ML18040B033
| ML18040B033 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/01/1983 |
| From: | CURTIS N W PENNSYLVANIA POWER & LIGHT CO. |
| To: | SCHWENCER A Office of Nuclear Reactor Regulation |
| References | |
| PLA-1934, NUDOCS 8311070417 | |
| Download: ML18040B033 (112) | |
Text
,DOCKET 05000388 REGULA+V]ORMATION DISTRIBUTICSYS'I (BIOS)ACCESSION NBR;8311070417 DOC+DATE: 83/11/01 NOTARIZED:
NO FACIL;50 388 Susquehanna Steam Electric Stationi Unit 2<Pennsylva ADVS,BA'HE AUTHOR AFFILIATION CURHSiN,l't<
Pennsylvania Power 8 Light Co.RECIP NAMK RECIPIENT AFFILIATION SCHWENCERgA
~Licensing Branch 2
SUBJECT:
Forwards.Rev 1 to preservice insp plan L Rev 0 to preservice.
insp Relief Request 8 through 12qin connection w/SER Item~3k'~%DISTRIBUTION CODE: BOOIS COPIES RECEIVED(LTR
'NCL g'I E: TITLE!Licensing Submittal:
PSAR/FSAR Amdts 8,~lated Correspondence NOTESiicy NMSS/FCAF/PM
~LPDR 2cys, 05000388 RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB2 LA INTERNAL: ELD/HDS4 IE/DEPER/CPB 36 IE/DEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MKB 18 NRR/DE/SAB 24 NRR/DHFS/HFEB40 NRA/DHFS/PSRB NRR/DS I/AKB 26 NRR/DSI/CPB 10'RA/DSI/ICSB 16 NRR/DSI/PS 8 19 NRR/DSI/RSB 23 RGNi EXTERNALS ACRS 41 DMB/DSS (AMDTS)LP&R 03 NSIC 05 NOTES'OPIES LTTR ENCL 0 0 1 0 3 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 6 6 1 1 2 2 1 1 RECIPIENT ID CODE/NAME NRR LB2 BC PERCHgRB IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB'8 NRR/DE/MTKB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/DS I/METB 12 NRR/RAB 22 IL 04 RM/AMI/MI 8 BNL(AMDTS ONLY)FEMA REP DIY 39 NRC PDR 02 NTIS COPIES LTTR ENCL-'0 1 1 1 1 1 1 0 1 2 2 1 1 1 1 1 1 1 0 1 1 1 1: 1-1 1 0 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REUUIRED: LTTR57 ENCL 50
~0~Pennsylvania Power 8 Light Company Two North Ninth Street~Allentown, PA 18101 o 215/770.5151 Norman W.Curtis Vice President-Engineering 8 Construction-Nuclear NOY 0].>g83 Director of Nuclear Reactor Regulation Attention:
Mr.A.Schwencer, Chief Licensing Branch No.2 Division of Licensing U.S.Nuclear Regulatory ConaLssion Washington, DC 20555 SUSQUE9KNA STFDM EUKTRIC STATION SER ITEM NO.111 ER 100508 FILE 841-2 PZA-1934 Docket No.50-388
Dear Mr.Schwencer:
Enclosed for your review and approval are the following items for the Preservice Inspection Report for Susquehanna SES Unit 2: o Preservice Inspection Plan o Relief Request N8 o Relief Request N9 o'Relief Request 510 o Relief Request Ill o Relief Request 512 At the present time, the Presexvice Inspection Program is approximately 95%ccaplete.We anticipate that there will be no additional relief requests submitted, however existing relief requests may r~e revision to include same of the outstanding mcaminations.
The completion of the remaining examinations should not alter the existing relief requests significantly and therefore should not delay your review.If you have any questions or camnents, please contact us.Very truly yours, 4M N.W.Curtis Vice President-Engineering 6 Constxuction-Nuclear Enclosure cc: R.L.Perch NRC 8311070417 831101 PDR aDOCX 05000388-'PDR.I',
SUSQUEHANNA STEAM ELECTRIC STATION~UNIT 82 PRESERVICE EXAMINATION (CLASS 1)L ITEM NO.EXAMINATION CATEGORY (TABLE IWB-2500)COMPONENTS AND PARTS TO BE EXAMINED METHOD REMARKS-REACTOR VESSEL-Bl.l B-A Pressure-retaining welds in reactor vessel Longitudinal and circumfer-Volumetric ential shell welds meridional and circumferential head welds vessel-to-flange and head-to--flange circumferential-welds (4)(5)B1.4 B-D Full penetration welds of nozzle in vessel Primary nozzle-to-vessel welds and nozzle inside radiused section Volumetric (4)(12)B1.5 B-E Pressure-retaining partial penetration welds in vessels Vessel penetration, includ-Visual (IWA-5000)
(4)ing control rod drive and instrumentation penetration Bl.6 B-F Pressure-retaining dissimilar metal welds Nozzle-to-safe end welds Volumetric and Surface (4)Bl.7 B1.8 B1.9 B-G-1 B-G-1 B-G-1 Pressure-retaining bolting greater than 2" in diameter Pressure-retaining bolting greater than 2" in diameter Pressure-retaining bolting greater than 2" in diameter Nuts Pressure-retaining bolts and studs Ligaments between threaded stud and holes Surface Volumetric and Surface Volumetric (4)(4)(4)B1.10 B-G-1 Pressure-retaining bolting greater than 2" in diameter Closure washers, bushings Visual (4)Page 1 of 9, Revision 1, 10/83
'0 t e'I 1 f III q e 0 SUSQUEHANNA STEAM ELECTRIC STATION'UNIT 82 PRESERVICE EXAMINATION (CLASS 1)(Continued)
ITEM NO.EXAMINATION CATEGORY (TABLE IWB-2500)COMPONENTS AND PARTS TO BE EXAMINED METHOD REMARKS Bl.ll B-G-2 Pressure-retaining bolting smaller than or equal to 2" in diameter Pressure-retaining bolting Visual (4)B1.12 B-H Vessel supports Integrally welded vessel supports Volumetric (4)B1.13 B-I-1 Interior clad surface of reactor vessel Closure head cladding 1)Visual and Surface or 2)Volumetric (4)Bl.14 B-I-1 Interior clad surface of reactor vessel Vessel cladding Visual (4)B1.15 Bl.16 B-N-1 Interior of reactor vessel Vessel interior Visual B-N-2 Integrally welded core support Interior attachments and core Visual structures and interior attach-support structures ments to reactor vessel (4)(4)B1.18 B-0 Pressure-retaining welds in control rod drive housings Control rod drive housings Volumetric (4)Bl.19 B-P Components exempted from examination by IWB-1220 Exempted components Visual (IWA-5000)
(4)-PIPING PRESSURE BOUNDARY-B4.1 B-F Pressure-retaining dissimilar metal welds Safe-end to piping welds and safe-end in branch piping welds Volumetric and Surface Page 2 of 9, Revision 1, 10/83 0 h SUSQUEHANNA STEAM ELECTRIC STATION~UNIT 82 PRESERVICE EXAMINATION (CLASS 1)(Continued)
ITEM NO.B6-150~B-G-1 EXAMINATION CATEGORY (TABLE IMB-2500).Pressure-retaining bolting greater than 2" in diameter COMPONENTS AND PARTS TO BE EXAMINED Pressure-retaining bolting, in place METHOD Volumetric REMARKS<2)B6-160 B-G-1 Pressure-retaining bolting greater than 2" in diameter Pressure-retaining bolting, when removed Volumetric and Surface (2)B6.170~B-G-1 Pressure-retaining bolting greater than 2" in diameter Bolting surfaces Visual (VT-1)(2)B7.50 B-G-2 Pressure-retaining bolting, smaller than or equal to 2" in diameter Bolts, studs, and nuts Visual (VT-1)(2)B4.5 B-J Pressure-retaining welds in piping Circumferential and longitud-Volumetric inal piping welds (1)(8)(9)(10)B4.6 B4.7 B4.8 B-J-Pressure-retaining welds in piping B-J-Pressure-retaining welds in piping B-J Pressure-retaining welds in piping Branch pipe connection welds exceeding 6" in diameter Branch pipe connection welds 6" diameter and smaller Socket welds Volumetric Surface Surface (1)(8)(9)(10)B10.10~B-K-1 Support members for piping Integrally welded attachments Volumetric piping (3)B4.10 B4.11 B-P Components exempted from examination by IWB-1220 Exempted components B-K-2 Support components for piping Support components Visual Visual (IMA-5000)
Page 3 of 9, Revision 1, 10/83 l II I J Q SUSQUEHANNA STEAM ELECTRIC STATION'UNIT 82 PRESERVICE EXAMINATION (CLASS 1)(Continued)
ITEM NO.EXAMINATION CATEGORY (TABLE IWB-2500)COMPONENTS AND PARTS TO BE EXAMINED METHOD REMARKS-PUMP PRESSURE BOUNDARY-B6.180 B-G-1 B6.190 B-G-1 Pressure-retaining bolting greater than 2" in diameter Pressure-retaining bolting greater than 2" in diameter Pressure-retaining bolting, in place Pressure-retaining bolting, when removed Volumetric Volumetric and Surface (2)(2)B7.60'-G-2 Pressure-retaining bolting, smaller than or equal to 2" in diameter Bolts, studs, and nuts Visual (VT-1)(2)B10.20 B-K-1 Support members for pumps Integrally welded attachments-Surface pumps (3)B5.5 B5.7 B5.8 B-K-2 Support components for pumps B-L-2 Pump casings B-P Components exempted from examination by IWB-1220 Support components Pump casings Exempted components Visual Visual Visual (IWA-5000)
(6)-VALVE PRESSURE BOUNDARY-B6.210 B6.220 B-G-1 Pressure-retaining bolting greater than 2" in diameter B-G-1 Pressure-retaining bolting greater than 2" in diameter Pressure-retaining bolts and studs, in place Pressure-retaining bolts and studs, when removed Volumetric Volumetric and Surface (2)(2)Page 4 of 9, Revision 1, 10/83 0 I II N 4 1' SUSQUEHANNA STEAM ELECTRIC STATION'UNIT 82 PRESERVICE EXAMINATION (CLASS 1)(Continued)
