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Rev 0 to Re Ginna Nuclear Power Plant 1996 ISI Program Rept.
	ML17264A683
Person / Time
Site:	Ginna
Issue date:	09/13/1996
From:	; ROCHESTER GAS & ELECTRIC CORP.
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ML17264A682	List: ML17264A681; ML17264A683;
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ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE, ROCHESTER, NY 14649 NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT FOR THE THIRD INTERVAL (1990-1999)SECOND PERIOD, FOURTH OUTAGE (1996)AT R.E.GINNA NUCLEAR POWER PLANT REVISION 0 SEPTEMBER 13, 1996 9610100113 960930 ,'DR ADOCK 05000244 Q PDR

R.E.GINNA NUCLEAR POWER PLANT NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT THIRD INTERVAL (1990-1999)SECOND PERIOD, FOURTH OUTAGE (1996)OWNERS DATA SHEET Date: 13 September, 1996 Owner: Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 Plant Location and Unit No.:~~R.E.Ginna Nuclear Power Plant Unit One 1503 Lake Road Ontario, New York 14519 Commercial 0 eratin Date: Suly 1970 A licable Code: ASME Section XI, 1986 Edition, No Addenda I

R.E.GINNA NUCLEAR POWER PLANT Inserv ice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)TABLE OF CONTENTS Introduction and Synopsis Summary of Work Accomplished Class 1 Components Class 2 Components Class 3 Components High Energy Components Design Break Weld Examinations Consequential Break Weld Examinations Component Support Examinations Steam Generators System Pressure Testing Hydrostatic Testing Leakage Testing Section XI, Service Induced Rejectable Components

-Expanded Examinations Snubbers Visual Examinations Functional Testing Seismic Support Program Erosion/Corrosion (Minwall)Program Attachment I Attachment II Attachment III ISI Program Examination Summary Repair, Replacement

&, Modification Program Summary Erosion/Corrosion (Minwall)Program Summary

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)INTRODUCTION AND SYNOPSIS: Inservice Inspection (ISI)activities for 1996 were performed on components within Class 1, 2, 3, High Energy Piping, Steam Generator Tubes, Seismic Supports and Snubbers.ISI examinations were concluded on July 2, 1996.Examination methods included Visual (VT), Liquid Penetrant (PT), Magnetic Particle (MT), Ultrasonic (UT), Radiographic (RT), and Eddy Current (ET).Functional Testing (FT)and System Pressure Tests were also performed.

Erosion/Corrosion examinations were also performed during this time.Personnel involved included RGAE Laboratory and Inspection Services, Sonic Systems Incorporated, Master Lee Services Corporation, ABB Combustion Engineering Corporation, Ginna Station Quality Control and the Ginna Station Results/Test Group.Additional Support Personnel included individuals from the followirig departments:

Ginna Station Insulators, Maintenance, Electricians, Pipe Fitters, Health Physics, Turbine Maintenance, RG8'cE General Maintenance and the Mechanical Engineering Group of the Nuclear Engineering Services Department.

ASME SECTION XI

SUMMARY

OF WORK ACCOMPLISHED:

Upon conclusion of the 1996 Outage, 61.7%of ASME Section XI Code required examinations for the Third Interval ISI Program has been completed.

A detailed component summary of all outage ISI activities with their associated results can be found within"Attachment I".CLASS 1 COMPONENTS:

A total of 46 ASME, Augmented or Owner Elected components were examined.The examinations for these components consisted of 19 VT's, 18 PT's, 8 MT's, 17 UT's and 4 RT's.A total of 66 examinations were performed on Class 1 Components.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)CLASS 1 COMPONENTS:

Cont.Class 1 examinations were performed on the following items/systems and/or plant lines/component:

Item/S stem Descri tion Plant Line/Com onent CVCS-Charging System: 2C-CHS-2502 2A-CHS-2501 2-CHS-2501 2H-CHS-2501 CVCS-Letdown System: High Pressure Safety Injection System: Pressurizer System: Reactor Coolant Pump A: Reactor Coolant Pump B: Reactor Coolant System: 2B-CH4-2501 10A-SI2-2501-B 10-RC8-2501 PRCOl A (Studs)PRC01B (Bolts)29-RC-2501-A 2A-RCO-2501-A 2B-RCO-2501-B 2C-RC0-2501-B Residual Heat Removal System: 10A-AC7-2501-A 10A-AC 7-2501-B Steam Generator A Steam Generator B EMS01A (Items)EMS01B (Items)

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)CLASS 2 COMPONENTS:

A total of 109 ASME or Owner Elected Components were examined.The examinations for these components consisted of 42 VT's, 26 PT's, 35 MT's, 11 RT's, and 28 UT's for a total of 142 examinations.

Class 2 examinations were performed on the following items/systems and/or plant lines/components:

Item/S stem Descri tion Plant Line/Com onent CVCS-Charging System: 2D-CH5-2501 8A-CH-2502 8B-CH-2502 8C-CH-2502 Feedwater System: 18A-FW-900-1A 18B-FW-900-1B 14A-FW-900-1A 14B-FW-900-1B High Pressure Safety Injection System: 2T-SI-2501 2U-SI-2501 3A-SI-1501 3C-SI-1501 4D-SI-1501 4E-SI-1501 8E-SI-301 8G-SI-301 4-SI-301 4A-SI-301 Mainsteam System: 30A-MS-600-1A 30B-MS-600-1B Residual Heat Removal System: 6C-AC-601 6K-AC-151

R.E.GINNA NUCLEAR PO%ER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)CLASS 2 COMPONENTS:

Cont.Item/S stem Descri tion Plant Line/Com onent Steam Generator A EMS01A (Items)Steam Generator B EMS01B (Items)Service Water System: 6G-SW-125 8B-SW-125 8F-SW-125 8 J-SW-125 8N-SW-125 CLASS 3 COMPONENTS:

A total of 12 ASME or Owner Elected Components were examined utilizing the VT visual examination method.Examinations were performed on the following items/systems and/or plant lines/components:

Item/S stem Descri tion Plant Line~IC Auxiliary Cooling System: Auxiliary Feedwater System: EACO I B (Integral Attachments

&Supports)3A-FW7-900-1A 3A-FW7-900-1B 3J-FW7-900-1 3K-FW7-900-1 Diesel Generator System: 5C-DG-B R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)HIGH ENERGY COMPONENTS:

Five (5)Augmented or Owner Elected items associated with the High Energy Program were examined during the 1996 Outage.The examinations for these items consisted of 3 VT's, 3 MT's and 1 UT for a total of 7 examinations.

High Energy component examinations were performed on the following items/systems and/or plant lines: Item/S stem Descri tion , Plant Line Feedwater System: Mainsteam System: 14A-FW-900-1 24B-MS-600-1A STEAM GENERATOR TUBING: Eddy Current ASME and Owner Elected Examinations were performed on tubes in the"A" and'B" Steam Generators.

The following Eddy Current examinations were performed.

1.Preservice (Baseline) examinations.

2.Open Generator Tubes, Bobbin Coil, 100%Full Length.3.Open Generator Tubes, Peripheral Tubes.Steam Generator Eddy Current Examination details are documented in the Rochester Gas 8'c Electric 1996 Steam Generator Eddy Current Final Report.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)SYSTEM PRESSURE TESTS: Leaka e Testin A total of five (5)ASME Leakage Examinations were performed.

Leakage tests performed included one (1)Class 1, Reactor Coolant System (PT-7)examination and four(4)Class 2 or 3 examinations.

ASME Section XI Re uired Com onents Service Induced Re ectable-Ex anded Examinations:

There were no ASME Section XI required components that were classified as"Service Induced Rejectable" that needed Code expanded examinations.

SNUBBER PROGRAM: Visual Examinations:

A total of 149 Snubber component supports were examined.These Augmented examinations were performed to satisfy Ginna Station Snubber Program commitment.

'nubber visual examinations were performed on the following items/systems and/or plant lines: Item/S stem Descri tion Plant Line Steam Generator"A": Steam Generator"B": Auxiliary Feedwater Pump Discharge-Intermediate Building Lines: 3K-FW7-900-1 3A-FW7-900-1A 3 J-FW7-900-1 3B-FW-900-1B 3A-FW7-900-1B 3A-FW-900-1A'B-FW

-900-1A l, i "R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)SNUBBER PROGRAM: Cont.Visual Examinations:

Item/S stem Descri tion Plant Line Turbine Driven Auxiliary Feedwater Pump Suction Line: Steam Generator B, Blowdown Line: Auxiliary Cooling Lines: 4A-CD-150-1C 2C-MS-600-1B 4S-AC6-152 3E-AC6-152 4T-AC6-152 2-IN.Letdown Lines: 2A-CH4-2501 2H-CH-601 2A-CH4-151 2-IN.Charging Line: 2G-CH5-2502 2-IN.Alternate Charging Line: 2F-CHS-2501 CVCS Relief Line: 2E-CH-601 Reactor Coolant Pump"1B" Seal Water Line: 2H-CHS-2501 Reactor Coolant Pump"1A" Seal Water Line: 2P-CH-2501 Feedwater Loop"A"&"B" Lines: 14A-FW-900-1A 14A-FW-900-1 14B-FW-900-1B 14B-FW-900-1

~~

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)SNUBBER PROGRAM: Cont.Visual Examinations:

Item/S stem Descri tion Plant Line Main Steam Lines: 30A-MS-600-1A 30B-MS-600-1B 6A-MS-600-1A 6B-MS-600-1A 6B-MS-600-1B 6A-MS-600-1 6B-MS-600-1 Safety Injection Lines: 10A-SI2-2501-A 10A-SI2-2501-B 10-SI-151 8J-SI-151 4-SI-301 Residual Heat Removal Lines: 10-AC-601 10A-AC7-2501-B 10A-AC7-2501-A 10D-AC-601 10E-AC-601 10G-AC-601 10GG-AC-151 8B-AC-601 6-AC-601 6D-AC-601 6K-AC-151 Service Water Lines: 10B-SWO-125-1 8A-SWO-125-1 8L-SW-125 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)SNUBBER PROGRAM: Cont.Visual Examinations:

Item/S stem Descri tion Plant Line Standby Auxiliary Feedwater Lines: 3C-FW-902S-1A 3C-FW-902S-1B Pressurizer Relief Lines: 6AP-RC-602 6BP-RC-602 3BP-RC-602 3B-RC8-2501 3A-RC8-2501 Seal, Water Return Lines: 2X-CH-2501 Functional Testin: A total of twenty-one (21)snubbers were Functionally Tested (FT)during the 1996 outage.From the twenty (20)snubbers that were originally scheduled, fourteen (1 4)were mechanical snubbers and six (6)were hydraulic snubbers.Due to snubber failure, an expansion was performed that consisted of one (1)additional snubber that was Functionally Tested.Snubber Functional Tests (FT)were performed on the following supports.Mechanical Snubbers.CVU-131 FWU-18 FWU-23 RHU-109 MSU-58 MSU-57 MSU-18(South)

MSU-19(South)

MSU-72 H draulic Snubbers: FWU-42 M SU-19(North).AFU-227 RHU-123 MSU-22 AFU-224 PS-6 N616 AFU-208 SGA-8 Note: (*)=Expanded Snubber Functional Test AFU-226(*)

AFU-229 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)SEISMIC SUPPORT PROGRAM: A total of seven (7)Augmented or Owner Elected Seismic Supports were inspected utilizing the visual (VT)examination technique.

