to be missed during the remote automatic examination.
Manual Examination Covera e No interference. One hundred percent coverage.
SUMMARY
WELD SEAM BC Fifty-eight and eight-tenth percent of weld seam BC was examined in accordance l
with Appendix of ASME Section XI using remote automatic techniques. Manual data exists for the 41.2 percent of the weld seam missed by the remote scanner and when combined with the remote examination, data provides 100 percent coverage.
WELD SEAM BD Remote Automatic Examination Covera e Weld seam BD was examined 100 percent by the remote automatic equipment.
WELD SEAM BE Remote Automatic Examination Covera e Weld seam BE was examined 100 percent by the remote automatic equipment.
WELD SEAM BF Remote Automatic Examination Covera e There was one (1) interference on weld seam BF left side that caused a missed area during the remote automatic examination. This was:
18" Missed The length of weld seam BF is 137".
The interference caused 13.14 percent of weld seam BF left side to be missed during the remote automatic examination.
Manual Examination Covera e No interference. One hundred percent coverage.
BF RIGHT SIDE CCW Remote Automatic Examination Covers e There was one (1) interference on weld seam BF right side that caused a missed area during the remote automatic examination. This was:
Nozzle N16B 44" Missed The interference caused 32.12 percent of weld seam BF right side to be missed during the remote automatic examination.
Manual Examination Covera e N16B interference. One hundred percent coverage*.
- NOTE: An area 15" long was examined in one direction only for parallel reflectors in accordance with the requirements of Paragraph I-5121 of ASME Section XI, Appendix I.
SUMMARY
WELD SEAM BF Seventy-seven and four-tenth percent of weld seam BF was examined in accordance with Appendix I of ASME Section ZI using remote automatic techniques. Manual data exists for the 22.6 percent of the weld seam missed by the remote scanner and when combined with the remote examination data provides 100 percent coverage.
WELD SEAM BG BG LEFT SIDE (CW)
Remote Automatic Examination"Covera e There was one (1) interference on weld seam BG left side that caused a missed area during the remote automatic examination. This was:
RPV Stabilizer Bracket 8" Missed The length of weld seam BG is 137".
The interference caused 5.8 percent of weld seam BG left side to be missed during the remote automatic examination.
Manual Examination Covera e No interference. One hundred percent coverage.
BG RIGHT SIDE (CCW Remote Automatic Examination Covera e There was one (1) interference on weld seam BG right side that caused a missed area during the remote automatic examination. This was:
RPV Stabilizer Bracket 8" Missed The interference caused 5.8 percent of weld seam BG right side to be missed during the remote automatic examination.
Manual Examination Covera e No interference. One hundred percent coverage.
SUMMARY
WELD SEAM BG Ninety-four and two-tenth percent of, weld seam BG was examined in accordance with Appendix I of ASME Section XI using remote automatic techniques. Manual data exists for the 5.8 percent of the weld seam missed by the remote scanner, and when combined with the remote examination data provides 100 percent coverage.
WELD SEAM BH Remote Automatic Examination Covera e There was one (1) interference on weld seam BH left side that caused a missed area during the remote automatic examination. This was:
RPV Stabilizer Bracket 10" Missed The length of weld seam BH is 137".
The interference caused 7.3 percent of weld seam BH left side to be missed during the remote automatic examination.
Manual Examination Covera e No interference. One hundred percent coverage.
BH RIGHT SIDE CCW Remote Automatic =Examination Covera e There was one (1) interference on weld seam BH right side that caused a missed area during the remote automatic examination. This was:
RPV Stabilizer Bracket 11" Missed The interference caused 8.0 percent of weld seam BH right side to be missed during the remote automatic examination.
Manual Examination Covera e No interference. One hundred percent coverage.
SUMMARY
WELD SEAM BH Ninety-two and four-tenth percent of weld seam BH was examined in accordance with Appendix I of ASME Section XI using remote automatic techniques. Manual data exists for the 7.6 percent of the weld seam missed by the remote scanner and when combined with the remote examination data provides 100 percent coverage.
WELD SEAM BJ BJ LEFT SIDE (CW)
Remote Automatic Examination Covera e There was one (1) interference on weld seam BJ left side that caused a missed area during the remote automatic examination. This was:
RPV Stabilizer Bracket 9" Missed The length of weld seam BJ is 137".
The interference caused 6.6 percent of weld seam BJ left side to be missed during the remote automatic examination.
Manual Examination Covera e No interference. One hundred percent coverage.
BJ RIGHT SIDE CCW Remote Automatic Examination Covera e There was one (1) interference on weld. seam BJ right side that caused a missed area during the remote automatic examination. This was:
RPV Stabilizer Bracket 8" Missed The interference caused 5.8 percent of weld seam BJ right side to be missed during the remote automatic examination.
Manual Examination Covera e
No interference. One hundred percent coverage.