ITEM NO.B6.3 B-G-2 EXAMINATION CATEGORY (TABLE IWB-2500)Pressure-retaining bolting smaller than or equal to 2" in diameter COMPONENTS AND PARTS TO BE EXAMINED Pressure-retaining bolting METHOD Visual REMARKS (2)B6.4 B6.5 B6.7 B6.8 B-P Components exempted from examination by IWB-1220 B-K-1 Support members for valves B-K-2 Support components for valves-B-M-2 Valve bodies Integrally welded supports Support components Valve bodies Exempted components Volumetric Visual Visual Visual (IWA-5000)
(3)(6)Page 5 of 9, Revision 1, 10/83
, 7 I 5 g4 A SUSQUEHANNA STEAM ELECTRIC STATION UNIT 82-PRESERVICE EXAMINATION (CLASS 2)ITEM NO.EXAMINATION CATEGORY (TABLE IWB-2500)COMPONENTS AND PARTS-TO BE EXAMINED METHOD REMARKS Cl.l C1.2 C-A Pressure-retaining welds in pressure vessels C-B Pressure-retaining nozzle welds in vessel-PRESSURE VESSELS-Circumferential butt welds Nozzle-to-vessel welds Volumetric Volumetric (1)(ll)(1)(11)C-C Integrally welded support attachment to vessels Integrally-welded support attachments Surface (3)C4.10 C-D Pressure-retaining bolting exceeding 2" diameter Bolts and studs Volumetric (2)-PIPING-C2.1 C-F Pressure-retaining welds in piping in systems which cir-culate reactor coolant Circumferential butt welds Volumetric (1)(8)(9)(10)C2.1 C-G Pressure-retaining welds in piping in systems which cir-culate other than reactor coolant Circumferential butt welds Volumetric (1)(8)(9)(10)C2.2 C-F Pressure-retaining welds in Longitudinal weld joints in Volumetric piping in systems which cir-fittings culate reactor coolant Page 6 of 9, Revision 1, 10/83 0'I SUSQUEHANNA STEAM ELECTRIC STATION UNIT/32 PRESERVICE EXAMINATION (CLASS 2)(Continued)
ITEM NO.EXAMINATION CATEGORY (TABLE IWB-2500)COMPONENTS AND PARTS TO BE EXAMINED METHOD REMARKS C2.2 C-G Pressure-retaining welds in piping in systems which cir-culate other than reactor coolant Longitudinyl weld joints in Volumetric fittings C2.3 C-F Pressure-retaining welds in piping in systems which cir-culate reactor coolant Branch pipe-to-pipe weld joints Volumetric C2.3 C-G Pressure-retaining welds in piping in systems which cir-culate other than reactor coolant Branch pipe-to-pipe weld joints Volumetric C4.20.C3.40~C-D Pressure-retaining bolting exceeding 2" diameter C-E-1 Support members for piping Bolts and studs Integrally-welded support attachments Volumetric Surface (2)(3)C2.6 C-E-2 Support components for piping Support components Visual-PUMPS-C3.1 CF Pressure-retaining welds in pumps in systems which cir-culate reactor coolant Pump shell welds Volumetric (7)C4.30~C-D Pressure-retaining bolting exceeding 1" diameter Bolts and studs Volumetric (2)Page 7 of 9, Revision 1, 10/83 V, I SUSQUEHANNA STEAM ELECTRIC STATION UNIT 82 PRESERVICE EXAMINATION (CLASS 2)(Continued)
ITEM NO.C3.70 EXAMINATION CATEGORY (TABLE IWB-2500)C-E-1 Support members for pumps COMPONENTS AND PARTS TO BE EXAMINED Integrally-welded support attachments METHOD Surface REMARKS (3)C3.4 C-E-2 Support components for pumps Support components Visual C4.2 C-D Pressure-retaining bolting exceeding 2" in diameter-VALVES-Bolts and studs Volumetric (2)C3.100 C-E-1 Support members for valves Integrally-welded support attachments Surface (3)C4.4 C-E-2 Support components for valves Support components Visual Footnotes:
1.Numbers listed designate applicable relief requests.2.Designates item number from upgraded Code edition and addenda.Page 8 of 9, Revision 1, 10/83 0 I~l t'h I I V 0 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 82 PRESERVICE EXAMINATION (CLASS 3)EXAMINATION REQUIREMENTS (IWD-2600)
REMARKS Components in systems or portions of systems shall be subjected to the following examinations: (a)Visual examination shall be conducted for evidence of component leakages (other than controlled or collected leakages), structural distress, or corrosion when the system is undergoing either a system inservice test, component functional test (i.e., valves and pumps)or a system pressure test.-(b)In the case of buried components (e.g., underground piping), valves shall be provided to permit isolation of the buried portions of piping for the purpose of conducting a system pressure test in lieu of the visual examination.
A loss of system pressure during the test shall constitute evidence of component leakage.(c)Supports (restraints) and hangers for components exceeding four-inch nominal pipe size whose structural integrity is relied upon to withstand design loads when the system function is required shall be visually examined to detect any loss of support capability, and evidence of inadequate restraint.
mts/chj260i:pas Page 9 of 9, Revision 1, 10/83 Id SUSQUEHANNA UNIT/32 PRESERVICE INSPECTION RELIEF RE VEST I/8 IDENTIFICATION OF COMPONENTS:
Class 1, Category BJ, pressure retaining welds in piping.Class 2, Category CF and CG pressure retaining welds in piping.Category BJ-Table IWB-2600, Item Numbers B4.5, B4.6, B4.7-of the ASME Code Code, 1974 Edition to Summer 1975 Addenda requires volumetric examination of 100%*of circumferential welds, longitudinal welds, and branch connections be performed completely as a preservice examination requirement prior to initial plant start-up.r H p(I Category CF/CG-Table IWC-2600, Item Numbers C2.1, C2.2, C2.3, C3.1-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 IWB-1220, IWC-1220.ASME Appendix III, Winter,.1975 Addenda, requires an angle beam~, examination og the'eld and required volume (the lesser of 1/2 or 1")be performed scanning both normal and parallel to the weld.BASIS FOR RELIEF: Relief is required from the ASME Section XI examination requirements on the basis of complete inaccessiblity of the weld and required volume due to plant design.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.All Class 1 and 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.MTS/rp)235c/pcs Page 1 of 2 Revision 0, 10/83 l I>>II')t, Il~C RELIEF RE UEST 88 NELD IDENTIFICATION NO.DBB-205-2-3J a CODE CATEGORY A ITEM NO.CC C2.1 X OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION Main Steam Pipe to Re-Qrapper Plate 100X: RT straint Insert SAFETY IMPACT Turbine Building vent Stack radiation monitor will detect significant leakage.Leakage greater than 250 CPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (500 CPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130X of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.DBB-221-I-FN1 CF C2.1 Reactor Pipe to Valve Nrapper Plate 100X Core Isol'ation Cooling!RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isoiation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser), Page 2 of 2 Revision 0, 10/83;4'.;i ,=rr a araa~a SUSQUEHANNA UNIT 82 PRESERVICE INSPECTION RELIEF RE UEST f19 IDENTIFICATION OF COMPONENTS:
Class 1, Category BJ, pressure retaining welds in piping.Class 2, Category CF and CG pressure retaining welds in piping.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, longitudinal welds, and branch connections be performed completely as a preservice examination requirements prior to initial plant start-up.Category CF/CG-Table IWC-2600, Item Numbers C2.1, C2.2, C2.3, C3.1-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 IWB-1200, IWC-1220.ASME Appendix III, Winter 1975 Addenda, requires an angle bepm examination of the weld and required volume (the less of 1/2 or 1")be performed scanning both normal and parallel to the weld.BASIS FOR RELIEF: Relief is required from the ASME Section XI examination requirements on the basis of partial inaccessibility of the weld and required volume due to plant design.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.Page 1 of ll Revision 0, 10/83 l~%It P i S 1 r, P) 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 these welds.V.ALTERNATE PROVISIONS:
A supplemental surface examination of the Class 2 welds will be performed where practical for preservice examination.