Seismic Support examinations were performed on the following items/systems and/or plant lines: Item/S stem Descri tion CVCS-Letdown System: High Pressure Safety Injection:

Mainsteam System: Plant Line 3-RC-601 2H-SI-902 6B-MS-600-1A 6C-MS-600-1B 6D-MS-600-1B Blowdown System: 2E-BD-600-1A 2E-BD-600-1B EROSION/CORROSION MINWALL PROGRAM: A total of 98 items were examined during the 1996 Outage.The breakdown of this total is as follows: Com onent T e Pipes Elbows Reducers Tees TAHITI 45 39 12 2 10 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)EROSION/CORROSION MINWALL PROGRAM: Cont.Component thickness measurements were performed on the following systems: DWG.NO.SYSTEM M-12A M-12B M-15B M-19 M-21 M-22 M-75 M-81 M-84 M-85 M-88D M-91 M-92 M-99 M-100 M-103 MSR 1A&, 1B 2ND PASS TO SA HEATER AND CONDENSER MSR 2A&, 2B 2ND PASS TO 5B HEATER AND CONDENSER MSR 1B 4TH PASS TO SA HEATER 1A, 2A,&3A L.P.HEATER DRAINS TO CONDENSER STEAM EXT.TO PRESEP.TANK B&4B L.P.HEATER STEAM EXT.TO PRESEP.TANK A Ec 4A L.P.HEATER STEAM EXTRACTION TO 5A 8c 5B HEATERS FEEDWATER DISCHARGE (TURBINE BUILDING)FEEDWATER TO S/G 1A (CONTAINMENT)

FEEDWATER TO S/G.1B (CONTAINMENT)

S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)FEEDWATER CLEANUP (CV-19)MAIN FEEDWATER PUMP RECIRCULATION GLAND STEAM CONDENSER TO TURB.GEN.&GOV.MAIN GLAND STEAM TO TURB.GEN.&GOV.ENDS F.W.HTR.DRAIN SYS.FROM H.D PUMPS TO H.T.TANK R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)The statements made in this report and attachments are correct and the examinations and corrective measures taken conform to the Rules of the ASME Code,Section XI.prepared By;~.//3/Pd Frank A.Klepacki Date ISI Engineer Approved y: Michael J.Sa orito Date Manager, Laboratory and Inspection Services, Technical Performance and Field Inspections

>/~/~<Certificate of Inservice Ins ection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspections and the State or Province of New York and employed by The Hartford Steam Boiler Ins ection and Insurance Com an have inspected and/or verified the components described within tl~s report and associated Attachments during the stated reporting time frame, and state to the best of my knowledge and belief, the Owner has performed examination and corrective measures described in this Report in accordance with the requirements of the ASME Code,Section XI.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Reviewed By:+~~~i 8 Wl~~s/za+es ANII's Signature Date 12 FORM NIS-1 OWNER'S REPORT FOR INSERVZCE INSPECTIONS As re uired bv the Provisions of the ASME Code Rules l.Owner Rochester Gas 6 Electric Cor.89 East Ave.Rochester N.Y.14649 (Nante and Address of Quitter)2.Plant R.E.Ginna Nuclear Power Plant 15 03 Lake Road Ontario NY 1 4 5 1 9 3.Plant Unit 5.Conunercial Service Date Jul 1970 7.Components Inspected (Name and Address of Plant)4.(hvner Certificate of Authorization (if required)6.National Board Number for Unit N/A N/A Component or Appurtenance hfanufacturer or Installer Manufacturer or Installer Serial No.State or Province No.National Board No.(*)SEE"ATTACHMENT I" FOR APPLICABLE INFORMATION Note: Supplemental siteets in form of lists, sketches, orArawings may be used, provided(1) size is 8-1/2 in.x I I in., (2)inforntatlon in items I tluou8It 6 on this report is included on each sheet, and (3)each sheet is numbered and thc number of sheets is recorded at thc top of this form.(12/86)This form (E0029)may bc obtained from the Order D~, ASh IE, 22 Law Drive, Box 2300, Fairfield, NJ07007-2300 0

FORM NIS-1 (Back)8.Exainination Dates 11/27/95 to 7/02/96 9.hlspection Interval from 1990 to 1999 10.ApplicableEditionsofScctionXI 1986 Addenda No 11.Abstract of Examinations, Include a list of examinations and a statement concerning status of work required for current interval.(*)12.Abstract of Conditions Noted.(*)13.Abstract of Corrective Measures Recoiiunended and Taken.(*)XI.IVc ccttify that statements made in this report arc correct and the examinations and corrective measures taken conform to the rules of the ASME Code, Section CertiTicate of Authorization No.(if applicable)

N/A Expiration Date N/A Date 13 Se member 19 96 Signed Rochester GaB A Flectric Cn mtion GNtter ISI Engineer CERTIFICATE OF INSERVICE INSPECTION I, Ibe undesigned, holding a vsgd conunisdon issn d by tbc Na lion st Board of Boiler and Presto o Vessel Inspcdora and the State or Province of~Zgdt andonptoy dby a'.c~of a have inspected the components described in this Ohhltei's Report during the period df a M to and state that to thc best of my hlowledge and belief, thc Ohvncr llas perfomled examinations and taken corrective measures described in this Ohvnei's Report in accordance with the inspection plan and as required by the ASME Code, Section Xl.By signing this certificate ncithcr thc Inspector nor his employer makes any warranty, expressed or implied, concenling the examinations and corrective measures described in this Ghvner's Rcport.Furthemiore, neither the hlspector nor his employer shall bc liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

~cz 8.W Inspector's Signature 19 94 Conlillissions National Board, State, Province, and Endorsements

(*)SEE"ATTACHMENT I" FOR APPLICABLE INFORMATION 2

R.E.G1NNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 5970 S.National Board Number for Unit N/A ATTACHMENT I A.CLASS 1 COMPONENTS:

Al.STEAM GENERATOR A DRAWINGS: A-5 Summary Number Etiam Categ Item Number Component Component Type 005700 B-B B2.40 LHTSW-AR LOWER HEAD-TO-TUBE SHEET WD ASME UT 96-UT: PERFORMED BY B&W, REF'EPORT ()7705-1-22:-ACCEPTABLE.

005900 B-D B3.140 INIR-AR INLET NOZZLE INSIDE RADIUS SECTION OE UT 96-UT;NO RECORDABLE INDICATIONS

-ACCEPT.>90%COVERAGE.005990 B-F B5.70 NSE-1R SAFE END-TO-NOZZLE (INLET)ASME PT UT 96-PT&UTr'O RECORDABLE INDICATIONS

-ACCEPTABLE.

PT&UT PERFORMED BY B&W UNDER REPORT ()7705-1-55.

006000 B-J B9.11 PL-FW-I-ASW-R ELBOW-TO-SAFE END OE PT RT 96-PT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

006100 B-D B3.140 ONIR-AR OUTLET NOZZLE INSIDE RADIUS SECTION UT 96-UT: NO RECORDABLE INDICATIONS

-ACCEPTABLE.

NOTE: "COMPONENT TYPE",ZS DEFINED AS FOLLOWS: "ASME"=ITEM REQUIRED BY ASME SECTION XI CODE AUG99=AUGMENTED PROGRAM-ITEM REQUIRED BY NRC COMMITMENT"OE"=OWNER ELECTED-NON MANDATORY EXAMINATIONS R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N1A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT.)Al.STEAM GENERATOR A (CONT.)DRAWINGS: A-5 Summary Number 006190 Exam Categ B-F Item Number Component aa rara ararraaaaaararaaaraaar B5.70 NSE-2R NOZZLE-TO-SAFE END (OUTLET)Component Type PT UT 96 PT&UT'ERFORMED BY B&Ws REPORT I 7705 1 566 ACCEPTABLE.

UT;PERFORMED BY RG&E NO RECORDABLE INDICATIONS

-ACCEPTABLE.

006200 B-J B9.11 PL-FW-ZX-ASW-R SAFE END-TO-ELBOW (OUTLET)OE PT RT 96-PT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

006430 B-G-2 B7.30 ZMN-AR INLET MANWAY NUTS (20)VT MT ,96-VT&MTS NO RECORDABLE INDICATIONS

-ACCEPTABLE.

006435 B-G-2 B7.30 IMS-AR OE INLET MANWAY STUDS (20)VT MT 96-VT&MTS'O RECORDABLE INDZCATZONS

-ACCEPTABLE.

006530 B-G-2 B7.30 OMN-AR OUTLET MANWAY NUTS (20)OE VT MT 96-VT&MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

006535 B-G-2 B7.30 OMS-AR OE OUTLET'MANWAY STUDS (20)VT MT 96-VT&MTS'O RECORDABLE INDICATIONS

-ACCEPTABLE.

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner Rochester Gas&Electric Cor.,89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/'A 5.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT~): A1.STEAM GENERATOR A (CONT.)DRAWINGS: A-5 Summary Number Exam Categ Item Number Component Component Type BSS NDE Exam 006609 F-A Fl.40 SGA-SL OE SUPPORT COMPONENT-LEGS A TO D VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

006641 F-A F1.40 SGA-MS MZD SUPPORT VT 96-VT;NO RECORDABLE ZNDICATIONS

-ACCEPTABLE.

006644 F-A F1.40 SGA-RS RING SUPPORT OE VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

A2.STEAM GENERATOR B DRAWINGS: A-5 Summary Number 006700 Exam Item Categ Number Component SBSBRR SB BS RK BSR RBB R Nr SBBB Nf B-B B2.40 LHTSW-BR LOWER HEAD-TO-TUBE SHEET WELD Component Type Exam UT 9 6 UT r PERFORMED BY B&W 6 RE PORT I 77 05 2"22 f ACCE PTABLE 006900 B-D B3.140 INIR-BR INLET NOZZLE INSIDE RADIUS SECTION UT 96-UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT~)-a A2.STEAM GENERATOR B (CONT.)DRAWINGS: A-5 Summary Number Exam Item Categ Number Component Component Type Exam 006990 B-F B5.70 NSE-3R SAFE END-TO-NOZZLE (INLET)PT UT 96 PT&UTf'ERFORMED BY B&WS REPORT g 7705 2 55f ACCEPTABLE.

UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

007000 B-J B9.11 PL-FW-III-R ELBOW-TO-SAFE END (INLET)ASME PT RT 96-PT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

007100 B-D B3.140 ONIR-BR OUTLET NOZZLE INSIDE RADIUS SECTION UT 96-UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

007190 B-F'5.70 NSE-4R NOZZLE-TO-SAFE END~(OUTLET)ASME PT UT 96-PT&UT;PERFORMED BY B&W, REPORT))7705-2-56,-ACCEPTABLE.

UTS'O RECORDABLE INDICATIONS

-ACCEPTABLE.

