Text

Forwards Rev 1 to Preservice Insp Plan & Rev 0 to Preservice Insp Relief Request 8 Through 12,in Connection W/Ser Item 111
	ML18040B033
Person / Time
Site:	Susquehanna
Issue date:	11/01/1983
From:	Curtis N; PENNSYLVANIA POWER & LIGHT CO.
To:	Schwencer A; Office of Nuclear Reactor Regulation
References
	PLA-1934, NUDOCS 8311070417
	Download: ML18040B033 (112)
	v • d • e

REGULA+V ]ORMATION DISTRIBUTICSYS'I (BIOS)

ACCESSION NBR;8311070417 DOC+DATE: 83/11/01 NOTARIZED: NO ,DOCKET FACIL;50 388 Susquehanna Steam Electric Stationi Unit 2< Pennsylva 05000388 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 DISTRIBUTION CODE: BOOIS TITLE! Licensing

~3k'~%

COPIES RECEIVED(LTR Submittal: PSAR/FSAR Amdts 8,

'NCL g'I E:

~lated Correspondence NOTESiicy NMSS/FCAF/PM ~ LPDR 2cys, 05000388 RECIPIENT RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL-'

NRR/DL/ADL 0 NRR LB2 BC 0 NRR LB2 LA 0 PERCHgRB 1 1 INTERNAL: ELD/HDS4 1 0 IE FILE 1 1 IE/DEPER/CPB 36 3 IE/DEPER/IRB 35 1 1 IE/DEQA/QAB NRR/DE/CEB NRR/DE/EQB NRR/DE/MKB 21 11 13 18 1

1 1

2 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB '8 NRR/DE/MTKB 17 2

1 0

1 2

1 NRR/DE/SAB 24 1 1 NRR/DE/SGEB 25 1 1 NRR/DHFS/HFEB40 1 1 NRR/DHFS/LQB 32 1 1 NOTES'OPIES NRA/DHFS/PSRB NRR/DS I/AKB 26 NRR/DSI/CPB 10 1

1 1

NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 1 0 1

1 1:

'RA/DSI/ICSB 16 1 1 NRR/DS I/METB 12 1 NRR/DSI/PS 8 19 1 1 NRR /RAB 22 1-NRR/DSI/RSB 23 1 IL 04 1 RGNi 3 3 RM/ AMI/MI8 1 0 EXTERNALS ACRS 41 6 6 BNL(AMDTS ONLY) 1 1 DMB/DSS (AMDTS) 1 1 FEMA REP DIY 39 1 1 LP&R 03 2 2 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REUUIRED: LTTR 57 ENCL 50

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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 o Relief Request 512 Ill 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 same of the outstanding mcaminations. The completion r~eof the remaining revision to include 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

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SUSQUEHANNA STEAM ELECTRIC STATION

~UNIT 82 L PRESERVICE EXAMINATION (CLASS 1)

ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS NO. (TABLE IWB - 2500) TO BE EXAMINED METHOD REMARKS REACTOR VESSEL Bl.l B-A Pressure-retaining welds Longitudinal and circumfer- Volumetric (4) (5) in reactor vessel ential shell welds meridional and circumferential head welds vessel-to-flange and head-to-flange circumferential-welds B1.4 B-D Full penetration welds of Primary nozzle-to-vessel Volumetric (4) (12) nozzle in vessel welds and nozzle inside radiused section B1.5 B-E Pressure-retaining partial Vessel penetration, includ- Visual (IWA-5000) (4) penetration welds in vessels ing control rod drive and instrumentation penetration Bl. 6 B-F Pressure-retaining dissimilar Nozzle-to-safe end welds Volumetric and (4) metal welds Surface Bl.7 B-G-1 Pressure-retaining bolting Nuts Surface (4) greater than 2" in diameter B1.8 B-G-1 Pressure-retaining bolting Pressure-retaining bolts Volumetric and (4) greater than 2" in diameter and studs Surface B1.9 B-G-1 Pressure-retaining bolting Ligaments between threaded Volumetric (4) greater than 2" in diameter stud and holes B1.10 B-G-1 Pressure-retaining bolting Closure washers, bushings Visual (4) greater than 2" in diameter Page 1 of 9, Revision 1, 10/83

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SUSQUEHANNA STEAM ELECTRIC STATION

'UNIT 82 PRESERVICE EXAMINATION (CLASS 1)

(Continued)

ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS NO. (TABLE IWB 2500) TO BE EXAMINED METHOD REMARKS Bl.ll B-G-2 Pressure-retaining bolting Pressure-retaining bolting Visual (4) smaller than or equal to 2" in diameter B1.12 B-H Vessel supports Integrally welded vessel Volumetric (4) supports B1.13 B-I-1 Interior clad surface of Closure head cladding 1) Visual and (4) reactor vessel Surface or

2) Volumetric Bl.14 B-I-1 Interior clad surface of Vessel cladding Visual (4) reactor vessel B1.15 B-N-1 Interior of reactor vessel Vessel interior Visual (4)

Bl.16 B-N-2 Integrally welded core support Interior attachments and core Visual (4) structures and interior attach- support structures ments to reactor vessel B1. 18 B-0 Pressure-retaining welds in Control rod drive housings Volumetric (4) control rod drive housings Bl. 19 B-P Components exempted from Exempted components Visual (IWA-5000) (4) examination by IWB-1220

-PIPING PRESSURE BOUNDARY-B4.1 B-F Pressure-retaining dissimilar Safe-end to piping welds and Volumetric and metal welds safe-end in branch piping Surface welds Page 2 of 9, Revision 1, 10/83

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SUSQUEHANNA STEAM ELECTRIC STATION

~UNIT 82 PRESERVICE EXAMINATION (CLASS 1)

(Continued)

ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS NO. (TABLE IMB 2500) TO BE EXAMINED METHOD REMARKS B6-150~ B-G-1 .Pressure-retaining bolting Pressure-retaining bolting, Volumetric <2) greater than 2" in diameter in place B6-160 B-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric and (2) greater than 2" in diameter when removed Surface B6.170~ B-G-1 Pressure-retaining bolting Bolting surfaces Visual (VT-1) (2) greater than 2" in diameter B7.50 B-G-2 Pressure-retaining bolting, Bolts, studs, and nuts Visual (VT-1) (2) smaller than or equal to 2" in diameter B4.5 B-J Pressure-retaining welds in Circumferential and longitud- Volumetric (1) (8) (9) (10) piping inal piping welds B4.6 B-J- Pressure-retaining welds in Branch pipe connection welds Volumetric (1) (8) (9) (10) piping exceeding 6" in diameter B4.7 B-J- Pressure-retaining welds in Branch pipe connection welds Surface piping 6" diameter and smaller B4.8 B-J Pressure-retaining welds in Socket welds Surface piping B10.10~ B-K-1 Support members for piping Integrally welded attachments Volumetric (3) piping B4. 10 B-K-2 Support components for piping Support components Visual B4.11 B-P Components exempted from Exempted components Visual (IMA-5000) examination by IWB-1220 Page 3 of 9, Revision 1, 10/83

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SUSQUEHANNA STEAM ELECTRIC STATION

'UNIT 82 PRESERVICE EXAMINATION (CLASS 1)

(Continued)

ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS NO. (TABLE IWB - 2500) TO BE EXAMINED METHOD REMARKS PUMP PRESSURE BOUNDARY B6.180 B-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric (2) greater than 2" in diameter in place B6.190 B-G-1 Pressure-retaining bolting Pressure-retaining bolting, Volumetric and (2) greater than 2" in diameter when removed Surface B7.60'-G-2 Pressure-retaining bolting, Bolts, studs, and nuts Visual (VT-1) (2) smaller than or equal to 2" in diameter B10.20 B-K-1 Support members for pumps Integrally welded attachments- Surface (3) pumps B5.5 B-K-2 Support components for pumps Support components Visual B5.7 B-L-2 Pump casings Pump casings Visual (6)

B5.8 B-P Components exempted from Exempted components Visual (IWA-5000) examination by IWB-1220 VALVE PRESSURE BOUNDARY B6.210 B-G-1 Pressure-retaining bolting Pressure-retaining bolts and Volumetric (2) greater than 2" in diameter studs, in place B6.220 B-G-1 Pressure-retaining bolting Pressure-retaining bolts and Volumetric and (2) greater than 2" in diameter studs, when removed Surface Page 4 of 9, Revision 1, 10/83

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SUSQUEHANNA STEAM ELECTRIC STATION

'UNIT 82 PRESERVICE EXAMINATION (CLASS 1)

(Continued)

ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS NO. (TABLE IWB 2500) TO BE EXAMINED METHOD REMARKS B6.3 B-G-2 Pressure-retaining bolting Pressure-retaining bolting Visual (2) smaller than or equal to 2" in diameter B6.4 B-K-1 Support members for valves Integrally welded supports Volumetric (3)

B6.5 B-K-2 Support components for valves Support components Visual B6.7 B-M-2 Valve bodies Valve bodies Visual (6)