Class 1 welds have received surface examination to satisfy ASME Section III;retesting at this time is redundant, and bears no benefit to plant safety.Based on the most current Edition and Addenda of ASME Section XI, a surface examination of the welds will be required during subsequent inservice inspections, and will be more meaningful at that time.MTS/rp)237c/pcs
)RR 89, Page 2 of ll Revision 0, 10/83
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RELIEP RE VEST f9 MELD IDENTIFICATION NO.VNB-B21-3-20-F CODE CATEGORY A ITEM NO.BJ B4.5 Main Steam Pipe to Sweep-1 Lug o-let RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Z OF ASME NATURE OF SCAN SECTION III SAFETY SYSTEM CONPIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-204-1-5A CG C2.1 Main Steam Pipe to Re-4 Restraint straint Insert Braces 25Z RT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (>500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130Z of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.CG C2.1 Main Steam Pipe to Re-4 Restraint 25Z straint Insert Braces RT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (>500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130Z of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.Page 3 of 11 Revision 0, 10/83 WELD IDENTIFICATION NO.DBB-202-1-5A CODE CATEGORY A ITEM NO.X OF ASME NATURE OF SCAN SECTION III SYSTEH CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION CG Hain Steam Pipe to Re-4 Restraint 25X RT C2.1 straint Insert Braces SAFETY IMPACT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (7500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130X of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core'cooling systems, depending upon the size of the leak.DBB-201-1-3A CG C2.1 Hain Steam Pipe to Re-4 Restraint 25X straint Insert Braces RT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (%500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130X of normal flow in one main steam linc will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.Page 4 of 11 Revision 0, 10/83 WELD IDENTIFICATION NO.CODE X OF ASME CATEGORY NATURE OF SCAN SECTION III B ITEM NO.SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-203-1-5B CG Main Steam Pipe to Re-4 Restraint 25X RT C2.1 straint Insert Braces Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (7500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that, causes greater than 130X of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.VNB-B21-4-17-F BJ B4.5 Main Steam Pipe to Sweep-1 Lug o-let 5X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM;DBB-204-1-5B CG C2.1 Main Steam Pipe to Re-4 Restraint 25X straint Insert Braces RT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (7500 GPM)will overflow sump and flood detectors will alert operators.
Leak-.age that causes greater than 130X of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.Page 5 of 11 Revision 0, 10/83 CODE WELD CATEGORY IDENTIFICATION NO.A ITEM NO.X OF ASME NATURE OF SCAN SECTION III SAFETY SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT VRR-B31-3-10-M 1 BJ Recirc.Longitudinal Branch Line B4.5 Seam RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown vith leakage greater than 5 GPM.VRR-B31-3-10-L 1 BJ B4.5 Recirc.Longitudinal Branch Line Seam 5X RT/PT Affects RCPB;veld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-4-10-P 1 BJ Recirc.Longitudinal Branch Line 10X B4.5 Seam RT/PT Affects RCPB;veld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-3-10-Q 1 BJ B4.5 Recirc.Longitudinal Branch Line 10X Seam RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DBA-201-2-FW34
.BJ B4.5 Reactor.Pipe to Elbow Rigid Water Restraint Cleanup 35X RT/PT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolati'on of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdovn methods are available (e.g., feedvater, RCIC, main condenser).
1.Obstructed areas are located outside of the required examination area (12 inches from the intersection with the edge of a circumferential veld)for subsequent inservice inspections.
Page 6 of 11 Revision 0, 10/83 WELD IDENTIFICATION NO.CODE CATEGORY 4 ITEM NO.X OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-203-1-3A CG Main Steam Pipe to Re-4 Restraint 13X RT C2.1 straint Insert Braces Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage+500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130X of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.DBB-201-1-5B DLA-202-I-PW 19 CG C2.1 BJ B4.5 Main Steam Pipe to Re-4 Restraint straint Insert Braces Feedwater Pipe to Elbow Branch Line 13X 7X RT RT/PT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM vill be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (7500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130X of normal flow in one main steam line will automatically clos'e main steam linc isolation valves thereby isola-ting the leek.Plant shutdown can be accomplish-ed through thc use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Page 7 of 11 Revision 0, 10/83 gQ<f~>a CODE WELD CATEGORY IDENTIFICATION NO.A ITEM NO.Z OF ASHE NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT HBB-211-2-3-D CF C2.1 Residual Heat Removal Pipe to Elbow Hanger Weld 10X RT During plant power operation, weld not pressurized.
During normal system operation, (max.165 psig), significant leakage detected by leak'etection systems.Alternate shutdown cooling path (FSAR 15.2.9)is unaffected and condenser is also available for cooldown.GBB-215-1-5A CF Residual Pipe to C2.1 Heat Elbow Removal Lugs RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However.sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
l~-t 1 DBB-214-1-9A
'E DCA-208-1-FW11 CF C2.1 High Pressure Coolant In)ection.Pipe to Elbow-Lugs Branch Line BJ Residual Elbow to 84.5 Heat Valve Removal 5X 5X RT RT/PT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not,required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
During plant power operation, weld not pressurized.
During normal system operation, (max.165 psig), significant leakage detected by leak detection systems.Alternate shutdown cooling path (FSAR 15'.9)is unaffected and condenser is also available for cooldown.DLA-201-1-FW6 BJ B4.5 Feedwater Pipe to Valve Welded Whip-60X Restraint RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Page 8 of ll Revision 0, 10/83 WELD IDENTIFICATION NO.DBB-207-1-FW3 CODE CATEGORY A ITEM NO.X OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION CF Residual Pipe to Branch Line 10X RT C2.1 Heat Valve Removal SAFETY IMPACT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-.nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
DBB-207-2-FW3 CF C2.1 Residual Heat Removal Pipe to Valve Branch Line 5X RT During normal plant power operation, wclds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
DBB-219-1-1C CF C2.1 Feedwater Pipe to Tee Branch Line RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required-for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
DBB-213-1-FW3 CG C2.1 Core spray Pipe to Pipe Branch Line RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one core spray loop.Plant can be safely cooled down by unaffected'ore spray loop.Page 9 of 11 Revision 0, 10/83 CODE WELD CATEGORY IDENTIFICATION NO.A ITEM NO.X OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-207-I-FWI CF Residual Pipe to Branch Line 15X RT C2.1 Heat Valve Removal During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
VBB-202-1-FW1 CG Control Pipe to C2.1 Rod Drive Reducer Branch Line 5X RT During normal operation of the CRD system, sig-nificant leakage will be detected by area radiation monitors.Leakage can be manually isolated.DBB-214-I-IOB CG C2.1 High Pressure Coolant Infection Pipe to Flange Branch Line 15X RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC,~main condenser).
DBB<<221-3-FW3 CF C2.1 Reactor Pipe to Valve 1)Branch Line 18X Core 2)Geometry Isolation Cooling RT Leak detection systems detect veld leakage, re<<suiting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are availablc (e.g., feedwater, RCIC, main condenser).
HBB<<211-2-11B CF Residual Pipe to C2.1 Heat Tee Removal Plate Ad)scent 5X to Weld RT During plant power operation, weld not pressurized.