007200 B-J B9.11 PL-FW-X-R SAFE END-TO-ELBOW (OUTLET)ASME PT RT 96-PT&RT;PERFORMED BY BECHTEL (CONAM),-ACCEPTABLE.

007430 B-G-2 B7.30 IMN-BR OE INLET MANWAY NUTS (20)96-VT&MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

VT i

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~cul 1970 6.National Board Number for Unit N/A ATTACHMENT CLASS 1 COMPONENTS (CONT.): A2.STEAM GENERATOR B (CONT.)DRAWINGS: A-5 Summary Number Item Categ Number Component Component Type 007435 B-G-2 B7.30 IMS-BR OE INLET MANWAY STUDS (20)VT MT 96-VT&MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

007530 B-G-2 B7.30 OMN-BR OUTLET MANWAY NUTS (20)OE VT MT 96-VT&MTa NO RECORDABLE INDICATIONS

-ACCEPTABLE.

007535 B-G-2 B7.30 OMS-BR OUTLET MANWAY STUDS(20)OE VT MT 96-VT&MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

007609 F-A F1.40 SGB-SL SUPPORT COMPONENT LEGS H TO K OE VT 96-VTr NO RECORDABLE INDICATIONS

-ACCEPTABLE.

007641 F-A F1.40 SGB-MS MID SUPPORT OE VT 96-VTr NO RECORDABLE INDICATIONS

-ACCEPTABLE

~007644 F-A F1.40 SGB-RS RING SUPPORT OE VT 96-VTr'O RECORDABLE INDICATIONS

-ACCEPTABLE.

0 R.E.GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.commercial Service Date~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT.)A3.REACTOR COOLANT SYSTEM-LOOP A DRAWINGS: A-3A Summary Number Item Categ Number Component Component Type 011000 B9.31 PL-FW-II/10A-RCO-2501-A 10" BRANCH WELD ASME PT UT 96-PT;ACCEPTABLE

-1 ROUNDED INDICATION.

UTf NO RECORDABLE INDICATIONS

-ACCEPTABLE.

A4.10-1N.PRESSURIZER SURGE LINE DRAWINGS: A-3D Summary Number 014000 Item Categ Number Component Component Type B9.11 A ASME REDUCER"TO-PIPE (SURGE LINE)NDE Exam UT PT 96-PT&UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

014400 F-A F1.10V RCU-1 VARIABLE SPRING VT 96 VT-BP SI ZiE 1 4 9 SETTING 33 1 9 g S ACCEPTABLE

~A5.2-ZN.PRESSURIZER SPRAY LINE DRAWINGS: A-11 Summary Number Item Categ Number Component aaa a a aaaaaaa a aaaa aaaaaaaaaaa aaa Component Type 025100 B-J 96-PT;NO B9.40 19 ASME COUPLING-TO-PI PE a RECORDABLE INDICATIONS

-ACCEPTABLE.

PT

'

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~oui 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT.)A6.RESIDUAL HEAT REMOVAL FROM LOOP A HOT LEG DRAWINGS: A-15 Summary Number Item Categ Number Component Component Type 031125 F-A F1.10S RHU-33 MECHANICAL SNUBBER OE VT 96 VTr S/N 70649 SETTING 3 1/4 r'O RECORDABLE INDICATIONS ACCEPTABLE.

A7.2" LETDOWN FROM REGEN HTX DRAWINGS: A-24 Summary Number Exam Item Categ Number Component Component Type 048200 B-J B9.40 1 NOZZLE-TO-PIPE PT 96-PTr'O RECORDABLE INDICATIONS

-ACCEPTABLE'8.

SEAL WATER TO RCP-B DRAWINGS: A-32 Summary Number 049370 Exam Item Categ Number Component RSBS CBB C QR C R BB CC C BB F-A F1.10S CVU-104 MECHANICAL SNUBBER Component Type ms cBBQ OE NDE Exam VT 96 VTr PSA 1 9 S/N 24499 SETTING 2 9 NO RECORDABLE INDICATIONS ACCEPTABLE

~A9.2" CHARGING TO LOOP B COLD LEG DRAWINGS: A-25 Summary Number 051300 Exam Categ B-J Item Number Component B9.40 28 PIPE-TO-NOZZLE Component Type ASME PT 96-PT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

R.E.GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Oui 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT.)A10.2" ALTERNATE CHARGING TO LOOP A COLD LEG DRAWINGS: A-26 Summary Number Item Categ Number Component Component Type Exam 051600 B-J B9.40 21 PIPE-TO-ELBOW ASME PT 96-PT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

052300 B-J B9.40 28 ELBOW-TO-PIPE ASME PT 96-PT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

053300 B-J B9.40 38 VALVE(383A)-TO-PIPE AUG PT UT 96-PT&UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

A11.2" ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS: A-27 Summary Number Exam Categ Z tern Number Component Component Type 054980 B-J B9.40 9E ASME TEE-TO-PIPE PT 96-PT;NO RECORDABLE INDZCATZONS

-ACCEPTABLE.

055100 B-J B9.40 11 VALVE(393)-TO-PIPE AUG PT UT 96-PT&UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

10 0

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval,, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A B.commercial Service Date~Jul 1970 B.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT.): A12.REACTOR COOLANT PUMP A DRAWINGS: A-7 Summary Number Ztem Categ Number Component Component Type 056812 B-G-1 B6.180 STUD$12 OE BOLTINGf INPLACE UT 96-UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

OE 056818 B-G-1 B6.180 STUD ()18 BOLTING, INPLACE 96-UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

UT A13.REACTOR COOLANT PUMP B DRAWINGS'-6 Summary Number Item Categ Number Component Component Type 058120 BOLT RCP-B ANCHOR BOLTS BOLTS OE UT 96-UT;INSIGNIFICANT; INDICATION STILL SEEN ON STUD N2.NO CHANGE SINCE LAST EXAMINATION IN 1995-ACCEPTABLE.

A14.H.P.SAFETY INJECTION LINE TO LOOP B COLD LEG DRAWINGS: A-16 Summary Number 058300 Item Number Exam Categ B-G-2 B7.70 Component BB~BBBBB BBBBBBBBBBBBBB~BBBBBBMBBBBMMBB V-842A (BOLTING)10" DARLING CHECK VALVE Component Type ASME VT 96-VT;TAKING CODE CREDIT THIS OUTAGE-ACCEPTABLE.

R.E.GINNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas a Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT.): A15.RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: A-14 Summary Number Exam Categ Item Number 059300 B-G-2 B7.70 Component V-720 (BOLTING)10" VELAN MOTOR OPER.GATE VALVE 1500N Component Type ASME VT 96-VT;TAKING CODE CREDIT THIS OUTAGE-ACCEPTABLE.

B.CLASS 2 COMPONENTS:

Bl.2" CHARGING FROM REGEN HTX DRAWINGS: A-29 Summary Number Exam Categ item Number Component Component Type Exam 050930 C3.20 CVU-54 (IA)INTEGRAL ATTACHMENT PT 96-PT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

050933 F1.20R CVU-'54 RIGID RESTRAINT (IA)VT 96-VT;DRAWING DOES NOT SHOW MISSING EDGE WELDS, ACTION REPORT 96-0433 GENERATED.

ACCEPT AS IS-DWG TO BE CHANGED.NO RECORDABLE INDICATIONS ACCEPTABLE.

12 8

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649'2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B2.STEAM GENERATOR A DRAWINGS: B-1 Summary Number Item Categ Number Component Component Type 070700 C1.30 TSSW-AR OE TUBE SHEET-TO-SHELL WELD UT 96-UT: PERFORMED BY B&W, REPORT I 7705-1-77-ACCEPTABLE.

070900 C-A C1.10 LST-AR OE LOWER SHELL-TO-TRANSITION CIRC WELD UT 96-UT;PERFORMED BY B&W, REPORT ()7705-1-80,-ACCEPTABLE.

071000 C-A C1.10 TUS-AR OE TRANSITION-TO-UPPER SHELL CIRC WELD UT 96 UT PERFORMED BY B&WS REPORT g 7705 1 1 60/1 59 f ACCEPTABLE 071100 C-A C1.20 USH-AR UPPER SHELL-TO-HEAD CIRC WELD OE UT 96 UTa PERFORMED BY B&WS REPORT ()7705 1 1629 ACCEPTABLE.

071200 C-B C2.21 FWIN-AR FEEDWATER INLET NOZZLE TO VESSEL WELD MT UT 96-MT&UT;PERFORMED BY B&W, REPORT I'S 17&7705-1-169,-ACCEPTABLE.

071250 C-B C2.22 FWIN-AR FEEDWATER INLET NOZZLE INSIDE RADIUS OE UT 96-UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B2.STEAM GENERATOR A (CONT.)DRAWINGS'-1 Summary Number Exam Categ Item Number 071360 C-C C3.10 Component Component Type AB1R OE EARTHQUAKE BRACKET-IA NDE Exam MT 96 MTa PERFORMED BY B&WS REPORT¹1 8f ACCEPTABLE

~071362 C-C C3.10 AB2R EARTHQUAKE BRACKET-IA OE MT 96 MT r'ERFORMED BY B&W 9 REPORT¹1 8 f ACCEPTABLE

~071364 C-C C3.10 AB3R EARTHQUAKE BRACKET-IA OE MT 96 MTr PERFORMED BY B&WS REPORT¹1 8 9 ACCEPTABLE 071366 C-C C3.10 AB4R EARTHQUAKE BRACKET-IA MT 96 MT PERFORMED BY B&WS REPORT¹18f ACCEPTABLE

~B3., STEAM GENERATOR B DRAWINGS B-1 Summary Number 071400 Exam Item Categ Number Component m C-A C1.30 TSSW-BR TUBE SHEET-TO-SHELL WELD Component Type m ASME UT 96-UT;PERFORMED PY B&W, REPORT¹7705-2-77,-ACCEPTABLE.

14 R.E.GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z CLASS 2 COMPONENTS (CONT.)B3.STEAM GENERATOR B (CONT.)DRAWINGS: B-1 Summary Number 071600 Exam Categ C-A Item Number Component C1.10 LST-BR LOWER SHELL-TO-TRANSITION CIRC WELD Component Type OE NDE Exam UT 96-UT;PERFORMED BY B&W, REPORT N 7705-2-80,-ACCEPTABLE.

071700 C-A C1.10 TUS-BR TRANSITION-TO-UPPER SHELL CIRC WELD OE UT 96 UTS PERFORMED BY B&WS REPORT g 7705 2 160/159,-ACCEPTABLE.

071800 C-A C1.20 USH-BR UPPER SHELL-TO-HEAD CIRC WELD OE UT 96-UTa PERFORMED BY B&W, REPORT ()7705-2-162,-ACCEPTABLE.

071900 C-B C2.21 FWIN-BR FEEDWATER INLET NOZZLE TO VESSEL WELD OE MT UT 96-MT&UT;PERFORMED BY B&W, REPORT O'S 18&7705-2-169,-ACCEPTABLE.

071950 C-B C2.22 FWIN-BR FEEDWATER INLET NOZZLE INSIDE RADIUS OE UT 96-UTS'O RECORDABLE INDICATIONS

-ACCEPTABLE.

a 072080 C-C C3.10'BB1R EARTHQUAKE BRACKET-IA OE 96 MTS PERFORMED BY B&WS REPORT ()1 8 9 ACCEPTABLE

~15 l

R.E.GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)B3.STEAM GENERATOR B (CONT.)DRAWINGS: B-1 Summary Number Exam Categ Item Number Component Component Type 072082 C-C C3.10 BB2R EARTHQUAKE BRACKET-IA OE MT 96-MT;PERFORMED BY B&W, REPORT¹18,-ACCEPTABLE.