B6.8 B-P Components exempted from Exempted components Visual (IWA-5000) examination by IWB-1220 Page 5 of 9, Revision 1, 10/83

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SUSQUEHANNA STEAM ELECTRIC STATION UNIT 82-PRESERVICE EXAMINATION (CLASS 2)

ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS-NO. (TABLE IWB 2500) TO BE EXAMINED METHOD REMARKS PRESSURE VESSELS Cl.l C-A Pressure-retaining welds Circumferential butt welds Volumetric (1) (ll) in pressure vessels C1.2 C-B Pressure-retaining nozzle Nozzle-to-vessel welds Volumetric (1) (11) welds in vessel C-C Integrally welded support Integrally-welded support Surface (3) attachment to vessels attachments C4.10 C-D Pressure-retaining bolting Bolts and studs Volumetric (2) exceeding 2" diameter PIPING C2.1 C-F Pressure-retaining welds in Circumferential butt welds Volumetric (1) (8) (9) (10) piping in systems which cir-culate reactor coolant C2.1 C-G Pressure-retaining welds in Circumferential butt welds Volumetric (1) (8) (9) (10) piping in systems which cir-culate other than reactor coolant 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

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SUSQUEHANNA STEAM ELECTRIC STATION UNIT /32 PRESERVICE EXAMINATION (CLASS 2)

(Continued)

ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS NO. (TABLE IWB 2500) TO BE EXAMINED METHOD REMARKS C2.2 C-G Pressure-retaining welds in Longitudinyl weld joints in Volumetric piping in systems which cir- fittings culate other than reactor coolant C2.3 C-F Pressure-retaining welds in Branch pipe-to-pipe weld Volumetric piping in systems which cir- joints culate reactor coolant C2.3 C-G Pressure-retaining welds in Branch pipe-to-pipe weld Volumetric piping in systems which cir- joints culate other than reactor coolant C4.20. C-D Pressure-retaining bolting Bolts and studs Volumetric (2) exceeding 2" diameter C3.40~ C-E-1 Support members for piping Integrally-welded support Surface (3) attachments C2.6 C-E-2 Support components for piping Support components Visual PUMPS C3.1 CF Pressure-retaining welds in Pump shell welds Volumetric (7) pumps in systems which cir-culate reactor coolant C4.30~ C-D Pressure-retaining bolting Bolts and studs Volumetric (2) exceeding 1" diameter Page 7 of 9, Revision 1, 10/83

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SUSQUEHANNA STEAM ELECTRIC STATION UNIT 82 PRESERVICE EXAMINATION (CLASS 2)

(Continued)

ITEM EXAMINATION CATEGORY COMPONENTS AND PARTS NO. (TABLE IWB 2500) TO BE EXAMINED METHOD REMARKS C3.70 C-E-1 Support members for pumps Integrally-welded support Surface (3) attachments C3.4 C-E-2 Support components for pumps Support components Visual VALVES C4.2 C-D Pressure-retaining bolting Bolts and studs Volumetric (2) exceeding 2" in diameter C3.100 C-E-1 Support members for valves Integrally-welded support Surface (3) attachments 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

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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.

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 r H p(

requirement prior to initial plant start-up.

I

+ 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.

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RELIEF RE UEST 88 CODE X OF ASME NELD CATEGORY NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. A ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-205-2-3J CC Main Steam Pipe to Re- Qrapper Plate 100X : RT Turbine Building vent Stack radiation monitor C2.1 straint Insert will detect significant leakage. Leakage greater than 250 CPM will be detected by turbine a

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 Reactor Pipe to Valve Nrapper Plate 100X RT Leak detection systems detect weld leakage, re-C2.1 Core sulting in either manual or automatic isoiation Isol'ation of leak. These lines are not required for nor-Cooling! mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser),

Page 2 of 2 Revision 0, 10/83

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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

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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.

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RELIEP RE VEST f9 CODE Z OF ASME MELD CATEGORY NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. A ITEM NO. SYSTEM CONPIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT VNB-B21-3-20-F BJ Main Steam Pipe to Sweep- 1 Lug RT/PT Affects RCPB; weld cannot be isolated. However B4.5 o-let RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DBB-204-1-5A CG Main Steam Pipe to Re- 4 Restraint 25Z RT Turbine building vent stack radiation monitor C2. 1 straint Insert Braces 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 Main Steam Pipe to Re- 4 Restraint 25Z RT Turbine building vent stack radiation monitor C2.1 straint Insert Braces 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

CODE X OF ASME WELD CATEGORY NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. A ITEM NO. SYSTEH CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-202-1-5A CG Hain Steam Pipe to Re- 4 Restraint 25X RT Turbine building vent stack radiation monitor C2.1 straint Insert Braces 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 Hain Steam Pipe to Re- 4 Restraint 25X RT Turbine building vent stack radiation monitor C2. 1 straint Insert Braces 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

CODE X OF ASME WELD IDENTIFICATION NO.