During normal system operation, (max.165 psig), significant leakage detected by leak detection systems.Alternate shutdown cooling path (FSAR 15'.9)is unaffected and condenser is also available for cooldown.Page 10 of 11 Revision 0, 10/83 CODE WELD'ATEGORY IDENTIFICATION NO.'ITEM NO.X OF ASME NATURE OF SCAN SECTION IIX SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-221-3-FW2 CF C2.1 Reactor Core Isolation Cooling Tee to Valve 1)Branch Line 10X RT 2)Geometry Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
CG C2.1 High Pressure Coolant In)ection Pipe to Valve Pipe Support SX RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
I GBB-205-2-1A f CF C2.1 Residual Hest Removal Reducer to Welded Hanger 25X Reducer RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-.nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
Page 11 of 11 Revision 0, 10/83 SUSQUEHANNA UNIT 82 PRESERVICE INSPECTION RELIEF RE UEST//10 IDENTIFICATION OF COMPONENTS:
Class 1, Category BJ, pressure retaining welds in piping.Class 2, Category CF and CG pressure retaining welds in piping.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, longitudinal welds, and branch connections be performed completely as a preservice examination requirement prior to initial plant start-up.Category CF/CG-Table IWC-2600, Item Numbers C2.1, C2.2, C2.3, C3.1-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 IWB-1220, IWC-1220.I ASME Appendix III, Winter 1975 Addenda, requires an angle beam examination of the weld and required volume (the lesser of 1/2 or 1")be performed scanning both normal and parallel to the weld.BASIS FOR RELIEF: Relief is required from the ASME Section XI examination requirements on the basis of inaccessibility of the weld and required volume due to geometric configuration.
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 the applicable examination and testing requirements of ASME Section III.Page 1 of 16 Revision 0, 10/83 I U r'-
2)Other system welds 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.V.ALTERNATE PROVISIONS:
The structural integrity of all Class 1 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 increased levels of plant safety.Based on the most current Edition and Addenda of ASME Section XI, a surface examination of the welds will be required during subsequent inservice inspections, and will be more meainingful at that time.Class 2 piping welds will receive a supplemental surface examination where practical.
Welds requiring relief from examination requirements due to geometric configuration were evaluated for radiographic examination 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 f/2 and implemented as required.MTS/rp)236c/pcs RR filo Page 2 of 16 Revision 0, 10/83 RELIEF RE UEST 810 WELD IDENTIFICATION NO.VRR-B31-3-FWA10 CODE CATEGORY 4 ITEM NO.BJ B4.5 Recirc.Sweep-o-let to Riser Pipe Part Geometry 25X RT/PT X OF ASME NATURE OF SCAN SECTION III SYSTEM.CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT Affects RCPB;veld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdovn with leakage gieater than 5 GPM.VRR-B31-3-FWA11 BJ B4.5 VRR-B31-3-FWA13 BJ B4.5 Recirc.Recirc.Sweep-o-let Part Geometry 25X to Riser Pipe Sweep-o-let Part Geometry 25X to Riser Pipe RT/PT RT/PT Affects RCPB;veld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-3-FWA14 BJ B4.5 Recirc.Sweep>>o-let Part Geometry'5X to Riser Pipe RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdovn with leakage-greater than 5 GPM.VRR-B31-4-FWB10 BJ B4.5 Recite.Sweep-o-let to Riser Pipe Part Geometry 25X RT/PT Affects RCPB;veld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31%-FWB11 BJ B4.5 Recirc.Svcep-o-let Part Geometry 25X to Riser Pipe RT/PT Affects RCPB;veld cannot be isolated.However RCPB leek detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-4-FWB13 BJ B4.5 Recirc.Sveep-o-let Part Geometry 25X to Riser Pipe RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Page 3 of 16 Revision 0, 10/83 CODE MELD CATEGORY IDENTIFICATION NO.&ITEM NO.X OF ASHE NATURE OP SCAN SECTION III SAFETY SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IHPACT VRR-B31-4-FWB14 BJ B4.5 Recirc.Sweep-o-let to Riser Pipe Part Geometry 25X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-3-FWA33 BJ B4.5 Rccirc.Tce to Valve Part Geometry 100X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-4-FWB33 BJ Recirc.Tee to B4.5 Valve Part Geometry 100X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPH.VRR-B31-3-PWA24 BJ B4~5 Recirc.Valve F032 A Part Geometry 100X to Pipe RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31%-PWB24 BJ B4.5 Recirc.Valve F0328 Part Geometry 100X to Pipe RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-4-FWB23 BJ B4.5 Recirc.Elbow to Valve Part Geometry 25X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPH.VRR-B31-3-3-P BJ B4.5 Recirc.Pipe to Cross Part Geometry 15X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Page 4 of 16 Revision 0, 10/83 WELD IDENTIFICATION NO.DCA-207-1-FW-3 CODE CATEGORY&ITEM NO.BJ B4.5 Core Spray Valve F006A Part Geometry to Valve F007A 100X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Z OF ASME NATURE OF SCAN SECTION III SAFETY SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DCA-207-2-FW3 BJ B4.5 Core Spray Valve F006B Part Geometry 100X to Valve F007B RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DLA-204-I-FW5 DLA-204-1-FW21 BJ B4.5 BJ B4.5 Feedwater Pipe to Safe End Feedwater Pipe to Safe End Part Geometry 35X Part Geometry 35X RT/PT RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage..Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.I DLA-202-I-FW5 BJ Feedwater Pipe to B4.5 Safe End Part Geometry 35X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DLA-202-1-FW10 BJ B4.5 r DBA 216 1 FWC14 NA Feedwater Pipe to Safe End Hain Steam Elbow to (Augmented)
Branch Pert Geometry 35X Part Geometry 30X RT/PT RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.Page 5 of 16 Revision 0, 10/83 HELD IDENTIFICATION NO.CODE CATEGORY A ITEM NO.X OF ASME NATURE OF SCAN'SECTION III SAFETY SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBA-214-I-FHA14 NA Main Steam Elbow to (Augmented)
Branch Part Geometry 30X RT/PT Affects reactor coolant preseure boundary*(RCPB);however.inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.DBA-214-I-FW22 NA Main Steam Elbow to (Augmented)
Tee Part Geometry 30X RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems'hich alert plant personnel to inspect and shutdown plant using unaffected systems.DBA-212-1-FW4 BJ Main Steam Tee to Tee Part Geometry 30X B4.5 RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DBB-215-I~FHIO CF C2.1 Residual Heat Removal Elbow to Valve Part Geometry 10X RT/PT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
DBB-215-1-FH6 CF Residual Elbow to C2.1 Heat Valve Removal Part Geometry 10X RT/PT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC.main condenser).
Page 6 of 16 Revision 0, 10/83 CODE MELD CATEGORY IDENTIFICATION NO.&ITEM NO.X OP ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT GBB-212-2-FW14 CF C2.1 Residual Valve F007B Part.'eometry 8X RT Heat to Flued Head Removal Containment boundary weld that is not normally pressurized during plant power operation.
Dur-ing normal system operation, leak detection systems would detect significant leakage.Max-imum system operating pressures at welds are 460 psig for RHR, 150 psig for HPCI, 25 psig for RCIC.HPCI and RCIC are not required for normal shutdowns.
Cooldown is achieved by the unaffect-ed RHR Loop or the main condenser.
GBB-212-I-FW14 CF C2.1 Residual Valve F007A Part Geometry 33X Heat to Plued Head Removal RT Containment boundary weld that is not normally pressurized during plant power operation.
Dur-ing normal system operation, leak detection systems would detect significant leakage.Max-imum system operating pressures at welds are 460 psig for RHR, 150 psig for HPCI, 25 psig for RCIC.HPCI and RCIC are not required for normal shutdowns.
Cooldown is achieved by the unaffect-ed RHR Loop or the main condenser.
GBB-216-2-FN1 CF C2.1 Residuai Heat Removal Reducer to Nozzle Part Geometry 10X RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
Page 7 of 16 Revision 0, 10/83 WEM IDENTIFICATION NO.GBB-206-1-FW2 CODE CATEGORY A ITEM NO.X OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION CF Residual Tee to Part Geometry 33X RT C2.1 Heat Valve Removal SAFETY IMPACT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However.sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
GBB-216-1-FW1 GBB-205-1-FW1 CF C2.1 CF C2.1 Residual Heat Removal Residual Heat Removal Reducer to Nozzle Valve to Reducer Part Geometry 15X Part Geometry 65X RT RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion s'ystems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffecbed RHR loop or main condenser.