072084 C-C C3.10 BB3R EARTHQUAKE BRACKET-IA OE 96-MTr'ERFORMED BY B&W, REPORT¹18,-ACCEPTABLE.

072086 C-C C3.10 BB4R EARTHQUAKE BRACKET-IA MT 96-MT;PERFORMED BY B&W, REPORT¹18,-ACCEPTABLE.

B4.CHARGING PUMP A TO PULSE DAMPENER DRAWINGS: B-6 Summary Number 075700 Exam Categ C-F-1 Item Number Component C5.11 1 CAP-TO-PIPE Component Type Exam VT PT 96-PTa REJECTf'/4" LONG INDICATION WITHIN ARC STRIKE, CONSTRUCTION, NOT SERVICE INDUCED.ACTION.REPORT 96-0412 GENERATED, CODE REPAIR MADE.RE-EXAM-ACCEPTABLE.

VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

075900 C-F-1 C5.11 3ELBOW-TO-PIPE ASME PT UT 96-PT&UTf'O RECORDABLE INDICATIONS

-ACCEPTABLE.

16

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.commercial Service Date~Jul 1970 6.National Board Number for Unit N/JL ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B4.CHARGING PUMP A TO PULSE DAMPENER (CONT)DRAWINGS B-6 Summary Number Exam Categ m Item Number Component.

Component Type 077400 F1.20R CVU-410 RIGID RESTRAINT (IA)OE VT 96 VT r RE JECT SELF LOCK 1NG NUTS LOOSE (4 THREADS)f ACTION REPORT 96-0411 GENERATED.

RE-EXAM AFTER TIGHTENING

-ACCEPTABLE.

NOT SERVICE INDUCED.077401 C-C C3.20 CVU-410 (IA)INTEGRAL ATTACHMENT ASME PT 96-PTr REJECT;POOR ORIGINAL CONSTRUCTION WELD QUALITY.ACTION REPORT 96-0411 GENERATED.

WELD REWORKED.RE-EXAM-ACCEPTABLE.

NOT SERVICE INDUCED.B5.CHARGING PUMP C TO PULSE DAMPENER DRAWINGS'-6 Summary Number Exam Item Categ Number Component Component Type 076800 C-F-1 C5.11 2 PIPE-TO-ELBOW ASME PT UT 96-PT&UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

17 R.E.GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A B.commercial Service Date~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B6.CHARGING PUMP B TO PULSE DAMPENER DRAWINGS B-6 Summary Number 077600 Exam Categ F-A Item Number F1.20R Component CVU-412 RIGID RESTRAINT (IA)Component Type OE VT 96-VT;REJECT;INTEGRAL ATTACHMENT ORIGINAL CONSTRUCTION POOR WELD QUALITY ACTION REPORT 96 0411 GENERATED'ELD REWORKEDf RE-EXAM-ACCEPTABLE.

NOT SERVICE INDUCED.077601 C-C C3.20 CVU-412 (IA)INTEGRAL ATTACHMENT PT 96-PTr'EJECTr'NTEGRAL ATTACHMENT ORIGIONAL CONSTRUCTION POOR WELD QUALITY.ACTION REPORT 96-0411 GENERATED.

WELD REWORKED, RE-EXAM-ACCEPTABLE.

NOT SERVICE INDUCED.B7.MAIN STEAM LOOP A INSIDE CV DRAWINGS: B-8 Summary Number Exam Ca'teg Item Number Component Component Type 079000 C-F-2 C5.51 A-R NOZZLE-TO"ELBOW (S/G-A)OE MT UT 96'-MTr'XAM PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

UT;NO RECORDABLE

&INSZGNIFZCANT; GEOMETRY-ACCEPTABLE.

079175 C-F-2 C5.51 A1Z PI PE-TO-PI PE OE MT RT 96-MT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

079200 C-F-2 C5.51 A1-R PI PE-TO-PI PE OE MT RT 96-MT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

18 R.E.GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric'Cor

.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial service Date~oui 1970 B.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)" B7.MAIN STEAM LOOP A INSIDE CV (CONT)DRAWINGS: B-8 Summary Number Item Categ Number Component Component Type 079500'1.20V MSU-1 VARIABLE SPRING OE VT 96-VTf'ETTING 3 1/2"=11123 O'S, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

079600 F-A F1.20S MSU-2 MECHANICAL SNUBBER OE VT 96-VT;SETTING 3 3/4", NO RECORDABLE ZNDICATIONS

-ACCEPTABLE.

079700 F-A F1.20S MSU-3 MECHANICAL SNUBBER (ZA)VT 96 VT SETTING 3 9 NO RECORDABLE INDICATIONS ACCEPTABLE 079750 C-C C3.20 MSU-3 (IA)INTEGRAL ATTACHMENT MT 96-MTr'O RECORDABLE INDICATIONS

-ACCEPTABLE.

080000" F-A F1.20V MSU-4 VARIABLE SPRING OE VT 96 VTa SETTING 1 1/4=>7989 g Sf NO RECORDABLE INDICATIONS ACCEPTABLE.

080100 F-A F1.20V MSU-5 VARIABLE SPRING ASME VT 96-VT: REJECT;LACK OF THREAD ENGAGEMENT.

ACTION REPORT 96-0489 GENERATED.

BECHTEL PERFORMED REWORK.RE-EXAM-ACCEPTABLE.

NOT SERVICE INDUCED.19 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B8.MAIN STEAM LOOP A OUTSIDE CV DRAWINGS B-9 Summary Number Exam Categ Item Number Component Component Type NDE Exam 081550 C-F-2 C5.52 E1L1 ELBOW LONGITUDINAL WELD ASME VT MT UT 96-VT&MT;NO RECORDABLE 1NDZCATIONS

-ACCEPTABLE.

UT;NO RECORDABLE

&INSIGNIFICANT; NO CHANGE SINCE LAST EXAM-ACCEPTABLE.

081650 C-F-2 C5.51 E1A PIPE-TO-ELBOW VT MT UT 96-VT&MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

UT;NO RECORDABLE

&COUNTERBORE GEOMETRYa-ACCEPTABLE.

B9.MAIN STEAM LOOP B INSIDE CV 6 DRAWINGS'-8 Summary Number 084400 Exam Categ C-F-2 C5.51 A-R NOZZLE-TO-ELBOW (S/G-B)Item Number Component Component Type NDE Exam MT UT 96-MTa PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

UT;NO RECORDABLE ID GEOMETRY-ACCEPTABLE.

084600 C-F-2 C5.51 Al-R PIPE-TO-ELBOW MT RT 96-MT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

084700 F-A v F1.20V MSU-6'ARIABLE SPRING VT 96-VT;SETTING 7900))'S, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

20 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)B9.MAIN STEAM LOOP B ZNSZDE CV (CONT.)DRAWINGS: B-8 Summary Number Exam Item Categ Number Component Component Type Exam 084900 F-A'1.20S MSU-7 MECHANICAL SNUBBER ASME VT 96-VT;SETTING 3"&2 3/4".NO RECORDABLE INDICATIONS

-ACCEPTABLE.

085200 F-A F1.20S MSU-8 HYDRAULIC SNUBBER OE VT 96-VT;REJECTa INCORRECT SETTING&NUT/BOLT TURNS AS ONE.ACTION REPORT 96-0465 GENERATED.

RE-EXAM AFTER ADJUSTMENTS

-ACCEPTABLE.

NOT SERVICE INDUCED.085300 F-A F1.20V MSU-9 VARIABLE SPRING OE VT 96-VTa SETTING=7400 O'S, INSIGNIFICANT; LACK OF THREAD ENGAGEMENT BY ONE THREAD OK PER MECH.ENG.LETTER-ACCEPTABLE.

085400 F-A F1.20V MSU-10 VARIABLE SPRING OE VT 96 VT.SETTING~8554 gfS NO RECORDABLE INDICATZONS ACCEPTABLE B10.MAIN STEAM LOOP B OUTSIDE CV DRAWINGS'-10A Summary Number 087625 Exam Categ Item Number Component m F1'0S MSU-25 MECHANICAL SNUBBER (IA)I'omponent Type OE Exam VT 96-VT;SETTING 1 3/4", NO RECORDABLE INDICATZONS

-ACCEPTABLE.

21 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2'.Plant R.E.Ginna Nuclear Power Plant,'1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul'970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B10.MAIN STEAM LOOP B OUTSIDE CV (cont.)DRAWINGS: B-10A Summary Number Exam Categ Item Number Component Component Type 087630 C-C C3.20 MSU-25 (IA)INTEGRAL ATTACHMENT ASME 96-MT: NO RECORDABLE INDICATIONS

-ACCEPTABLE.

Bll.FEEDWATER LOOP A OUTSIDE CV DRAWINGS: B-ll Summary Number Exam Categ Item Number Component Component Type 091225 F-A F1.20S FWU-15 MECHANICAL SNUBBER (ZA)VT 96-VT;SETTING 2 5/8", NO RECORDABLE INDICATIONS

-ACCEPTABLE.

091226 C-C C3.20 FWU-15 (ZA)ASME INTEGRAL ATTACHMENT 96-MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

B12.FEEDWATER LOOP A INSIDE CV DRAWINGS: B-12 Summary Number 092300 Exam Item Categ Number Component KKRRRRBS BS QSB RRRRRRRBSSS RR~~RRBSR F-A F1.20V FWU-6 VARIABLE S PRING Component Type OE VT 96-VT: SETTING=2556 O'S, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

22 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)t 1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)B12.FEEDWATER LOOP A INSIDE CV (CONT.)DRAWINGS: B-12 Summary Number 092600 Item Categ Number Component F1.20V FWU-4 VARIABLE SPRING Component Type OE VT 96-.VTl SETTING=2797 O'S.NO RECORDABLE INDICATIONS

-ACCEPTABLE.

093100 F-A F1.20V FWU-2 VARIABLE SPRING VT 9 6 VT a SETTING 2 1 04 g S 6 NO RECORDABLE INDICATIONS ACCEPTABLE 093400 C-F-2 C5.51 DD3-R PIPE-TO-ELBOW OE MT RT 96-MT&RTf PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

093500 F-A F1.20V FWU-1 VARIABLE SPRING (IA)OE VT 96 VTr SETTING 2617 g Sf NO RECORDABLE INDICATIONS ACCEPTABLE 093505 C-C C3.20 FWU-1 (IA)INTEGRAL ATTACHMENT OE MT 96-MTS NO RECORDABLE INDICATIONS

-ACCEPTABLE.

093800 C-F-2 C5.51 DD6-R ELBOW-TO-PIPE OE MT RT 96-MT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

R.E.GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 B.National Board Number for Unit N/JL ATTACHMENT I CLASS 2 COMPONENTS (CONT.)'12.