CATEGORY NATURE OF SCAN SECTION III SAFETY B ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-203-1-5B CG Main Steam Pipe to Re- 4 Restraint 25X RT Turbine building vent stack radiation monitor C2.1 straint Insert Braces 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 Main Steam Pipe to Sweep- 1 Lug 5X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 o-let RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM; DBB-204-1-5B CG Main Steam Pipe to Re- 4 Restraint 25X RT Turbine building vent stack radiation monitor C2. 1 straint Insert Braces 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 X OF ASME WELD CATEGORY NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. A ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT VRR-B31-3-10-M 1 BJ Recirc. Longitudinal Branch Line RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Seam 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 Recirc. Longitudinal Branch Line 5X RT/PT Affects RCPB; veld cannot be isolated. However B4.5 Seam 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 RT/PT Affects RCPB; veld cannot be isolated. However B4.5 Seam 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 Recirc. Longitudinal Branch Line 10X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Seam RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DBA-201-2-FW34 . BJ Reactor . Pipe to Elbow Rigid 35X RT/PT Leak detection systems detect weld leakage, re-B4.5 Water Restraint sulting in either manual or automatic isolati'on Cleanup 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.

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CODE X OF ASME WELD CATEGORY NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. 4 ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-203-1-3A CG Main Steam Pipe to Re- 4 Restraint 13X RT Turbine building vent stack radiation monitor C2.1 straint Insert Braces 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 CG Main Steam Pipe to Re- 4 Restraint 13X RT Turbine building vent stack radiation monitor C2.1 straint Insert Braces 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.

DLA-202-I-PW19 BJ Feedwater Pipe to Elbow Branch Line 7X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 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 Z OF ASHE WELD CATEGORY NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. A ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT HBB-211-2-3-D CF Residual Pipe to Hanger 10X RT During plant power operation, weld not C2.1 Heat Elbow Weld pressurized. During normal system operation, Removal (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 Lugs RT During normal plant power operation, welds are not C2. 1 Heat Elbow under pressure. During normal system operation, Removal 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.

1 DBB-214-1-9A CF High Pipe to Elbow - Lugs 5X RT Leak detection systems detect weld leakage, re-

'E C2. 1 Pressure sulting in either manual or automatic isolation Coolant of leak. These lines are not,required for nor-In)ection . mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, l~

main condenser).

t Residual Elbow to Branch Line DCA-208-1-FW11 BJ 5X RT/PT During plant power operation, weld not 84.5 Heat Valve pressurized. During normal system operation, Removal (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 Feedwater Pipe to Valve Welded Whip - 60X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Restraint RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

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CODE X OF ASME WELD IDENTIFICATION NO.

CATEGORY NATURE OF SCAN SECTION III SAFETY A ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-207-1-FW3 CF Residual Pipe to Branch Line 10X RT During normal plant power operation, welds are not C2.1 Heat Valve under pressure. During normal system operation, Removal 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 Residual Pipe to Branch Line 5X RT During normal plant power operation, wclds are not C2.1 Heat Valve under pressure. During normal system operation, Removal 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 Feedwater Pipe to Tee Branch Line RT Leak detection systems detect weld leakage, re-C2.1 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 Core spray Pipe to Pipe Branch Line RT During normal plant power operation, weld is not C2.1 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.

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CODE X OF ASME WELD IDENTIFICATION NO.

CATEGORY ITEM NO.

NATURE OF SCAN SECTION III SAFETY A SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-207-I-FWI CF Residual Pipe to Branch Line 15X RT During normal plant power operation, welds are not C2.1 Heat Valve under pressure. During normal system operation, Removal 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 Branch Line 5X RT During normal operation of the CRD system, sig-C2.1 Rod Drive Reducer nificant leakage will be detected by area radiation monitors. Leakage can be manually isolated.

DBB-214-I-IOB CG High Pipe to Flange Branch Line 15X RT Leak detection systems detect weld leakage, re-C2.1 Pressure sulting in either manual or automatic isolation Coolant of leak. These lines are not required for nor-Infection mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, ~

main condenser).

DBB<<221-3-FW3 CF Reactor Pipe to Valve 1)Branch Line 18X RT Leak detection systems detect veld leakage, re<<

C2.1 Core 2)Geometry suiting in either manual or automatic isolation Isolation of leak. These lines are not required for nor-Cooling mal safe shutdowns and alternate shutdown methods are availablc (e.g., feedwater, RCIC, main condenser).