DLA-203-I-FW2 BJ Feedwater Flued Head to Part Geometry 25Z B4.5 Valve RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.Page 8 of 16 Revision 0, 10/83 CODE WELD CATEGORY IDENTIFICATION NO.A ITFM NO.X OF ASME NATURE OF SCAN SECTION III SAFETY SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DCA-207-I-FW5 BJ B4.5 Core Spray Reducer Part Geometry to Nozzle 20X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DCA-207-2-FW10 BJ B4.5 Core Spray Reducer to Nozzle Pert Geometry 15X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DCA-202-2-FW1 BJ B4.5 Reactor Water Cleanup Tee to Weld-o-let Part Geometry 60X RT/PT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
DCA-209>>1.-FW2 DCA-209-2-FW2 BJ B4.5 BJ B4.5 Core Spray Flued Head to Part Gcomctry 50X Valve Core Spray Flued Heed to Part Geometry 50X Valve RT/PT RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.Page 9 of 16 Revision 0, 10/83
WELD IDENTIFICATION NO.CODE CATEGORY A ITEM NO.X OF ASME NATURE OF SCAN SECTION III SAFETY, SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBA-201-1-FW10 BJ B4.5 Reactor Water Cleanup Flued Head to Valve Part Geometry 20X RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.DBA-202-2-FW6 BJ B4.5 High Pressure Coolant Infection Flued Head to Part Geometry 18X Valve RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be deteched by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.DCA-210-1-FWB DCA-211-3.-FW12 BJ B4.5 BJ B4.5 Residual Heat Removal Residual Heat Removal Elbow to Valve Elbow to Flange Part Geometry 10X Part Geometry 8X RT/PT RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.GBB-201-4-FW1 CG C2.1 Core Spray Pipe to Valve Part-Geometry 8X RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of w'eld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.Page 10 of 16 Revision 0, 10/83 CODE WELD CATEGORY IDENTIFICATION NO.&ITEM NO.X OF ASME NATURE OF SCAN~SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT GBB-204-3-FW15 CF Residual Pipe to Part Geometry 10X RT C2.1 Heat Flange Removal During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
EBB-202-1-FW4 CG C2.1 High Pressure Coolant Infection Pipe to Flange Part Geometry 8X RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
EBB-202-1TFW5 CG C2.1 High Pressure Coolant In>ection Pipe to Plange Part Geometry 8X RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g..feedwater, RCIC, main condenser).
DBB-222-1-3B NA Reactor Water Cleanup (Augmented)
Tee to Flange Part Geometry IOX RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
DCA-211-3-2A BJ Residual Pipe B4.5 Heat to Flange Removal Part Geometry 20X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.-i Page 11 of 16 Revision 0, 10/83 HELD IDENTIFICATION NO.CODE CATEGORY A ITEM NO.Z OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT HBB-218-2-FW5 CG Containment Pipe Part Geometry 13X RT C2.1 Atmosphere to Valve Control During normal plant power operation, weld is not pressurized.
During normal system operation, weld is exposed to a pressure of less than 10 inches of water.Any leakage is detectable dur-ing Integrated Leak Rate Testing as required by plant Tech.Specs.System is not required for plant shutdown.HBB-201-1-FW3 CG C2.1 Reactor Core Isolation Cooling Pipe to Valve Part Geometry 13Z RT Leak detection system detects significant leak-age;containment isolation valves perform weld isolation function., HPCI performs backup func-tion for RPV water addition for safe shutdown.HBB-201-1-FW10 GBB-205-2-FW3 CG C2.1 CF C2.1 Reactor Core Isolation Cooling Residual Heat Removal'ipe to Valve Pipe to Valve Part Geometry 10X Part Geometry 10X RT RT Leak detection system detects significant Ieak-age;containment isolation valves perform weld isolation function.HPCI performs backup func-tion for RPV water addition for safe shutdown.~(During normal plant power dperation, welds are not under pressure.During normal system operation>
significant leakage of weld can affect pres-sure boundary of one RHR lbp.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
Page 12 of 16 Revision 0, 10/83 CODE WELD CATEGORY IDENTIFICATION NO.A ITEM NO.X OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT HBB-211-2-FW14 CF Residual Valve to Part Geometry 10X RT C2.1 Heat Elbow Removal During normal plant power operation, welds are'ot under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
HBB-201-1-FW4 CG C1.2 Reactor Core Isolation Cooling Flued Head to Part Geometry 10X Valve RT Containment boundary weld that is not normally pressurized during plant operation.
During nor-mal system operation, leak detection systems would detect significant leakage.Maximum sys-tem operating pressures'at welds are 460 psig for RHR, 150 psig for HPCI, 25 psig for RCIC.HPCI and RCIC are not required for normal shut-downs.Cooldown is achieved by the unaffected RHR loop or the main condenser.
2P-206-A-361-4-6 B C D CG Core Spray Elbow to C2.1 (Pump)'ozzle Part Geometry 10X~~RT During normal plant power operation>
weld is not pressurized.
During normal system operation, weld is under.a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.-Y@pe~2P-202-A-3614-6 B C D CF C2.1 Residual Heat Removal (Pump)Elbow to Nozzle Part Geometry.30X RT During normal plant power operation, weld is not pressuilzed.
During normal system operation, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop..Plant can be safely cooled down by unaffected RHR loop.Page 13 of 16 Revision 0, 10/83 CODE HELD CATEGORY IDENTIFICATION NO.6 ITEM NO.X OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT Residual Heat Removal (Pump)2P-202-A-361-1-5 CF Support Shell Part Geometry 10X RT B C2.1 to Head Hub C D During normal plant power operation,-weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.2P-202-A-361-5-13 B C D 2P-202-AT361-3-13 B C D.CP C2.1 CF C2.1 Residual Heat Removal (Pump)Residual Heat Removal (Pump)Nozzle to Vertical Support Shell Flange to Nozzle Part Geometry 10X'art Geometry 10X RT RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.During normal plant power operation.
veld is not pressurized.
During normal system operation, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.2P-202-A-361-5-6 B C D CF C2.1 Residual Heat Removal (Pump)Elbow to Vertical Support Shell Part Geometry;10Z During normal plant power operation, veld is not pressurized.
During normal system operation, veld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.Page 14 of 16 Revision 0, 10/83 WELD IDENTIFICATION NO.CODE CATEGORY 4 ITEM NO.X OP ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT 2P-206-A 361-5-13 B C D CG C2.1 Core Spray Inlet Nozzle to Part Geometry 10X RT (Pump)Vertical Support Shell During normal plant power operation, veld is not pressurized.
During normal system operation, veld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of veld can affect one core spray loop.Plant can be safely cooled dovn by unaffected core spray loop.2P-206-A 361-5-6 CG B C2.1 C D Core Spray Elbow to (Pump)Vertical Support Shell Part Geometry 10X RT During normal plant pover operation, veld is not pressurized.
During normal system operation, veld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of veld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.GBB-201-1-FW2 CG C2.1 CG C2.1 Core Spray Valve to Pipe Control Rod Pipe to Drive Elbow Part Geometry 25Z Part Geometry 5X RT RT During normal plant pover operation, weld is not pressurized.
During normal system operation, veld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of veld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.During normal operation of the CRD system, significant leakage vill be detected by area radiation monitors.Leakage can be manually isolated.Page 15 of 16 Revision 0, 10/83
CODE HEID CATEGORY IDENTIFICATION NO.A ITEM NO.Z OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT GBB-204-I-FN7 CF Residual Valve to Part Geometry 5Z RT C2.1 Heat Pipe Removal During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
mts/ch)2501:pas Page 16 of 16 Revision 0, 10/83
I~SUSQUEHANNA UNIT//2 PRESERVICE INSPECTION RELIEF RE UEST//11 I.IDENTIFICATION OF COMPONENTS:
Class 2 pressure retaining welds and pressure retaining nozzle welds in the Residual Heat Removal heat exchangers.
Category C-A of ASME Section XI, 1974 Edition to Summer 1975 Addenda requires volumetric examination of shell and head circumferential discontinuity welds and base material for one plate thickness beyond the edge of the weld)oint.Category C-B of ASME Section XI, 1974 Edition to Summer 1975 Addenda requires volumetric examination of 100%of the nozzle-to-vessel attachment welds.These examinations must be performed completely, once, as a preservice examination requirement prior to initial plant startup.III.BASIS FOR RELIEF: Relief is required from the ASME Section XI examination requirements on the basis of partial inaccessibility of the weld due to design of the component.
IV.JUSTIFICATION:
The justification for requesting relief from ASME Section XI preservice examination requirements is as follows: 1)The structural integrity of the pressure boundary has been verified by ASME Section III construction code testing requirements.
I'.2)Accessible portions of the welds have been satisfactorily inspected to ASME Section XI.V.ALTERNATE PROVISIONS:
I, A surface examination.
will be performed on the unexamined areas.mts/rp)259c:pas Page 1 of 2 Revision 0, 10/83
~e>e 7 I IIEET I~"l I'1~
RELIEF RE HEST Oil WELD IDENTIFICATION NUHBER CODE CATEGORY AND ITEM NUMBER SYSTEM NATURE OF CONFIGURATION OBSTRUCTION X OF SCAN OBSTRUCTED APPROXIMATED ASME SECTION III EXAMINATION SAFETY IMPACT 2E-205-A-R CA C1~1 RHR Shell to Head Welded 5X PT, UT, RT Attachment During normal plant power operation, weld is not pressurized.