FEEDWATER LOOP A INSIDE CV (CONT,)DRAWINGS: B-12 Summary Number 093900 Exam Categ Item Number Component C-F-2 C5.51 DD7-R PIPE-TO-ELBOW Component Type OE NDE Exam MT RT 96-MT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

094000 C-F-2 C5.51 DDS-R ELBOW-TO-PIPE MT RT 96-MT&RT a PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE

.094200 C-F-2 C5.51 DD10-R REDUCER-TO-ELBOW OE MT RT 96-MT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

094300 C-F-2 C5.51 EE-R ELBOW-TO-SAFE END (S/G-A)OE UT PT 96-PT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

UT;NO RECORDABLE

&INS IGNI FI CANT ROOT f METALLURGI CAL INTER FACE&COUNTERBORE ACCEPTABLE.

094310 C-F-2 C5.51 E-R SAFE END-TO-NOZZLE (S/G-A)OE UT PT 96-PT&UT;PERFORMED BY B&W, REPORT O'S 16&7705-1-140;

-ACCEPTABLE.

24 R.E.GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B13.FEEDWATER LOOP B OUTSIDE CV DRAWINGS: B-14 Summary Number Exam Categ Item Number Component Component Type NDE Exam 094850 F-A F1.20R FWU-43 RIGID RESTRAINT OE VT 96-VTa NO RECORDABLE

&INSIGNIFICANT

-ACCEPTABLE.

B14.FEEDWATER LOOP B INSIDE CV DRAWINGS: B-13 Summary Number Exam Categ Item Number Component Component Type 097700 F-A F1.20V FWU-13 VARIABLE SPRING (IA)OE VT 96-VT: SETTING=3880 ()'S, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

098100 F-A Fl.20V FWU-11 VARIABLE SPRING OE VT 96-VT;SETTING 2199 OSS.NO RECORDABLE INDICATIONS

-ACCEPTABLE.

098600 F-A F1.20V FWU-10 VARIABLE SPRING VT 96 VTS SETTING 23 15 (t S 9 NO RECORDABLE

&INSZGNI FICANT J LACK OF ONE THREAD FULL ENGAGEMENT AT LOWER CLAMPS OK PER MECH ENG~LETTERS NOT SERVICE INDUCED-ACCEPTABLE.

098825 F-A Fl.20V FWU-9 VARIABLE SPRING OE VT 96 VTS SETTING 2 8 56 g S 9 NO RECORDABLE INDICATIONS ACCEPTABLE 25 R.E.GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B14.FEEDWATER LOOP B ZNSZDE CV (CONT.)DRAWINGS: B-13 Summary Number 098900 Exam Categ C-F-2 Item Number C5.51 Component AA-R PIPE-TO-ELBOW Component Type NDE Exam MT RT 96-MT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

099000 F-A F1.20V FWU-7 VARIABLE SPRING (IA)OE VT 96-VT;SETTING=2856 O'S, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

099005 C-C C3.20 FWU-.7 (IA)INTEGRAL ATTACHMENT OE 96-MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

099500 C-F-2 C5.51 AA4-R PIPE-TO-ELBOW OE MT RT 96-MT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

099800 C-F-2 C5.51 AA7-R REDUCER-TO-ELBOW OE RT MT 96-MT&RT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

099900 C-F-2 C5.51 BB-R OE UT ELBOW-TO-SAFE END PT (S/G-B)VT 96-PT;PERFORMED BY BECHTEL (CONAM)-ACCEPTABLE.

UT;NO RECORDABLE

&INSIGNIFICANTa GEOMETRY&METALLURGICAL INTERFACE-ACCEPTABLE.

VTa NO RECORDABLE INDICATIONS

-ACCEPTABLE.

26 n'

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 B.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B14.FEEDWATER LOOP B INSIDE CV (CONT.)DRAWINGS: B-13 Summary Number Item Categ Number Component Component Type NDE Exam 099910 C-F-2 C5.51 B-R SAFE END-TO-NOZZLE (S/G-B)OE UT PT 96 PT&UTa PERFORMED BY B&Wf REPORT f)S 17&7705 2 1409 ACCEPTABLE.

B15.H.P.SAFETY INJECTION LINE 8E-SZ-301 DRAWINGS: B-1 6 Summary Number 104200 Exam Categ Item Number Component mfa KBBBB D Km Rt RK RK R&rmrm F1.20R SZU-104 RIGID SUPPORT (IA)Component Type a 9 at aaaaaa VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

104210 C-C C3.'20 SIU-104 (ZA)INTEGRAL ATTACHMENT PT 96-PTr'O RECORDABLE INDICATIONS

-'ACCEPTABLE.

B16~H.P.SAFETY INJECTION LINE 8G-SZ-301 DRAWINGS: B-19 Summary Number 122600 Exam Categ Item Number Component me F1.20R RHU-112 RIGID SUPPORT (IA)Component Type OE VT 96-VTa NO RECORDABLE INDICATZONS

-ACCEPTABLE.

122602 C-C C3.20 RHU-112 (IA)INTEGRAL ATTACHMENT PT 96-PT;NO RECORDABLE INDICATIONS

<<ACCEPTABLE.

27 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~cul 1970 S.National Board Number for Unit N/A ATTACHMENT Z CLASS 2 COMPONENTS (CONT.): B17.RESIDUAL HEAT REMOVAL LINE 6K-AC-151 DRAWINGS: B-21 Summary Number 130050 Exam Categ Item Number F1.20V Component RHU-93 VARIABLE SPRING (IA)Component Type OE Exam VT 96-VT/'ETTING

=1755 ((', NO RECORDABLE

&INSIGNIFICANT; CAN BODY HAS LIGHT RUST&PEELING PAINT.BASE CHANNEL HAS HEAVY BA RESIDUE, RE-EXAM AFTER CLEANING-NO RECORDABLE

-ACCEPTABLE.

130055----C3.20 RHU-93 (IA)INTEGRAL ATTACHMENT PT 96-PT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

B18.RESIDUAL HEAT REMOVAL LINE 6C-AC-601 DRAWINGS: B-1 9 Summary Number Item Categ Number Component RRDRBBRXRSNNS Component Type NS M SN M BB BB M NS NDE Exam 157400 C-F-1 17 PI PE-TO-VALVE (857C)UT OE PT 96-PT&UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

B19.H.P.SAFETY INJECTION PUMP B SUCTZON LINE DRAWINGS: B-16B Summary Number 160500 Exam Item C-F-1 C5.21, 1 8X8X4 TEE-TO-PIPE r Categ Number Component Component Type NDE Exam PT UT 96-PT&UT/'O RECORDABLE INDZCATIONS

-ACCEPTABLE.

28 i e R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.commercial Beruice Date~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)B20.H.P.SAFETY INJECTION PUMP A SUCTZON LZNE DRAWINGS: B-1 6B Summary Number Exam Categ Item Number Component Component Type 160850 F1.20R RHU-120 OE VT RIGID SUPPORT (IA)96-VT;NO RECORDABLE

&INSIGNIFICANT; HEAT TRACE CLAMPED TO SUPPORT, WELL NOT INTERFERE WITH SUPPORT FUNCTION-ACCEPTABLE.

160851 C-C C3.20 RHU-120 (IA)INTEGRAL ATTACHMENT ASME PT 96-PTr'O RECORDABLE INDICATIONS

-ACCEPTABLE.

B21.H.P.SAFETY INJECTION LINE 3A-SZ-1501 DRAWINGS: B-37 Summary Number Exam Categ Item Number Component Component Type NDE Exam 161140 C5.21 12 ELBOW-TO-PIPE PT UT 96-PT&UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

B22.H.P.SAFETY INJECTION LZNE 4D-SZ-1501 DRAWINGS: B-37 Summary Number 161425 Exam Categ F-A Item Number F1.20A Component PEN 113 ANCHOR ANCHOR (IA)Component Type OE VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

161426 C-C C3.20 PEN 113 ANCHOR (IA)INTEGRAL ATTACHMENT ASME PT 96-PT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

29

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 B.National Board Number fo r'Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B22.H.P.SAFETY ZNJECTZONj'LINE 4D-SZ-1501 (CONT.)DRAWINGS: B-37 Summary Number 161530 Exam Categ F-A Item Number F1.20R Component SIU-39 RIGID RESTRAINT (IA)Component Type OE VT 96-VT;ACTION REPORT 96-0434 GENERATED DUE TO 0 DEG.STRUT AT 19 DEG.OK AS IS-DRAWING TO BE REVISED.NOT SERVICE INDUCED-CONSTRUCTION.

NO RECORDABLE INDICATIONS

-ACCEPTABLE.

161531 C-C C3.20 SZU-39 (IA)INTEGRAL ATTACHMENT PT 96-PT: NO RECORDABLE INDICATIONS

-ACCEPTABLE.

B23.H.P.SAFETY INJECTION LINE 2T-SZ-2501 DRAWZNGS: B-39 Summary Number Exam Item Categ Number Component Component Type 161760 C-F-1 C5.30 6 ASME PIPE-TO-TEE PT 96-PT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

B24.H.P.SAFETY INJECTZON LINE 2U-SZ-2501 DRAWINGS: B-39 Summary Number 162180 Z tern Categ Number Component F1.20A SZU-30 ANCHOR (IA)OE VT NDE Component Type Exam 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

30 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z CLASS 2 COMPONENTS (CONT.): B24.H.P.SAFETY INJECTION, LINE 2U-SZ-2501 (CONT.)DRAWZNGS: B-39 Summary Number 162181 Exam Item Categ Number Component C-C C3.20 SIU-30 (IA)INTEGRAL ATTACHMENT Component Type ASME Exam PT 96-PT;NO RECORDABLE

&1NSIGNIFICANT; SEVERAL ROUNDED INDICATIONS THAT WERE 3/16" OR LESS-ACCEPTABLE.

162220 C-F-1 C5.30 38 PIPE-TO-VALVE (878F)ASME PT 96-PTr'O RECORDABLE INDICATIONS

-ACCEPTABLE.

B25.H.P.SAFETY INJECTION LINE 3C-SZ-1501 DRAWINGS: B-41 Summary Number Exam Categ Item Number Component Component Type 163030 C-F-1 C5.21 3 ELBOW-TO-PIPE ASME PT UT 96-PT&UTr NO RECORDABLE INDICATIONS

-ACCEPTABLE.

B26.H.P.SAFETY INJECTION LINE 4E-SI-1501 DRAWINGS: B-42 Summary Exam Number Categ 163935 F-A Item Number Component F1.20A PEN 101 ANCHOR ANCHOR (IA)v Component Type OE Exam VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

31

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear.Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)B26.H.P.SAFETY ZNJECTZONNLZNE 4E-SZ-1501 (CONT.)DRAWINGS: B-42 Summary Number 163936 Etiam Categ C-C Item Number C3.20 Component PEN 101 ANCHOR (IA)INTEGRAL ATTACHMENT Component Type ASME PT 96-PT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

164000 C-F-1 C5.21 38 ASME ELBOW-TO-PIPE PT UT 96-PT&UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

164360 C-F-1 C5.21 60 TEE-TO-REDUCER ASME PT UT 96-PT&UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

B27.SERVICE WATER LINE 6G-SW-125 DRAWZNGS'-50 Summary Number Etiam 1 tern Categ Number Component Component Type 173035 F1.20A PEN 319 ANCHOR ANCHOR (IA)OE VT 96-VT: NO RECORDABLE INDICATIONS

-ACCEPTABLE.