SUMMARY
WELD SEAM BJ Ninety-three and eight-tenth percent of weld seam BJ was examined in accordance with Appendix Z of ASME Section XI using remote automatic techniques. Manual data exists for the 6.2 percent of the weld seam missed by the remote scanner and when combined with the remote examination data provides 100 percent coverage.
WELD SEAM BK Manual Examination Covera e No interference. One hundred percent coverage.
WELD SEAM BM j Manual Examination Covera e No interference. One hundred percent coverage.
WELD SEAM BN Manual Examination Covera e No interference. One hundred percent coverage.
WELD SEAM BP Manual Examination Covera e No interference. One hundred percent coverage.
CATEGORY BA PRESSURE RETAINING WELDS IN REACTOR VESSEL CIRCUMFERENTIAL AND MERIDIONAL WELDS IN VESSEL HEADS CLOSURE HEAD TOP The following circumferential weld seams were examined manually with 100 percent coverage:
AG (Head to Flange)
AH (Dollar Plate to Side Plates)
The following meridional weld seams were examined manually with 100 percent coverage:
DJ (Side Plate to Side Plate)
DK (Side Plate to Side Plate)
DM (Side Plate to Side Plate)
DN (Side Plate to Side Plate)
DP (Side Plate to Side Plate)
DR (Side Plate to Side Plate)
SUMMARY
FOR CLOSURE HEAD WELD SEAMS All weld seams in the RPV closure head were examined in accordance with Appendix I of ASME Section XI using manual examination techniques. There were no interferences to the examination.
BOTTOM HEAD The following circumferential weld seam was examined manually with 100 percent coverage:
AJ (Dollar Plate to Side Plates)
The following longitudinal weld seams were examined manually with 100 percent
'overage:
DJ (Dollar Plate Longitudinal Seam)
DH (Dollar Plate Longitudinal Seam)
BOTTOM HEAD (Continued)
The following meridional weld seams were examined manually with partial coverage due to interference:
DA (Side Plate to Side Plate)
DB (Side Plate to Side Plate)
DC (Side Plate to Side Plate)
DD (Side Plate to Side Plate)
DE (Side Plate to Side Plate)
DF (Side Plate to Side Plate)
The weld buildup for the vessel skirt attachment caused an interference to the manual examination of weld seams DA DF. The interference caused unexamined volumes as follows:
0 0 Base Metal Exam 12% Missed 0 Weld Metal Exam 12% Missed 45 Exam 4% Missed 60 Exam 2% Missed A composite of all examination angles shows that a volume equal to 2 percent of the required examination volume for welds DA DF is completely unexamined.
Per Relief Request II8, PPSL requests relief from ASME Section XI examination requirements for the unexamined volumes as indicated above.
CATEGORY BD PRIMARY NOZZLE-TO-VESSEL WELDS AND NOZZLE INSIDE RADIUSED SECTIONS The following nozzle-to-vessel welds were examined 100 percent using remote automatic examination techniques:
NIA and B Recirculation Outlet Nozzles N2 A B E F G and K Recirculation Inlet Nozzles N3 A B C and D Main Steam Outlet Nozzles N4 B C E and F Feedwater Inlet Nozzles N5 A and B Core Spray Inlet Nozzles The following nozzle-to-vessel welds were examined partially using remote automatic examination techniques:
Recirculation Inlet (N2) Nozzles N2C
'288.8 Completely examined 71.2 Examined with a short scan due to interference from nozzle N8A N2D 313.5 Completely examined 46.5 Examined with a short scan due to interference from nozzle NSA N2H 314.9 Completely examined 45.1 Examined with a short scan due to interference from nozzle N8B N2J 321.5 Completely examined 38.5 Examined with a short scan due to interference from nozzle N8B
SUMMARY
OF N2 PARTIAL EXAMINATIONS The interference from the N8 nozzles caused a short scan of the affected areas. A scan length of 16" from the weld centerline is needed to achieve a complete examination of the required examination volume. The N8 nozzle interference allowed only a 13.75" scan length. This caused a missed volume of 19 percent in the affected areas. (81 percent was examined)
Manual data exists for the 19 percent of the affected areas missed by the remote scanner and when combined with the remote examination data, provides 100 percent coverage.
FEEDVATER INLET (N4) NOZZLES N4A 0
300 Completely examined 60 0 - Not examined due to interference from nozzle NllA N4D 300 0 - Completely examined 60 0 - Not examined due to interference from nozzle N11B.
SUMMARY
OF N4 PARTIAL EXAMINATIONS The proximity of nozzles Nll A and B to the affected feedwater nozzles precludes a complete Section XI examination of weld seams N4A and N4D. The
- spacing of 4.5" between the nozzles allows only a best effort manual
~examination of the areas. Partial manual data exists for the affected areas but does not provide 100 percent coverage. Per Relief Request 89, PP&L requests relief from ASME Section XI examination requirements for the unexamined volumes (16.67 percent of the weld seam).