During normal system opera-tion, veld is under a maximum pressure of 460 psig.Leak detection system detects significant leakage and can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.2E-205-A-A 2E-205-A-AC CB C1.2 CA C1.1 RHR Shell to Nozzle RHR Shell to Flange Ad)scent Weld Outlet Nozzle 20X 20X PT, UT, RT PT, UT, RT~2E-205-B-R 2E-205-B-A 2E-205-B-AC 2E-205-A-P CA C1.1 CB C1.2 CA C1.1 CB C1.2 RHR Shell to Head RHR Sheil to Nozzle RHR Shell to Flange RHR Shell to Nozzle Welded Attachment Ad)scent Weld Outlet Nozzle Adjacent Weld-o-let 20X 20X 5X PT, UT, RT PT, UT, RT PT, UT, RT PT, UT>RT 2E-205-B-P mts/chg259c:pas CB C1.2 RHR Shell to Nozzle Ad)scent Weld-o-let PT, UT, RT Page 2 of 2 Revision 0, 10/83 (ta,l+I SUSQUEHANNA UNIT//2 PRESERVICE INSPECTION RELIEF RE UEST//12 I.IDENTIFICATION OF COMPONENTS:
Class 1 feedwater inlet nozzles N4A and N4D.II.CODE REQUIREMENTS:
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 seems N4A and N4D as follows: N4A 300'Completely examined (automatic) 60'Not examined due to interference from nozzle NllA N4D 300'Completely examined (automatic) 60'ot examined due to interference from nozzle NllB Spacing of only 4.5" between the nozzles'allows only a best effort manual examination of the affected areas.Page 1 of 2 Revision 0, 10/83
~"~~~H N l LS I N')))'~1 I,I "IV.JUSTIFICATION:
The justification for requesting relief from ASME Section XI examination requirements is as follows: 1)The excluded area is 16.67 percent of the weld seam;83.33 percent has 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 tested following RPV hydrotest and accepted.V.ALTERNATE PROVISIONS:
Due to extensive testing already performed during fabrication, no additional NDE is required to establish integrity of the welds.mts/rp)259c:pas Page 2 of 2 Revision 0, 10/83 RELIEF RE UEST i/8 CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO,%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-205-2-3 J CG C2.1 Main Steam Pipe to Re-Wrapper Plate 100%~i RT straint Insert Turbine Building vent Stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130%of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe, shutdown system or emergency core cooling systems, depending upon the size of the leak.DBB-221-1-FWl CF C2.1 Reactor Core Isolation Cooling']Pipe to Valve Wrapper Plate 100%RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown, methods are available (e.g., feedwater, RCIC, main condenser).
Page 2 of 2 Revision 0, 10/83 NLW RELIEF REQUEST I/9 CODE WELD CATEGORY-IDENTIFICATION NO.5 ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT VNB-B21-3-20-F BJ B4.5 Main Steam Pipe to Sweep-1 Lug o-let 3%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DBB-204-1-5A CG C2.1 Main Steam Pipe to Re-4 Restraint-straint Insert Braces 25%RT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage ()500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130%of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.DBB-202-1-3A CG C2.1 Main Steam Pipe to Re-4 Restraint straint Insert Braces 25%RT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be.detected by turbine building radwaste sump high level alarm.Large amounts of leakage (>500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130%of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.0 Page 3 of ll Revision 0, 10/83 I V RELIEF REQUEST 89 (Continued)
CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO.%OF.ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-202-1-5A CG C2.1 Main Steam Pipe to Re-'Restraint 25%RT straint Insert Braces Turbine building vent stack radiation monitor will detect significant leakage.:Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (@500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130%of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core'cooling systems, depending upon the size of the leak.DBB-201-1-3A CG C2.1 Main Steam Pipe to Re-4 Restraint straint Insert Braces 25%RT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage (2500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130%of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-'d through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.Page 4 of ll Revision 0, 10/83 l l)(4 l I J RELIEF REQUEST 89 (Continued)
CODE WELD CATEGORY IDENTIFICATION NO.&ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-203-1-5B CG C2.1 Main Steam Pipe to Re-straint Insert 4 Restraint Braces 25%RT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage ($500 GPM)will overflow sump-and flood detectors will alert operators.
Leak-age that causes greater than 130%of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.VNB-B21-4-17-F DBB-204-1-5B BJ B4.5 CG C2.1 Main Steam Pipe to Sweep-1 Lug o-let Main Steam Pipe to Re-4 Restraint straint Insert Braces 5%25%RT/PT RT Affects RCPB;weld cannot be isolated.HoweverRCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump, high level alarm.Large amounts of leakage (7500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130%of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.Page 5 of ll Revision 0, 10/83
$1 CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO.X OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT VRR-B31-3-10-M 1 BJ B4.5 Recirc.Longitudinal Seam Branch Line 5X RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech., Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-3-10-L 1 VRR-B31-4-10-P 1 VRR-B31-3-10-q 1 BJ B4.5 BJ B4.5 BJ B4.5 Recirc.Recirc.Recirc.Longitudinal Seam Branch Line Longitudinal Branch Line Seam Longitudinal Branch Line Seam 5X 10X 10X RT/PT RT/PT RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DBA-201-2-FW34
.BJ B4.5 Reactor Water Cleanup Pipe to Elbow Rigid Restraint 35X RT/PT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolati'on of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
1.Obstructed areas are located outside of the required examination area (12 inches from the intersection with the edge of a circumferential weld)for subsequent inservice inspections.
Page 6 of ll Revision 0, 10/8 U\W 34 a CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO./o OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-203-1-3A CG C2.1 Main Steam Pipe to Re-4 Restraint 13/RT straint Insert Braces Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage ()500 GPM)will overflow sump and flood detectors will alert operators.
Leak-age that causes greater than 130/of normal flow in one main steam line will automatically close main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.DBB-201-1-5B CG C2.1 Main Steam Pipe to Re-4 Restraint straint Insert Braces 13/RT Turbine building vent stack radiation monitor will detect significant leakage.Leakage greater than 250 GPM will be detected by turbine building radwaste sump high level alarm.Large amounts of leakage+500 GPM)will overflow sump.and flood detectors will alert operators.
Leak-age that causes greater than 130/of normal flow in one main steam line will automatically clos'e main steam line isolation valves thereby isola-ting the leak.Plant shutdown can be accomplish-ed through the use of safe shutdown system or emergency core cooling systems, depending upon the size of the leak.DLA-202-1-FW19 BJ B4.5 Feedwater Pipe to Elbow Branch Line 7/RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.0 Page 7 of ll Revision 0, 10/83
, l'J'1'I I II P 1 1 CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT HBB-211-2-3-D CF C2.1 Residual Heat Removal Pipe to Elbow Hanger Weld 10%RT During plant power operation, weld not pressurized.
During normal system operation, (max.165 psig), significant leakage detected by leak'etection systems.Alternate shutdown cooling path (FSAR 15.2.9)is unaffected and condenser is also available for cooldown.GBB-215-1-5A CF C2.1 Residual Heat Removal Pipe to Elbow Lugs 5%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
DBB-214-1-9A CF C2.1 High Pressure Coolant Inj ection.Pipe to Elbow Lugs 5%RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
DCA-208-1-FWll BJ B4.5 Residual Heat Removal Elbow to Valve Branch Line 5%RT/PT During plant power operation, weld not pressurized.
During normal system operation, (max.165 psig), significant leakage detected by leak detection systems.Alternate shutdown cooling path (FSAR 15.2.9)is unaffected and condenser is also available for cooldown.DLA-201-1-FW6 BJ B4.5 Feedwater Pipe to Valve Welded Whip Restraint 60%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak-detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Page 8 of 11 Revision 0, 10/83 0 t ,e Ih H 4" t III RELIEF REQUEST//9 (Continued)
CODE MELD CATEGORY IDENTIFICATION NO.&ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-207-1-FW3 CF C2.1 Residual Heat Removal Pipe to Valve Branch Line 10%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of-weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
DBB-207-2-FW3 CF C2.1 Residual Heat Removal Pipe to Valve Branch Line 5%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant.leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
DBB-219-1-1C CF C2.1 Feedwater Pipe to Tee Branch Line 5%RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
DBB-213-1-PW3 CG C2.1 Core spray Pipe to Pipe Branch Line 5%RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.0 Page 9 of ll Revision 0, 10/8
¹lt MM"'l 4 I I I 4'I I 1 I 0 l t'I\V 0 q~V'I I I I/IMJ 4 I M 1,)'I M~I I J I\t ,J ,r I¹I I¹It t ,t I~I I M CODE%OF ASME WELD CATEGORY NATURE OF SCAN SECTION III IDENTIFICATION NO.5 ITEM NO.SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-207-1-FWl CF C2.1 Residual Heat Removal Pipe to Valve Branch Line 15%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
VBB-202-1-FWl CG C2.1 Control Rod Drive Pipe to Reducer Branch Line 5%During normal operation of the CRD system, sig-nificant leakage will be detected by area radiation monitors.Leakage can be manually isolated.DBB-214-1-10B CG C2.1 High Pressure Coolant Injection Pipe to Flange Branch Line 15%RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, ma'in condenser).