173036 C3.20 PEN 319 ANCHOR (IA)INTEGRAL ATTACHMENT OE 96-MT: NO RECORDABLE INDICATIONS

-ACCEPTABLE.

32 R.E.GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A B.commercial Service Date~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B28.SERVICE WATER LZNE 8N-SW-125.

DRAWINGS: B-50 Summary Number Exam Categ Item Number'omponent Component Type Exam 173160 C3.20 SWU-81 (IA)OE INTEGRAL ATTACHMENT MT'6-MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

173170----F1.20R SWU-81 OE GUIDE (IA)VT 96-VT;NO RECORDABLE

&INSIGNIFICANT; PAINT BU1LD-UP IN GAP-ACCEPTABLE.

B29.SERVICE WATER LINE 88-SW-125 DRAWZNGS: B-51 Summary Number Exam Categ Item Number Component Component Type 173860 C3.20 SWU-88 (IA)OE INTEGRAL ATTACHMENT MT 96-MT;NO RECORDABLE INDICATIONS

'-ACCEPTABLE.

173870 F1.20R SWU-88 GUIDE (IA)VT 96-VTJ'O RECORDABLE INDICATZONS

-ACCEPTABLE.

B30.SERVICE WATER LZNE 8F-SW-125 DRAWINGS: B-52 Summary Number 174460 Item Categ Number COmponent C3.20 SWU-89 (ZA)INTEGRAL ATTACHMENT Component Type OE 96-MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

33

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 1nterval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.): B30.SERVICE WATER LZNE 8F-SW-125 (CONT.)DRAWINGS: B-52 Summary Number Item Categ Number Component Component Type NDE Exam 174470 F1.20R SWU-89 RIGID RESTRAINT (IA)OE VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

B31.SERVICE WATER LINE 8B-SW-125 DRAWINGS: B-53 Summary Number 175460 Item Categ Number C3.20 Component SWU-42 (IA)INTEGRAL ATTACHMENT Component Type OE MT 96-MTS NO RECORDABLE 1NDICATZONS

-ACCEPTABLE.

175470-;--F1.20R SWU-42 RIGID RESTRAINT (ZA)VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

C.CLASS 3 COMPONENTS:

Cl.DIESEL GENERATOR B Z.W.COOLING RETURN DRAWINGS: C-36 Summary Number Exam Categ Item Number Component Component Type 500140 D-B D2.20 DG-1B (IA)INTEGRAL ATTACHMENT VT 96-VT;REJECTS'RIGINAL CONSTRUCTION UNDERCUT WITHIN INTEGRAL ATTACHMENT.

OK PER MECH.ENG.MEMO.NOT SERVICE INDUCED.NO RECORDABLE

&INSIGNIFICANT; GAP IN PLATE-ACCEPTABLE.

34

R.E.GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 3 COMPONENTS (CONT.)Cl.DIESEL GENERATOR B tT.W.COOLING RETURN (CONT.)DRAWINGS: C-36 Summary Number Item Categ Number Component Component Type Exam 500145 F1.30R DG-1B RIGID SUPPORT (ZA)OE VT 96-REJECT;ORIGINAL CONSTRUCTION UNDERCUT WITHIN INTEGRAL ATTACHMENT.

OK PER MECH.ENG.MEMO.NOT SERVICE INDUCED.NO RECORDABLE

&INSIGNIFICANT; GAP IN PLATE-ACCEPTABLE.

500150 D-B D2.20 DG-2B (IA)INTEGRAL ATTACHMENT ASME VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

500155 F-A F1.30R DG-2B RIGID SUPPORT (IA)OE VT 96-VT;NO RECORDABLE'INDICATIONS

-ACCEPTABLE.

a C2.AUX.FW PUMPS DZSCH-ZNTERMED.BLDG.DRAWINGS C-1C Summary Number 505260 Exam Item Categ Number Component BBQLSC'RRD BB CS RC ZRZZZRS R BBR F1.30S AFU-103 MECHANICAL SNUBBER Component Type OE'DE VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

SETTINGS: EAST 3" S/N 18184, WEST 3 1/2" S/N 18185.505320 F-A F1.30S AFU-34~MECHANICAL SNUBBER OE VT 96-VTS'O RECORDABLE INDICATIONS

-ACCEPTABLE.

SETTING=2 3/4".35 p~t R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.commercial Service Date~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 3 COMPONENTS (CONT.)C2.AUX.FW PUMPS DZSCH-.~ZNTERMED.BLDG.(CONT.)DRAWINGS: C-1C Summary Number Item Categ Number Component Component Type NB Qc R Rc 505500 F-A F1.30S AFU-52 MECHANICAL SNUBBER OE VT 96-VTr NO RECORDABLE 1NDICATIONS

-ACCEPTABLE.

SETTZNG=1 3/4" 505750 F-A F1.30S AFU-75 MECHANICAL SNUBBER OE VT 96-VT'O RECORDABLE ZNDICATIONS

-ACCEPTABLE.

SETTING=2 1/8".C3.COMPONENT COOLING HEAT EXCHANGER B DRAWINGS C-41 Summary Number Item Categ Number Component Component Type NDE Exam 555200 D-B D2.20 CCW1B-W (IA)INTEGRAL ATTACHMENT ASME VT 96-VT;NO RECORDABLE

&INSIGNIFICANT; LIGHT RUST-ACCEPTABLE.

555250 F-A F1.40.CCW1B-W SUPPORT WEST (IA)VT 96-VTr NO RECORDABLE INDICATIONS

-ACCEPTABLE.

555300 D-B D2.20 CCWlB-E (IA)INTEGRAL ATTACHMENT ASME VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

555350 F-A 9 F1.40 CCW1B-E SUPPORT EAST (IA)VT 96-VT;NO RECORDABLE INDZCATIONS

-ACCEPTABLE.

36 I,

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I D.HIGH ENERGY COMPONENTS:

D1.MAIN STEAM TURBINE BUILDING DRAWINGS: HE-7A Summary Number Item Categ Number Component Component Type 200265 HE-CB B PIPE-TO-ELBOW AUG UT MT VT 96-MT&VT;REJECT-ARC STRIKES, GOUGES&LUG STUBS.NOT SERVICE INDUCED CONSTRUCTION.

INDICATIONS REMOVED BY GRINDING.MT&VT RE-EXAM AFTER REPAIRS-ACCEPT.

UT THICKNESS READINGS-ACCEPT.

UT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

D2.FEEDWATER LOOP A OUTSIDE CV DRAWINGS: HE-5 Summary Number Exam Item Categ Number Component Component Type 201700 HE-CS*F1.20S FWU-26 OE MECHANICAL SNUBBER (IA)VT 96-VT;NO RECORDABLE INDZCATIONS

-ACCEPTABLE.

201701 HE-IA*C3.20 FWU-26 (IA)INTEGRAL ATTACHMENT AUG MT 96-MTr NO RECORDABLE INDICATIONS

-ACCEPTABLE.

201720 HE-CS*F1.20R FWU-27 RIGID SUPPORT (IA)OE VT 96-VT: NO RECORDABLE

&INSIGNIFICANT; 2 ADDITIONAL STANCHION LUGS HAVE BEEN ADDED, DRAWING TO BE REVISED-ACCEPTABLE.

201721 HE-IA*C3.20FWU-27 (IA)INTEGRAL ATTACHMENT AUG MT 96-MT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

37 e

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commeccial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I E.LEAKAGE TESTING: E 1 LEAKAGE EXAMZNAT IONS CLASS 1 9 2 9 3 DRAWINGS L-1 Summary Number 411000 Etiam Categ B-P Item Number Component IWB5221 PT-7 LEAKAGE TEST OF REACTOR COOLANT SYSTEM Component Type ASME VT 96-VT;NO EVIDENCE OF LEAKAGE AT FINAL PLATEAU.LAST PLATEAU WAS HELD FOR 4 HRS AT OPERATING TEMPERATURE

&PRESSURE BEFORE WALKDOWN.ACCEPTABLE.

412100 D-B IWD5221 STANDBY AUXILIARY FEEDWATER PUMP"D" ASME VT 96-VTr NO EVIDENCE OF LEAKAGE.COMPLETED BOUNDARY THIS OUTAGE-ACCEPTABLE.

414000 D-A IWD5221 SERVICE WATER OUTSIDE CONTAINMENT ASME VT 96-VT;NO EVIDENCE OF LEAKAGE.COMPLETED BOUNDARY THIS OUTAGE.-ACCEPTABLE.

415600 C-H, IWC5221 PRESSURIZER (TRC01)CLASS 2 INSTRUMENTATION ASME VT 96-VTf-ACCEPTABLE.

415650 C-H IWC5221 RPV (RPC01)CLASS 2 INSTRUMENTATION ASME VT 96-VT;-ACCEPTABLE.

38

, 0 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I F.STEAM GENERATOR EDDY CURRENT EXAMINATIONS:

Fl.STEAM GENERATOR A DRAWINGS: N/A Summary Number Exam Item Categ Number Component Component Type NDE Exam 802500 B-Q B16.20 OPEN GENERATOR TUBES BOBBIN COIL-100%FULL LENGTH ASME ET ET 96-ET;SEE 1996 S/G EDDY CURRENT FINAL REPORT&BWZ FINAL REPORT FOR DETAILS,-ACCEPTABLE.

802600 SG-ET----OPEN GENERATOR TUBES OE ET PERIPHERAL TUBES ET 96-ET'EE 1996 S/G EDDY CURRENT FINAL REPORT&BWI FINAL REPORT FOR DETAILS,-ACCEPTABLE.

F2.STEAM GENERATOR B DRAWINGS: N/A Summary Number Item Categ Number Component Component Type NDE Exam 803500 B-Q B16.20 OPEN GENERATOR TUBES BOBBIN COIL-100'8 FULL LENGTH ET ET 96-ET SEE 1996 S/G EDDY CURRENT FINAL REPORT&BWI FINAL REPORT FOR DETAZLS,-ACCEPTABLE.

803600 SG-ET----OPEN GENERATOR TUBES OE ET PERIPHERAL TUBES ET 96-ET;SEE 1996 S/G EDDY CURRENT FINAL REPORT&BWI FINAL REPORT FOR DETAILS,-ACCEPTABLE.

39

,S R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Gi.nna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I G.SNUBBER PROGRAM COMPONENTS:

Gl.STEAM GENERATOR A DRAWINGS: A-7F Summary Number Item Categ Number Component Component Type Exam 600080 SN-VT SGA-7 HYDRAULIC SNUBBER AUG VT 96 VTS SETTING 38 1/8 f S/N 7728073 A NO RECORDABLE 1NDICATIONS ACCEPTABLE.

600090 SN-VT----SGA-8 HYDRAULIC SNUBBER AUG VT 96 VTS SETTING 38 1/4 9 S/N 7728073 A NO RECORDABLE INDICATIONS ACCE PTABLE.a a 600091 SN-FT----SGA-8 HYDRAULIC SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.G2.STEAM GENERATOR B DRAWINGS: A-7F Summary Number 600120., SN-VT SGB-3 HYDRAULIC SNUBBER Exam Item Categ Number Component Component Type AUG NDE Exam VT 96 VT SETTING 38 1/2 f S/N 7728073 A NO RECORDABLE INDICATIONS ACCEPTABLE.