HBB<<211-2-11B CF Residual Pipe to Plate Ad)scent 5X RT During plant power operation, weld not C2.1 Heat Tee to Weld pressurized. During normal system operation, Removal (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.

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CODE X OF ASME WELD 'ATEGORY NATURE OF SCAN SECTION IIX SAFETY IDENTIFICATION NO.' ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-221-3-FW2 CF Reactor Tee to Valve 1)Branch Line 10X RT Leak detection systems detect weld leakage, re-C2.1 Core 2) Geometry sulting in either manual or automatic isolation Isolation of leak. These lines are not required for nor-Cooling mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).

CG High Pipe to Valve Pipe Support SX RT Leak detection systems detect weld leakage, re-C2. 1 Pressure sulting in either manual or automatic isolation Coolant of leak. These lines are not required for nor-In)ection mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).

I GBB-205-2-1A CF Residual Reducer to Welded Hanger 25X RT During normal plant power operation, welds are not f

C2.1 Hest Reducer under pressure. During normal system operation, Removal 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.

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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.

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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 CODE X OF ASME WELD IDENTIFICATION NO.

CATEGORY 4 ITEM NO. SYSTEM . CONFIGURATION NATURE OF SCAN SECTION III SAFETY OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT VRR-B31-3-FWA10 BJ Recirc. Sweep-o-let Part Geometry 25X RT/PT Affects RCPB; veld cannot be isolated. However B4.5 to Riser Pipe RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdovn with leakage gieater than 5 GPM.

VRR-B31-3-FWA11 BJ Recirc. Sweep-o-let Part Geometry 25X RT/PT Affects RCPB; veld cannot be isolated. However B4.5 to Riser Pipe RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

VRR-B31-3-FWA13 BJ Recirc. Sweep-o-let Part Geometry 25X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 to Riser Pipe 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 to Riser Pipe Part Geometry '5X 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 Recite. Sweep-o-let Part Geometry 25X RT/PT Affects RCPB; veld cannot be isolated. However B4.5 to Riser Pipe RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

VRR-B31%-FWB11 BJ Recirc. Svcep-o-let Part Geometry 25X RT/PT Affects RCPB; veld cannot be isolated. However B4.5 to Riser Pipe RCPB leek detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

VRR-B31-4-FWB13 BJ Recirc. Sveep-o-let Part Geometry 25X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 to Riser Pipe RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

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CODE X OF ASHE MELD IDENTIFICATION NO.

CATEGORY NATURE OP SCAN SECTION III SAFETY

& ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IHPACT VRR-B31-4-FWB14 BJ Recirc. Sweep-o-let Part Geometry 25X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 to Riser Pipe RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

VRR-B31-3-FWA33 BJ Rccirc. Tce to Part Geometry 100X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Valve 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 Part Geometry 100X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Valve RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPH.

VRR-B31-3-PWA24 BJ Recirc. Valve F032 A Part Geometry 100X RT/PT Affects RCPB; weld cannot be isolated. However B4 ~ 5 to Pipe RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

VRR-B31%-PWB24 BJ Recirc. Valve F0328 Part Geometry 100X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 to Pipe RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

VRR-B31-4-FWB23 BJ Recirc. Elbow to Part Geometry 25X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Valve RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPH.

VRR-B31-3-3-P BJ Recirc. Pipe to Part Geometry 15X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Cross RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

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CODE Z OF ASME WELD IDENTIFICATION NO.

CATEGORY NATURE OF SCAN SECTION III SAFETY

& ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DCA-207-1-FW-3 BJ Core Spray Valve F006A Part Geometry 100X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 to Valve F007A RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DCA-207-2-FW3 BJ Core Spray Valve F006B Part Geometry 100X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 to Valve F007B RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DLA-204-I-FW5 BJ Feedwater Pipe to Part Geometry 35X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Safe End RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DLA-204-1-FW21 BJ Feedwater Pipe to Part Geometry 35X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Safe End 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 Part Geometry 35X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Safe End RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DLA-202-1-FW10 BJ Feedwater Pipe to Pert Geometry 35X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Safe End RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

r DBA 216 1 FWC14 NA Hain Steam Elbow to Part Geometry 30X RT/PT Affects reactor coolant pressure boundary (RCPB);

(Augmented) Branch 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.