DBB-221-3-FW3 CF C2.1.Reactor Core Isolation Cooling Pipe to Valve l)Branch Line 2)Geometry 18%RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
HBB-211-2-llB CF C2.1 Residual Heat Removal Pipe to Tee Plate Adjacent to Weld 5%RT During plant power operation, weld not pressurized.
During normal system operation, (max.165 psig), significant leakage detected by leak detection systems.Alternate shutdown cooling path (FSAR 15.2.9)is unaffected and condenser is also available for cooldown.Page 10 of ll Revision 0, 10/83 I II
~i8 CODE WELD CATEGORY IDENTIFICATION NO.'ITEM NO.X OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBB-221-3-FW2 CF C2.1 Reactor Core Isolation Cooling Tee to Valve 1)Branch Line 2)Geometry lOX RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
DBB-217-1-FW2 CG C2.1 High Pressure Coolant Injection Pipe to Valve Pipe Support 8X RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
GBB-205-2-1A CF C2.1 Residual Reducer to.Heat Reducer Removal Welded Hanger'5/RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-.nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
Page ll of 11 Revision 0, 10/8 r I t 0 I IK 7 I N I RELIEF RE UEST iI10 CODE WELD CATEGORy IDENTIFICATION NO.a ITEM NO%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT VRR-B31-3-FWA10 B4.5 Recirc.-Sweep-o-let to Riser Pipe Part Geometry 25%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-3-FWA11 VRR-B31-3-FWA13 VRR-B31-3-FWA14 BJ B4.5 BJ B4.5 BJ B4.5 Recirc.Recirc.Recirc.Sweep-o-let to Riser Pipe Sweep-o-let to Riser Pipe Sweep-o-let to Riser Pipe Part Geometry 25%Part Geometry 25%Part Geometry 25%RT/PT RT/PT RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB.leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-4-FWB10 VRR-B31-4-FWBll VRR-B31-4-FWB 13 BJ B4.5 BJ B4.5 BJ=B4.5 Recirc.Recirc.Recirc.Sweep-o-let to Riser Pipe Sweep-o-let to Riser Pipe Sweep-o-let to Riser Pipe Part Geometry 25%Part Geometry 25%Part Geometry 25%RT/PT RT/PT RT/PT Affects RCPB;weld cannot be isolated.However'RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Page 3 of 16 Revision 0, 10/8 lh J'I I;I~I II k II e RELIEF REQUEST//10 (Continued)
CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT VRR-B31-4-FWB14 BJ B4.5 Recirc.Sweep-o-let Part Geometry 25%RT/PT to Riser Pipe Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs'equire plant shutdown with leakage greater than 5 GPM.VRR-B31-3-FWA33 VRR-B31-4-FWB33 BJ B4.5 BJ B4.5 Recirc.Recirc.Tee to Valve Tee to Valve Part Geometry 100%Part Geometry 100%RT/PT RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs'equire plant shutdown with leakage greater than 5 GPM.VRR-B31-3-FWA24 BJ B4~5 Recirc.Valve F032 A Part Geometry 100%RT/PT to Pipe Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage'.Plant Tech.Specs'equire plant shutdown with leakage greater than 5 GPM.VRR-B31-4-FWB24 BJ B4~5 Recirc.Valve F032B to Pipe Part Geometry 100%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs'equire plant shutdown with leakage greater than 5 GPM.VRR-B31-4-FWB23 BJ B4~5 Recirc.Elbow to Valve Part Geometry 25%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.VRR-B31-3-3-F BJ B4~5 Recirc.Pipe to Cross Part Geometry 15%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs'equire plant shutdown with leakage greater than 5 GPM.Page 4 of 16 Revision 0, 10/
H I f~~I I 6 6'6!6 r!6~4~6~I 6 6!6 RELIEF REQUEST f/10 (Continued)
CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO,%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DCA-207-1-FW-3 DCA-207-2-FW3 DLA-204-1-FW5 DLA-204=1-FW21 DLA-202-1-FW5 DLA-202-1-FW10 DBA-216-1-FWC14 BJ B4.5 BJ B4.5 BJ B4.5 BJ B4.5 BJ B4.5 BJ B4.5 NA Core Spray Valve F006A to Valve F007A Core Spray Valve F006B to Valve F007B Feedwater Pipe to Safe End Feedwater Pipe to Safe End Feedwater Pipe to Safe End Feedwater Pipe to Safe End Main Steam Elbow to (Augmented)
Branch Part Geometry 100%Part Geometry 100%Part Geometry 35%Part Geometry 35%Part Geometry 35%Part Geometry 35%Part Geometry 30%RT/PT RT/PT RT/PT RT/PT RT/PT RT/PT RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.Page 5 of 16 Revision 0, 10/8 I t f'J I'h e'I CODE WELD CATEGORy IDENTIFICATION NO.<ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DBA-214-1-FWA14 NA Main Steam Elbow to (Augmented)
Branch Part Geometry 30%RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.DBA-214-1-FW22
.NA Main Steam Elbow to (Augmented)
Tee Part Geometry 30%RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.DBA-212-1-FW4 BJ B4.5 Main Steam Tee to Tee Part Geometry 30%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DBB-215-1-.FW10 CF C2.1 Residual Heat Removal Elbow to Valve Part Geometry 10%RT/PT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater,-
DBB-215-1-FW6 CF C2.1 Residual Heat Removal Elbow to Valve Part Geometry 10%RT/PT Leak detection systems detect weld leakage, re-'ulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
Page 6 of 16 Revision 0, 10/8 I 4"~I'I V I 1 7 I'I lt It II fl RELIEF REQUEST//10 (Continued)
CODE WELD CATEGORy IDENTIFICATION NO~5 ITEM NO%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT GBB-212-2-FW14 CF C2.1 Residual Heat Removal Valve F007B to Flued Head Part'eometry 8%RT Containment boundary weld that is not normally-.pressurized during plant power operation.
Dur-ing normal system operation, leak detection systems would detect significant leakage.Max-imum system operating pressures at welds are 460 psig for RHR, 150 psig for HPCI, 25 psig for RCIC.HPCI and RCIC are not required for normal shutdowns.
Cooldown is achieved by the unaffect-ed RHR Loop or the main condenser.
GBB-212-1-FW14 CF C2.1 Residual Valve F007A Heat to Flued Head Removal Part Geometry 33%RT Containment boundary weld that is not normally pressurized during plant power operation.
Dur-ing normal system operation, leak detection systems would detect significant leakage.Max-imum system operating pressures at welds are 460 psig for RHR, 150 psig for HPCI, 25 psig for RCIC.HPCE and RCIC are not required for normal shutdowns.
Cooldown is achieved by the unaffect-ed RHR Loop or the main condenser.
GBB-216-2-FW1 CF C2.1 Residuai Heat Removal Reducer to Nozzle Part Geometry 10%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
Page 7 of 16 Revision 0, 10/8 s a~~I t P l h J l I)~g L I II II 0 IH 3 CODE MELD CATEGORy IDENTIFICATION NO.5 ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT GBB-206-1-FW2 CF C2.1 Residual Tee to Part Geometry 33%Heat Valve Removal RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.Ho~ever, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
GBB-216-1-FW1 CF C2.1 Residual Reducer to Heat Nozzle Removal Part Geometry 15%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
GBB-205-1-FML CF C2.1 Residual Valve to Heat Reducer Removal Part Geometry 65%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
DLA-203-1-Ff<2 BJ B4.5 Feedwater Flued Head to Part Geometry 25%Valve RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.Page 8 of 16 Revision 0, 10/83
~~)I~lt~F 1~th~tt 7!.t I~'4)tg CODE MELD CATEGORY IDENTIFICATION NO.>ITEM NO.%OF ASME NATURE OF SCAN SECTION III'SYSTEM , CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT DCA-207-1-FW5 B4.5 Core Spray Reducer to Nozzle Part Geometry 20%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DCA-207-2-FW10 BJ B4.5 Core Spray Reducer to Nozzle Part Geometry 15%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DCA-202-2-FW1 BJ B4.5 Reactor Water Cleanup Tee to Weld-o-let Part Geometry 60%RT/PT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
DCA-209-1.-FW2 BJ B4.5 Core Spray Flued Head to Part Geometry 50%Valve RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.DCA-209-2-FW2 BJ B4.5 Core Spray Flued Head to Part Geometry 50%Valve RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.Page 9 of 16 Revision 0, 10/83 I$n l 1 k 4 l J 3 1 7 F 4~I CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO.%OF ASME NATURE OF SCAN , SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY.IMPACT DBA-201-1-FW10 BJ B4.5 Reactor Water Cleanup Flued Head to Part Geometry 20%RT/PT Valve Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be detected by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.DBA-202-2-FW6 BJ B4.5 High Pressure Coolant Injection Flued Head to Part Geometry 18%Valve RT/PT Affects reactor coolant pressure boundary (RCPB);however, inside containment isolation valve per-forms RCPB isolation function.Any significant RCPB leakage would be deteched by leak detection systems, which alert plant personnel to inspect and shutdown plant using unaffected systems.DCA-210-1-FW8 BJ B4.5 Residual Heat Removal Elbow to Valve Part Geometry 10%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.DCA-211-3;FW12 GBB-201-4-FWl BJ B4.5 CG C2.1 Residual Heat Removal Elbow to Flange Part Geometry Core Spray Pipe to Valve Part Geometry 8%8%RT/PT RT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.During normal plant power operation, weld is not pressurized.