600130 SN-VT----SGB-4 HYDRAULIC SNUBBER AUG VT 96-VT;SETTING 38 3/8", S/N=7728073-A.

NO RECORDABLE INDICATIONS

-ACCEPTABLE.

a 40 J!

R.E.GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G3.TURBINE DRIVEN AUX.FW PUMP SUCTION DRAWINGS: C-16 Summary Number Exam Item Categ Number Component Component Type Exam 600200 SN-VT AFU-3 MECHANICAL SNUBBER AUG VT 9 6 VT r SETTING 2 9 S/N 2 0 925 9 NO RECORDABLE I NDI CAT IONS ACCEPTABLE G4.AUX.FW PUMPS DZSCH-ZNTERMED~BLDG.DRAWINGS: C-1E Summary Number Exam Item Categ Number Component Component Type NDE Exam 600220 SN-VT AFU-31 MECHANICAL SNUBBER AUG VT 96 VTS'ETTING 2 3/4 9 S/N 244529 NO RECORDABLE INDICATIONS ACCEPTABLE

~600240 SN-VT----AFU-34 MECHANZCAL SNUBBER AUG VT 96 VT SETTING 2 3/4 9'/N 144489 NO RECORDABLE INDICATIONS ACCEPTABLE

~600260 SN-VT----AFU-52 MECHANICAL SNUBBER AUG VT 96 VTS SETTING 1 3/4 9 S/N 244539 NO RECORDABLE INDICATIONS ACCEPTABLE

~600280 SN-VT----AFU-75 MECHANICAL SNUBBER AUG VT 96-VT;SETTING 2 1/8", S/N=20924, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

r

,

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.;Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G4.AUX.FW PUMPS DZSCH-ZNTERMED.BLDG.(CONT.)DRAWINGS: C-1E Summary Number Etiam Categ Item Number Component Component Type 600300 SN-VT----AFU-98 AUG MECHANICAL SNUBBER VT 96-VT;SETTING 1 9/16", S/N=24454, NO RECORDABLE INDICATIONS

-ACCEPTABLE'00320 SN-VT AFU-101 MECHANICAL SNUBBER AUG VT 96 VTS SETTING 3 3/8 f S/N 1 575 1 9 NO RECORDABLE I NDI CAT IONS ACCEPTABLE

~600339 SN-VT----AFU-103 (EAST)MECHANICAL SNUBBER AUG VT 96 VT SETTING 3 f S/N 1 8 1 84 f NO RECORDABLE INDZCATIONS ACCEPTABLE

~VT 600340 SN-VT----AFU-103 (WEST)AUG MECHANICAL SNUBBER 96-VT;SETTING 3 1/2", S/N=18185, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

600360 SN-VT----AFU-109 HYDRAULIC SNUBBER AUG VT 96 VTJ SETTING 2 1/4 f S/N 30986 NO RECORDABLE INDICATIONS ACCEPTABLE

~600380 SN-VT----AFU-111 MECHANICAL SNUBBER AUG VT 96 VT SETTING 2 1/16 f S/N 1 6377 f NO RECORDABLE INDICATIONS ACCEPTABLE 600400 SN-VT----AFU-123 MECHANICAL SNUBBER AUG VT 96-VT;SETTING 1 5/8", S/N=22485, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

42 0

-R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G4.AUX.FW PUMPS DISCH-1NTERMED.BLDG.(CONT.)DRAWZNGS: C-1E Summary Number Exam Item Categ Number Component Component Type 600420 SN-VT AFU-124 MECHANICAL SNUBBER AUG VT 96 VTa SETTING 2 f S/N 24451 f NO RECORDABLE INDICATIONS ACCEPTABLE G5.STEAM GENERATOR B BLOWDOWN LINE DRAWINGS: B-31 Summary Number Item Exam Categ Number Component Component Type CSS ZXNCS CBSNS 600460 SN-VT BDU-16 MECHANICAL SNUBBER AUG VT VTa RE J LOOSE NUTS f MZSALIGNMENT ACTION REPORTS 96 02469 0345 9 0426&0 5 3 5 GENERATED DI S POS I T ION OF ACTION REPORTS&MECH ENGS MEMO ACCEPT.SETTING=2 3/4" HOT, 1 1/2" COLD.S/N=10182.VT-ACCEPT.

SERVICE INDUCED-SNUBBER PROGRAM REQUIREMENTS.

G6.AUX.COOL LINE 4S-AC6-152 DRAWINGS: B-29 Summary Number 600530 Exam Item Categ Number Component RRRRR SS R%%%ASS SN-VT CCU-43 MECHANICAL SNUBBER Component Type MSS AUG NDE Exam VT 96-VT'ETTING 1 5/8", S/N=11462, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

G7.AUX.COOL SYS.FRM.PUMP COOL OUT.TO PEN126 DRAWINGS'-34 Summary Number Exam Categ Item Number Component Component Type NDE Exam 600610 SN-VT----CCU-57 AUG MECHANICAL SNUBBER VT 96 VT a'ETTING 2 1/2 9 S/N 1 8 1 94 9 NO RECORDABLE INDICATIONS ACCEPTABLE

.43 0

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT.)G8.AUX.COOL L1NE 4T-AC6-152 DRAWINGS: B-30 Summary Number Exam Categ Item Number Component Component Type 600710 SN-VT CCU-71 MECHANICAL SNUBBER AUG VT 96 VTr SETTING 2 1/2 f S/N 181939 NO RECORDABLE INDICATIONS ACCEPTABLE G9.2" LETDOWN TO REGEN HTX DRAWINGS: A-23 Summary Number Exam Item Categ Number Component Component Type 600880 SN-VT CVU-26 MECHANICAL SNUBBER AUG VT 96 VT SETTING 2 9 S/N 208 80 f NO RECORDABLE INDICATIONS ACCEPTABLE G10~2" CHARGING TO REGEN HTX DRAWINGS: A-30 Summary Number 600900 Exam Categ SN-VT Item Number Component CVU-46 MECHANICAL SNUBBER Component Type AUG.NDE Exam VT 9 6 VT r SETT ZNG 2 9 S/N 3 8 555 9 NO RECORDABLE INDICATIONS ACCEPTABLE G11.2" ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS'-27 Summary Number 600920 Exam Categ Item Number Component SN-VT----CVU-49 MECHANICAL SNUBBER Component Type AUG VT 96-VT;SETTING 1 1/2", S/N=9483, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

i 4 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~oui 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G12.2" CVCS RELZEF LINE TO PRT DRAWINGS: B-32 Summary Number Item Categ Number Component Component Type 600940 SN-VT CVU-80 MECHANICAL SNUBBER AUG VT 96 VTr SETTING 1 1/2 9 S/N 2 35 1 8 9 NO RECORDABLE INDICATIONS ACCEPTABLE G13.SEAL WATER TO RCP-B DRAWINGS'-32 Summary Number Exam Item Categ Number Component Component Type 600960 SN-VT CVU-103 MECHANICAL SNUBBER AUG VT 96 VTe SETTING 2 1/8 9 S/N 244509 NO RECORDABLE

&INSIGNIFICANT ACCE PTABLE.VT 600980 SN-VT----CVU-104 AUG MECHANICAL SNUBBER 96 VTa SETTING 2 9 S/N 24499 NO RECORDABLE INDICATIONS ACCEPTABLE

~G14.SEAL WATER RETURN FROM RCP-A DRAWINGS: B-34 Summary Number 9 OC SBB 601000 Exam Item Categ Number Component RRBBBBBSBSBB K%R BB 9 K D K R mt 9 BBBBK Component Type NDE Exam SN-VT----CVU-186 AUG VT MECHANICAL SNUBBER 96 VTe SETTING 14 9 S/N'654 1 9 NO RECORDABLE INDI CATZONS ACCEPTABLE

~45

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G15.2" LETDOWN LINE TO NON-REGEN HTX DRAWINGS: B-35 Summary Number Item Categ Number Component Component Type 601040 SN-VT CVU-345 MECHANICAL SNUBBER AUG VT 96 VT SETTING 1 1/4 9 S/N 9 4 9 1 9 NO RECORDABLE INDICATIONS ACCEPTABLE 601060 SN-VT----CVU-351 MECHANICAL SNUBBER AUG VT 96 VT SETTING 3/4 9 S/N 9472 9 NO RECORDABLE INDICATIONS ACCEPTABLE G16.CVCS LETDOWN LINE TO MZX BED DEMZN DRAWZNGS: B-36 Summary Number Exam Categ 601080SN-VT Item Number Component SN CVU-372 MECHANZCAL SNUBBER AUG VT Component Type Exam 96 VTr'ETTING 3/4 9 S/N 94789 NO RECORDABLE INDICATIONS ACCEPTABLE

~G17.FEEDWATER LOOP A INSIDE CV DRAWZNGS: B-12 Summary Number 601100 Exam Z tern Categ Number Component SN-VT FWU-3 HYDRAULIC SNUBBER Component Type AUG VT 96-VT;SETTING 4 1/8", S/N 438629 REJECTr'EAVY OIL RESIDUES ACTION REPORT 96-0466 GENERA/ED.

RE-EXAM-NO RECORDABLE INDICATIONS

-ACCEPTABLE.

SNUBBER WAS REPLACED.SNUBBER PROGRAM REQUIREMENTS APPLY.46

,I l lt R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas 6 Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G17.FEEDWATER LOOP A INSIDE CV (CONT.)DRAWZNGS: B-12 Summary'umber Exam Z tern Categ Number Component Component Type 601110 SN-VT FWU-5 HYDRAULIC SNUBBER AUG VT 96-VT;REJECT;IMPROPER SETTING.ACTION REPORT 96-0590 GENERATED.

SETTING ACCEPTED BY MECH'NG MEMOS SETTING 3 7/8 9 S/N 2500 10 1529 NO RECORDABLE INDICATIONS

-,ACCEPTABLE.

SNUBBER PROGRAM REQUIREMENTS APPLY.G18.FEEDWATER LOOP B INSIDE CV DRAWINGS: B-13 Summary Number Exam Item Categ Number Component Component Type 601120 SN-VT FWU-8 MECHANICAL SNUBBER AUG VT 96-VT;SETTING 2 1/4", S/N=8033, NO RECORDABLE INDICATZONS

-ACCEPTABLE.

601130 SN-VT----FWU-12 MECHANICAL SNUBBER AUG VT 96 VTr SETTING 3 1/4 9 S/N 80349 NO RECORDABLE INDICATIONS ACCEPTABLE.

G19.FEEDWATER LOOP A OUTSIDE CV DRAWINGS: B-11 Summary Number Exam Categ Item Number Component Component Type 601140 SN-VT FWU-15~MECHANICAL SNUBBER AUG VT 96 VTa SETTING 2 5/8 9 S/N 9358 9 NO RECORDABLE INDICATIONS ACCEPTABLE

~

li R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2~Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (Zf Req.)N/A B.Commercial Service Date~Jul 1970 6.National Board Number for Unit N/R ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G19~FEEDWATER LOOP A OUTSIDE CV (CONT~)DRAWINGS B-11 Summary Number Exam Categ Item Number Component Component Type Exam 601150 SN-VT FWU-17 MECHANICAL SNUBBER AUG VT 96 VTr'ETTING 4 3/4 9 S/N 93929 NO RECORDABLE

&INSZGNZFICANTf CORROSION STAINS ON PAINTED SURFACE-ACCEPTABLE.