MANUAL NOZZLE EXAMINATIONS The following nozzle-to-vessel welds were examined 100 percent using manual examination techniques:
N6 A&B Head Instrumentation Nozzles N7= Head Vent Nozzle N8 A&B -Jet Pump Instrumentation Nozzles N9 GRD Hydraulic Return Nozzle
CATEGORY BE PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS The following partial penetration welds were examined for evidence of leakage during the system hydrostatic test on Susquehanna Unit Ill.
N10 CoreLLP and Liquid Control Nozzle Nll A & B Instrumentation Nozzles Shell Course 83 N12 A & B Instrumentation Nozzles Shell Course 84 N13 Flange Seal Leak Detector Nozzle on Vessel Flange N15 RPV Bottom Head Drain Nozzle N16 A & B Instrumentation Nozzles Shell Course //2 Control Rod Drive Penetrations 185 In-Core Penetrations 55
CATEGORY BF
'PRESSURE RETAINING DISSIMILAR METAL WELDS NOZZLE TO SAFE END FIELDS Nozzle to safe end welds were examined in accordance with Table IWB-2600 of ASME Section XI.
The volumetric examination was manual ultrasonic testing in accordance with Appendix III of ASME Section XI.
The surface examination was liquid penetrant testing in accordance with Article 6 of ASME Section V.
The following safe end welds were completely examined in accordance with ASME Section XI:
N1A&B Recirculation Outlet N2A-K Recirculation Inlet N3A-D Main Steam Outlet N4A-F Feedwater Inlet N5 A & B (including extention)
Core Spray Inlet N6A&B Head Instrumentation N7 Head Vent N8A&B Jet Pump Instrumentation
- N9 CRD Hydraulic Return
- The N9 safe end has been removed and the nozzle has been capped. The nozzle-to-cap weld has not yet been examined, but it can be completely examined.
P
CATEGORY BG-1 PRESSURE RETAINING BOLTING TWO INCHES AND LARGER IN DIAMETER FLANGE CLOSURE NUTS Nut f/1 N /376 were completely surface examined in accordance with Table IWB-2600 of ASME Section XI. The examination was a wet magnetic particle examination in acordance with Article 7 of ASME Section V.
FLANGE CLOSURE STUDS Stud //1 Stud 876 were completely examined by both volumetric and surface techniques. The volumetric examination was ultrasonic in accordance with the requirements'of Article 5 of ASME Section V. The surface examination was a wet magnetic particle examination in accordance with Article 7 of ASME Section V.
LIGAMENTS BETWEEN FLANGE STUD HOLES The ligaments between stud holes 1 76 were volumetrically examined in accordance with Table IWB-2600 of ASME Section XI. The volumetric examination was ultrasonic in accordance with General Electric Company specifications.
FLANGE CLOSURE WASHERS Washer 81 Washer 876 were visually examined in accordance with Table IWB-2600 of ASME Section XI. The visual examination was in accordance with Article 9 of ASME Section V.
CATEGORY BH VESSEL SUPPORTS Weld *CG, the support skirt to skirt knuckle attachment weld, was completely examined volumetrically in accordance with Table IWB-2600 of ASME Section XI.
The volumetric examination was ultrasonic in accordance with Appendix I of ASME Section XI.
- NOTE P
The skirt knuckle was machined from a weld buildup designated as weld FR.
Weld FR was examined to the maximum extent possible as an addition to weld CG. Approximately 59 percent of weld seam FR was ultrasonically examined. Weld FR is an ASME Section III NF integral attachment to the pressure boundary and as such is not within the examination scope of Section XI.
CATEGORY BI-1 INTERIOR CLAD SURFACES OF REACTOR VESSELS VESSEL CLADDING Six (6) cladding examination patches were visually examined in accordance with Table IWB-2600 of ASME Section XI. The visual'examination was in accordance with Article 9 of ASME Section V.
CATEGORY BN-1 INTERIOR QF REACTOR VESSELS VESSEL INTERIOR All items and surfaces above and below the core support plate were visually examined in accordance with Table IWB-2600 of ASME Section XI. The visual examination was in accordance with Article 9 of ASME Section V. Items and surfaces normally accessible for ISI were also photographed to provide a comparison for ISI purposes.
CATEGORY BO PRESSURE RETAINING WELDS IN CONTROL ROD HOUSINGS CRD HOUSING WELDS The welds in CRD housings were exempted from volumetric examination based upon plant makeup capacity. They were examined for leakage during the system hydro.
CATEGORY BP COMPONENTS EXEMPTED FROM EXAMINATION BY IWB-1220 EXEMPTED COMPONENTS All components exempted from examination were examined for leakage during the system hydro.
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CATEGORY BN-2 INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSELS All core support and attachment welds were visually examined in accordance with Table IWB-2600 of ASME Section XI. The visual examination was in accordance with Article 9 of ASME Section V.
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