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CODE X OF ASME HELD CATEGORY NATURE OF SCAN 'SECTION III SAFETY IDENTIFICATION NO. A ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBA-214-I-FHA14 NA Main Steam Elbow to Part Geometry 30X RT/PT Affects reactor coolant preseure boundary *(RCPB);

(Augmented) Branch 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 Part Geometry 30X RT/PT Affects reactor coolant pressure boundary (RCPB);

(Augmented) Tee 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 RT/PT Affects RCPB; weld cannot be isolated. However B4.5 RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DBB-215-I~FHIO CF Residual Elbow to Part Geometry 10X RT/PT Leak detection systems detect weld leakage, re-C2.1 Heat Valve sulting in either manual or automatic isolation Removal 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 Part Geometry 10X RT/PT Leak detection systems detect weld leakage, re-C2.1 Heat Valve sulting in either manual or automatic isolation Removal of leak. These lines are not required for nor-mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC.

main condenser).

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CODE X OP ASME MELD IDENTIFICATION NO.

CATEGORY NATURE OF SCAN SECTION III SAFETY

& ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT GBB-212-2-FW14 CF Residual Valve F007B Part.'eometry 8X RT Containment boundary weld that is not normally C2.1 Heat to Flued Head pressurized during plant power operation. Dur-Removal 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 Residual Valve F007A Part Geometry 33X RT Containment boundary weld that is not normally C2.1 Heat to Plued Head pressurized during plant power operation. Dur-Removal 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 Residuai Reducer to Part Geometry 10X RT During normal plant power operation, welds are not C2.1 Heat Nozzle under pressure. During normal system operation, Removal 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.

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CODE X OF ASME WEM IDENTIFICATION NO.

CATEGORY ITEM NO.

NATURE OF SCAN SECTION III SAFETY A SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT GBB-206-1-FW2 CF Residual Tee to Part Geometry 33X RT During normal plant power operation, welds are not C2.1 Heat Valve under pressure. During normal system operation, Removal 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 CF Residual Reducer to Part Geometry 15X RT During normal plant power operation, welds are not C2.1 Heat Nozzle under pressure. During normal system operation, Removal 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.

GBB-205-1-FW1 CF Residual Valve to Part Geometry 65X RT During normal plant power operation, welds are not C2.1 Heat Reducer under pressure. During normal system operation, Removal 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 RT/PT Affects reactor coolant pressure boundary (RCPB);

B4.5 Valve 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.

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CODE X OF ASME WELD IDENTIFICATION NO.

CATEGORY A ITFM NO.

NATURE OF SCAN SECTION III SAFETY SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DCA-207-I-FW5 BJ Core Spray Reducer Part Geometry 20X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 to Nozzle RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DCA-207-2-FW10 BJ Core Spray Reducer Pert Geometry 15X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 to Nozzle RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DCA-202-2-FW1 BJ Reactor Tee to Part Geometry 60X RT/PT During normal plant power operation, welds are not B4.5 Water Weld-o-let under pressure. During normal system operation, Cleanup 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 Core Spray Flued Head to Part Gcomctry 50X RT/PT Affects reactor coolant pressure boundary (RCPB);

B4.5 Valve 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 Core Spray Flued Heed to Part Geometry 50X RT/PT Affects reactor coolant pressure boundary (RCPB);

B4.5 Valve 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.

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CODE X OF ASME WELD IDENTIFICATION NO.

CATEGORY ITEM NO.

NATURE OF SCAN SECTION III SAFETY, A SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBA-201-1-FW10 BJ Reactor Flued Head to Part Geometry 20X RT/PT Affects reactor coolant pressure boundary (RCPB);

B4.5 Water Valve however, inside containment isolation valve per-Cleanup 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 High Flued Head to Part Geometry 18X RT/PT Affects reactor coolant pressure boundary (RCPB);

B4.5 Pressure Valve however, inside containment isolation valve per-Coolant forms RCPB isolation function. Any significant Infection 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 BJ Residual Elbow Part Geometry 10X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Heat to Valve RCPB leak detection systems detect leakage.

Removal Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DCA-211-3.-FW12 BJ Residual Elbow Part Geometry 8X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Heat to Flange RCPB leak detection systems detect leakage.

Removal Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

GBB-201-4-FW1 CG Core Spray Pipe to Valve Part-Geometry 8X RT During normal plant power operation, weld is not C2.1 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.

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CODE X OF ASME WELD CATEGORY NATURE OF SCAN ~ SECTION III SAFETY IDENTIFICATION NO. & ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT GBB-204-3-FW15 CF Residual Pipe to Part Geometry 10X RT During normal plant power operation, welds are not C2.1 Heat Flange under pressure. During normal system operation, Removal 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 High Pipe to Part Geometry 8X RT Leak detection systems detect weld leakage, re-C2.1 Pressure Flange sulting in either manual or automatic isolation Coolant of leak. These lines are not required for nor-Infection mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).