During normal system operation, t weld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.Page 10 of 16 Revision 0, 10/83 (J 1'I CODE WELD CATEGORY IDENTIFICATION NO.6 ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT GBB-204-3-FW15 CF C2.1 Residual Heat Removal Pipe to Flange Part Geometry 10%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
EBB-202-1-FW4 EBB-202-1-.FW5 CG C2.1 CG C2.1 High Pressure Coolant Injection High Pressure Coolant Inj ection Pipe to Flange Pipe to Flange Part Geometry Part Geometry 8%8%RT RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
DBB-222-1-3B NA Reactor Water Cleanup (Augmented)
Tee to Flange Part Geometry 10%RT Leak detection systems detect weld leakage, re-sulting in either manual or automatic isolation of leak.These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).
DCA-211-3-2A BJ B4.5 Residual Heat Removal Pipe to Flange Part Geometry 20%RT/PT Affects RCPB;weld cannot be isolated.However RCPB leak detection systems detect leakage.Plant Tech.Specs.require plant shutdown with leakage greater than 5 GPM.Page ll of 16 Revision 0, 10/83 1~(4'5 4'1)0 4'4'4 4 4 4 I J 4 1 L CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT HBB-218-2-FW5 CG C2.1 Containment Pipe Atmosphere to Valve Control Part Geometry 13%RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is exposed to a pressure of less than 10 inches of water.Any leakage is detectable dur-ing Integrated Leak Rate Testing as required by plant Tech.Specs.System is not required for plant shutdown.HBB-201-1-FW3 CG C2.1 Reactor Core Isolation Cooling Pipe to Valve Part Geometry 13%RT Leak detection system detects significant leak-age;containment isolation valves perform weld isolation function.HPCI performs backup func-tion for RPV water addition for safe shutdown.HBB-201-1-FW10 CG C2.1 Reactor Core Isolation Cooling Pipe to Valve Part Geometry 10%RT Leak detection system detects significant leak-age;containment isolation valves perform weld isolation function.HPCI performs backup func-tion for RPV water addition for safe shutdown.GBB-205-2-FW3 CF C2.1 Residual Heat Removal'ipe to Valve Part Geometry 10%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
Page 12 of 16 Revision 0, 10/83 I c~II'I t I ll I N CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO.%OF ASME NATURE OF SCAN.SECTION III SYSTEM=CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT HBB-211-2-FW14 CF C2.1 Residual Heat Removal Valve to Elbow Part Geometry 10%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
HBB-201-1-FW4 CG C1.2 Reactor Core Isolation Cooling.Flued Head to Part Geometry 10%Valve RT Containment boundary weld that is not normally pressurized during plant operation.
During nor-mal system operation, leak detection systems would detect significant leakage.Maximum sys-tem operating pressures'at welds are 460 psig for RHR, 150 psig for HPCI, 25 psig for RCIC.HPCI and RCIC are not required for normal shut-downs.Cooldown is achieved by the unaffected RHR loop or the main condenser.
2P-206-A-361-4-6 B C D CG C2.1 Core Spray (Pump)'lbow to Nozzle Part Geometry 10%RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under.a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.2P-202-A-361-4-6 B C D CF C2.1 Residual Heat Removal (Pump)Elbow to Nozzle Part Geometry 30%RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.Page 13 of 16 Revision 0, 10/8 1 w1 ,~'I ws S~IL',~'
CODE'ELD CATEGORY IDENTIFICATION NO.5 ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT 2P-202-A-361-1-5 B C D CF C2.1 Residual Heat Removal (Pump)Support Shell Part Geometry 10%RT to Head Hub During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.2P-202-A-361-5-13 B C D 2P-202-A-.361-3-13 B C D.CF C2.1 CF C2.1 Residual Heat Removal (Pump)Residual Heat Removal (Pump)Nozzle to Vertical Support Shell Flange to Nozzle Part Geometry 10%'art Geometry 10%RT RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.2P-202-A-361-5-6 B C D CF C2.1 Residual Heat Removal (Pump)Elbow to Vertical Support Shell Part Geometry 10%RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.Page 14 of 16 Revision 0, 10/8
~c CODE WELD CATEGORY IDENTIFICATION NO.&ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION
.OBSTRUCTED EXAMINATION SAFETY IMPACT 2P-206-A 361-5-13 CG B C2.1 C D Core Spray Inlet Nozzle to Part Geometry 10%(Pump)Vertical Support Shell RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.2P-206-A 361-5-6 B C D CG C2.1 Core Spray Elbow to (Pump)Vertical Support Shell Part Geometry 10%RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.GBB-201-1-FW2 CG C2.1 Core Spray Valve to Pipe Part Geometry 25%RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 475 psig.Leak detection system detects significant leak-age.Significant leakage of weld can affect one core spray loop.Plant can be safely cooled down by unaffected core spray loop.VBB-202-1-5B CG C2.1 Control Rod Pipe to Drive Elbow Part Geometry 5%RT During normal operation of the CRD system, significant leakage will be detected by area radiation monitors.Leakage can be manually isolated.Page 15 of 16 Revision 0, 10/8
~r 7 IP RELIEF REQUEST 810 (Continued)
CODE WELD CATEGORY IDENTIFICATION NO.5 ITEM NO.%OF ASME NATURE OF SCAN SECTION III SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT GBB-204-1-FW7 mts/ch)250i:pas CF C2.1 Residual Heat Removal Valve to Pipe Part Geometry 5%RT During normal plant power operation, welds are not under pressure.During normal system operation, significant leakage of weld can affect pres-sure boundary of one RHR loop.However, sig-nificant leakage is detectable by leak detec-tion systems or loss of system function.Plant can be safely cooled down by unaffected RHR loop or main condenser.
Page 16 of 16 Revision 0, 10/8 o.I I RELIEF RE UEST 811 WELD IDENTIFICATION NUMBER CODE CATEGORY%OF SCAN ASME AND NATURE OF OBSTRUCTED SECTION III ITEM NOSER SYSTEM CONFIGURATION OBSTRUCTION (APPROXIMATED)
EXAMINATION SAFETY IMPACT 2E-205-A-R 2E-205-A-A CA C1.1 CB C1.2 RHR Shell to Head Welded Attachment RHR Shell to Nozzle Adjacent Weld 5%20%PT, UT, RT PT, UT, RT During normal plant power operation, weld is not pressurized.
During normal system opera-tion, weld is under a maximum pressure of 460 psig.Leak detection system detects significant leakage and can affect one RHR loop.Plant can be safely cooled down by unaffected RHR loop.2E-205-A-AC 2E-205-B-R 2E-205-B-A CA C1.1 CA C1.1 CB C1.2 RHR Shell to Flange Outlet Nozzle RHR Shell to Head Welded Attachment RHR Shell to Nozzle Adjacent Weld 20%5%20%PT, UT, RT PT, UT, RT PT, UT, RT 2E-205-B-AC CA C1.1 RHR Shell to Flange Outlet Nozzle 20%PT, UT, RT 2E-205-A-P CB C1.2 RHR Shell to Nozzle Adjacent Weld-o-let 5%PT, UT, RT 2E-205-B-P CB C1.2 RHR Shell to Nozzle Adjacent Weld-o-let 5%PT, UT, RT mts/chj259c:pas Page 2 of 2.Revision 0, 10/83 t t+'I~'~J h