EBB-202-1TFW5 CG High Pipe to Part Geometry 8X RT Leak detection systems detect weld leakage, re-C2.1 Pressure Plange sulting in either manual or automatic isolation Coolant of leak. These lines are not required for nor-In>ection mal safe shutdowns and alternate shutdown methods are available (e.g.. feedwater, RCIC, main condenser).

DBB-222-1-3B NA Reactor Tee to Part Geometry IOX RT Leak detection systems detect weld leakage, re-Water Flange sulting in either manual or automatic isolation Cleanup of leak. These lines are not required for nor-(Augmented) mal safe shutdowns and alternate shutdown methods are available (e.g., feedwater, RCIC, main condenser).

DCA-211-3-2A BJ Residual Pipe Part Geometry 20X RT/PT Affects RCPB; weld cannot be isolated. However B4.5 Heat to Flange RCPB leak detection systems detect leakage.

Removal Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

-i Page 11 of 16 Revision 0, 10/83

CODE Z OF ASME HELD IDENTIFICATION NO.

CATEGORY A ITEM NO.

NATURE OF SCAN SECTION III SAFETY SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT HBB-218-2-FW5 CG Containment Pipe Part Geometry 13X RT During normal plant power operation, weld is not C2.1 Atmosphere to Valve pressurized. During normal system operation, Control 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 Reactor Pipe Part Geometry 13Z RT Leak detection system detects significant leak-C2.1 Core to Valve age; containment isolation valves perform weld Isolation isolation function., HPCI performs backup func-Cooling tion for RPV water addition for safe shutdown.

HBB-201-1-FW10 CG Reactor Part Geometry 10X Leak detection system detects significant Ieak-

'ipe RT C2.1 Core to Valve age; containment isolation valves perform weld Isolation isolation function. HPCI performs backup func-Cooling tion for RPV water addition for safe shutdown.

~(

GBB-205-2-FW3 CF Residual Pipe to Part Geometry 10X RT During normal plant power dperation, welds are not C2.1 Heat Valve under pressure. During normal system operation>

Removal 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.

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CODE X OF ASME WELD CATEGORY NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. A ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT HBB-211-2-FW14 CF Residual Valve to Part Geometry 10X RT During normal plant power operation, welds are'ot C2.1 Heat Elbow under pressure. During normal system operation, Removal 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 Reactor Flued Head to Part Geometry 10X RT Containment boundary weld that is not normally C1.2 Core Valve pressurized during plant operation. During nor-Isolation mal system operation, leak detection systems Cooling 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 CG C2.1 (Pump) 'ozzle to Core Spray Elbow 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.

D 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-3614-6 CF Residual Elbow to Part Geometry . 30X RT During normal plant power operation, weld is not B C2.1 Heat Nozzle pressuilzed. During normal system operation, C Removal weld is under a maximum pressure of 460 psig.

D (Pump) 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.

-Y Page 13 of 16

@pe~ Revision 0, 10/83

CODE X OF ASME HELD CATEGORY NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. 6 ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT 2P-202-A-361-1-5 CF Residual Support Shell Part Geometry 10X RT During normal plant power operation,-weld is not B C2.1 Heat to Head Hub pressurized. During normal system operation, C Removal weld is under a maximum pressure of 460 psig.

D (Pump) 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 CP Residual Nozzle to Part Geometry 10X RT During normal plant power operation, weld is not B C2. 1 Heat Vertical pressurized. During normal system operation, C Removal Support Shell weld is under a maximum pressure of 460 psig.

D (Pump) Leak detection system detects significant leak-age. Significant leakage of weld can affect one RHR loop. Plant can be safely cooled down

'art by unaffected RHR loop.

2P-202-AT361-3-13 CF Residual Flange to Geometry 10X RT During normal plant power operation. veld is not B C2.1 Heat Nozzle pressurized. During normal system operation, C Removal weld is under a maximum pressure of 460 psig.

D. (Pump) 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 CF Residual Elbow to Part Geometry; 10Z During normal plant power operation, veld is not B C2.1 Heat Vertical pressurized. During normal system operation, C Removal Support Shell veld is under a maximum pressure of 460 psig.

D (Pump) 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

CODE X OP ASME WELD IDENTIFICATION NO.

CATEGORY NATURE OF SCAN SECTION III SAFETY 4 ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT 2P-206-A 361-5-13 CG Core Spray Inlet Nozzle to Part Geometry 10X RT During normal plant power operation, veld is not B C2. 1 (Pump) Vertical pressurized. During normal system operation, C Support Shell veld is under a maximum pressure of 475 psig.

D 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 Core Spray Elbow to Part Geometry 10X RT During normal plant pover operation, veld is not B C2.1 (Pump) Vertical pressurized. During normal system operation, C Support Shell veld is under a maximum pressure of 475 psig.

D 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 Core Spray Valve to Part Geometry 25Z RT During normal plant pover operation, weld is not C2.1 Pipe 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.

CG Control Rod Pipe to Part Geometry 5X RT During normal operation of the CRD system, C2.1 Drive Elbow significant leakage vill be detected by area radiation monitors. Leakage can be manually isolated.

Page 15 of 16 Revision 0, 10/83

CODE Z OF ASME HEID CATEGORY NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. A ITEM NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT GBB-204-I-FN7 CF Residual Valve to Part Geometry 5Z RT During normal plant power operation, welds are not C2.1 Heat Pipe under pressure. During normal system operation, Removal 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

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RELIEF RE HEST Oil WELD CODE CATEGORY X OF SCAN ASME IDENTIFICATION NUHBER AND ITEM NUMBER SYSTEM CONFIGURATION NATURE OF OBSTRUCTION OBSTRUCTED SECTION III APPROXIMATED EXAMINATION SAFETY IMPACT 2E-205-A-R CA RHR Shell to Head Welded 5X PT, UT, RT During normal plant power operation, weld is C1 ~ 1 Attachment 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 CB RHR Shell to Nozzle Ad)scent 20X PT, UT, RT C1.2 Weld 2E-205-A-AC CA RHR Shell to Flange Outlet 20X PT, UT, RT C1.1 Nozzle

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2E-205-B-R CA RHR Shell to Head Welded PT, UT, RT C1.1 Attachment 2E-205-B-A CB RHR Sheil to Nozzle Ad)scent 20X PT, UT, RT C1.2 Weld 2E-205-B-AC CA RHR Shell to Flange Outlet 20X PT, UT, RT C1.1 Nozzle 2E-205-A-P CB RHR Shell to Nozzle Adjacent 5X PT, UT> RT C1. 2 Weld-o-let 2E-205-B-P CB RHR Shell to Nozzle Ad)scent PT, UT, RT C1.2 Weld-o-let mts/chg259c:pas 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

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"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 % OF ASME WELD IDENTIFICATION NO.

CATEGORY 5 ITEM NO, SYSTEM NATURE OF SCAN SECTION III SAFETY CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-205-2-3 J CG Main Steam Pipe to Re- Wrapper Plate 100% ~i RT Turbine Building vent Stack radiation monitor C2.1 straint Insert 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 Reactor Pipe to Valve Wrapper Plate 100% RT Leak detection systems detect weld leakage, re-C2.1 Core sulting in either manual or automatic isolation Isolation of leak. These lines are not required for nor-Cooling'] mal safe shutdowns and alternate shutdown, methods are available (e.g., feedwater, RCIC, main condenser).

Page 2 of 2 Revision 0, 10/83

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RELIEF REQUEST I/9 CODE % OF ASME WELD CATEGORY-5 ITEM NO.

NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT VNB-B21-3-20-F BJ Main Steam Pipe to Sweep- 1 Lug 3% RT/PT Affects RCPB; weld cannot be isolated. However B4.5 o-let RCPB leak detection systems detect leakage.

Plant Tech. Specs. require plant shutdown with leakage greater than 5 GPM.

DBB-204-1-5A CG Main Steam Pipe to Re- 4 Restraint- 25% RT Turbine building vent stack radiation monitor C2.1 straint Insert Braces 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 Main Steam Pipe to Re- 4 Restraint 25% RT Turbine building vent stack radiation monitor C2.1 straint Insert Braces 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 % OF .ASME WELD CATEGORY 5 ITEM NO.

NATURE OF SCAN SECTION III SAFETY IDENTIFICATION NO. SYSTEM CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION IMPACT DBB-202-1-5A CG Main Steam Pipe to Re- '

Restraint 25% RT Turbine building vent stack radiation monitor C2.1 straint Insert Braces 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 Main Steam Pipe to Re- 4 Restraint 25% RT Turbine building vent stack radiation monitor C2. 1 straint Insert Braces 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

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RELIEF REQUEST 89 (Continued)

CODE % OF ASME WELD IDENTIFICATION NO.

ML18040B033

Text

SUBJECT:

Dear Mr. Schwencer:

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