601160 SN-VT----FWU-18 MECHANICAL SNUBBER AUG VT 96 VTr'ETTING 3 1/2 9 S/N 70679 NO RECORDABLE INDICATIONS ACCEPTABLE'01161 SN-FT----FWU-18 MECHANICAL SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE'01170 SN-VT----FWU-20 MECHANICAL SNUBBER AUG VT 96 VTr SETTING 1 3/4 r S/N 70499 NO RECORDABLE ZNDICATZONS ACCEPTABLE 601180 SN-VT----FWU-21 HYDRAULIC SNUBBER AUG VT 96-VTr SETTING 3 13/16", S/N=2500-20-38, NO RECORDABLE

&INSIGNIFICANT; FLUID LEVEL DOES NOT CORRESPOND WITH SNUBBER PISTON BY 1"-ACCEPTABLE.

601190 SN-VT FWU-23 MECHANICAL SNUBBER AUG VT 96 VTr SETTING 4 f S/N 86309 NO RECORDABLE INDICATIONS ACCEPTABLE.

R.E.GZNNA NUCLEAR POWER PLANT Inservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas 6 Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~oui 1970 S.National Board Number for Unit N/R ATTACHMENT SNUBBER PROGRAM COMPONENTS (CONT.)G19.FEEDWATER LOOP A OUTSIDE CV (CONT.)DRAWINGS: B-11 Summary Number Exam Categ Item Number Component Component Type Exam 601191 SN-FT FWU-23 MECHANICAL SNUBBER AUG FT 96-FT'UNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.601200 SN-VT----FWU-24 MECHANICAL SNUBBER AUG VT 96-VT: SETTING 3 1/32", S/N=10061, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

601209 SN-VT----FWU-26 (EAST)MECHANICAL'NUBBER AUG VT 96 VT a SETTING 3 f S/N 1 8 1 7 9 f NO RECORDABLE ZNDZCATZONS ACCEPTABLE 601210 SN-VT----FWU-26 (WEST)MECHANICAL SNUBBER AUG VT 96 VTa SETTING 3 f S/N 1 8 1 80f NO RECORDABLE INDICATIONS ACCEPTABLE G20.FEEDWATER LOOP B OUTSIDE CV DRAWINGS: HE-5 Summary Number 601220 Exam Categ SN-VT Z tern Number'omponent FWU-32 MECHANICAL SNUBBER Component Type AUG VT 96 VTr SETTING 3 1/4 f S/N=7053 f NO RECORDABLE

&ZNS IGNI FZCANTa ZD TAG BROKEN-ACCEPTABLE.

49 i V t R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G20.FEEDWATER LOOP B OUTSIDE CV (CONT.)DRAWINGS: HE-5 Summary Number Exam Item Categ Number Component Component Type NDE Exam 601230 SN-VT----FWU-38 AUG MECHANICAL SNUBBER VT 96 VT/SETTING 3 9/16/S/N 9395/NO RECORDABLE INDICATIONS ACCEPTABLE 601240 SN-VT----FWU-39 MECHANICAL SNUBBER AUG VT 96 VT!SETTING 4/S/N 9854 5 1 642 9 NO RECORDABLE INDICATZONS ACCEPTABLE 601250 SN-VT----FWU-40 MECHANICAL SNUBBER AUG VT 9 6 VT/'ETTING 3 1/2/S/N 7 0 66 9 NO RECORDABLE

&INS ZGNZ FZ CANT f BROKEN ID TAG-ACCEPTABLE.

601260 SN-VT----FWU-42 MECHANICAL SNUBBER AUG VT 96 VT/SETTING 4 1/4 9 S/N 6 1 5 9 9 NO RECORDABLE INDI CAT IONS ACCEPTABLE 601261 SN-FT----FWU-42 MECHANICAL SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.601270 SN-VT----FWU-44 HYDRAULIC SNUBBER AUG VT 96-VT;SETTING 3)/8"f S/N=G43864-02-20, NO RECORDABLE INDICATIONS ACCEPTABLE.

50

R.E.GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT.): G20.FEEDWATER LOOP B OUTSIDE CV (CONT.)DRAWINGS: HE-5 Summary Number Item Categ Number Component Component Type NDE Exam 601280=SN-VT FWU-47 MECHANICAL SNUBBER AUG VT a 96 VT SETTING 4 5/8 6 S/N 7474 9 INSIGNI FICANT ACTION REPORT 96 05 13 GENERATED FOR RIPPED BOOT-ACCEPTABLE.

601290 SN-VT----FWU-48 MECHANICAL SNUBBER AUG VT 96-VT;SETTING 4 1/2", S/N 47856 REJECTa ACTION REPORT 96 0513 GENERATED.TO ADDRESS RADIAL MOVEMENT OF SNUBBER.RE-EXAM AFTER CORRECTIONS ACCEPTABLE.

NOT SERVICE INDUCED.SNUBBER PROGRAM REQUIREMENTS APPLY.601300 SN-VT----FWU-51 AUG MECHANICAL SNUBBER VT 96-VTv SETTING 4 1/2", S/N=7483, NO RECORDABLE

&INSIGNZFZCANTf'IGEON FECES-ACCEPTABLE.

601310 SN-VT----FWU-52 MECHANICAL SNUBBER AUG VT 96 VTa SETTING 3 1/8 6 S/N 66079 NO RECORDABLE

&INSIGNIFICANT!

PIGEON FECES-ACCEPTABLE.

601320 SN-VT-"--FWU-54 MECHANICAL SNUBBER AUG VT 96 VTa SETTING 4 6 S/N 7482 6 NO RECORDABLE

&INS IGNI FICANT!PIGEON FECES ACCEPTABLE

.51 i

R.E.GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G20.FEEDWATER LOOP B OUTS1'DE CV (CONT.)DRAWINGS: HE-5 Summary Exam 1 tern Number Categ Number Component Component Type 601330 SN-VT FWU-57 MECHANICAL SNUBBER AUG VT 96 VTr SETTING 3 ACCEPTABLE.

S/N 10064/NO RECORDABLE

&ZNSIGNI FICANT/PIGEON FECES G21.MAIN STEAM LOOP A INSIDE CV DRAWINGS: B-8 Summary Number Exam Item Categ Number Component Component Type 601350 SN-VT----MSU-2 AUG MECHANICAL SNUBBER VT 9 6 VT r SETTING 3 3/4/S/N 7 0 87 9 NO RECORDABLE INDICATIONS ACCEPTABLE 601360 SN-VT----MSU-3 MECHANICAL SNUBBER AUG VT 96 VT/'ETTING 3 9 S/N 7060/NO RECORDABLE INDICATIONS ACCEPTABLE.

G22.MAIN STEAM LOOP B INSIDE CV DRAWINGS: B-8 Summary Number 601369 Exam Categ SN-VT Item Number Component SB MSU-7 (TOP/WEST)

MECHANICAL SNUBBER Component Type AUG VT 96-VT;SETTING 2 8/4", S/N=7051, NO RECORDABLE ZNDICATIONS

-ACCEPTABLE.

52

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A B.commercial Bervice Date~cul 1970 6.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G22.MAIN STEAM LOOP B INSIDE CV (CONT.)DRAWINGS: B-8 Summary Number Exam Item Categ Number Component Component Type 601370 SN-VT MSU-7 (BOTTOM/EAST)

MECHANICAL SNUBBER AUG VT 96 VT!SETTING 3 r S/N 7 047/NO RECORDABLE INDICATIONS ACCEPTABLE

~601380 SN-VT----MSU-8 HYDRAULIC SNUBBER AUG VT 96-VT'EJECT; ACTION REPORT 96-0465 GENERATED FOR INCORRECT SETTING&LACK OF 2 THREADS FOR FULL ENGAGEMENT.

RE-EXAM AFTER CORRECTIONS.

NO RECORDABLE INDICATIONS

-ACCEPTABLE.

SETTING 3", S/N=G20968130.

NOT SERVICE INDUCED.SNUBBER PROGRAM REQUIREMENTS APPLY.G23.MAIN STEAM LOOP B OUTSIDE CV DRAWINGS: B-10A Summary Number Exam Categ Item Number Component Component Type 601390 SN-VT----MSU-12 MECHANICAL SNUBBER VT 96 VT/SETTING 3 5/8 f S/N 9400/NO RECORDABLE

&INSIGNI FICANT/PIGEON FECES-ACCEPTABLE.

601399 SN-VT----MSU-13 (EAST)MECHANICAL SNUBBER AUG VT 96-VT;SETTING 3 1/8", S/N=1467, NO RECORDABLE

&INSIGNIFICANT, PIGEON FECES-ACCEPTABLE.

601400 SN-VT----MSU-13,(WEST)

MECHANICAL SNUBBER AUG VT 96-VT;SETTING 3 3/8", S/N=1464, NO RECORDABLE

&INSIGNIFICANT, PIGEON FECES-ACCEPTABLE.

53 i

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (Zf Req.)N/A S.commercial Service Date~cul 1970 S.National Board Number foe Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G23.MAIN STEAM LOOP B OUTSIDE CV (CONT.)DRAWZNGS: B-10A Summary Number Item Exam Categ Number Component Component Type 601409 SN-VT MSU-15 (NORTH)MECHANICAL SNUBBER AUG VT 96 VT SETTING 3 3/8 I S/N 7 47 6 I NO RECORDABLE

&INS I GNI FZ CANT I PIGEON FECES-ACCEPTABLE.

601410 SN-VT----MSU-15 (SOUTH)MECHANICAL SNUBBER AUG VT 96 VTS SETTING 3 7/8 6 S/N 7477 9 NO RECORDABLE

&INSIGNI FICANTs PIGEON FECES-ACCEPTABLE.

601419 SN-VT----MSU-16 (NORTH)MECHANICAL SNUBBER AUG VT 96-VT;REJECT;ACTION REPORT 96-0534 GENERATED FOR INCORRECT SETTING.SETTINGS ACCEPTABLE PER ACTION REPORT&MECH ENG MEMO.SETTINGS HOT=3 5/8", COLD=3 1/8";S/N=7481.NO RECORDABLE

&INSIGNZFZCANT-PIGEON FECES-ACCEPTABLE.

SNUBBER PROGRAM REQUIREMENTS APPLY.601420 SN-VT----MSU-16 (SOUTH)MECHANICAL SNUBBER AUG VT 96-VTS REJECT: ACTION REPORT 96-0534 GENERATED TO ADDRESS SETTING.SETTINGS ACCEPTABLE PER ACTION REPORT&MECH ENG MEMO.SETTZNGSS'OT

=4 3/16'OLD=3 3/4".S/N=7480.NO RECORDABLE

&INSIGNIFICANT-PIGEON FECES-ACCEPT.

SNUBBER PROGRAM REQUIREMENTS APPLY.601429 SN-VT----MSU-18 (NORTH)MECHANICAL SNUBBER VT 96 VTS SETTING 2 1/4 6 S/N-7478 I NO RECORDABLE

&INSZGNI FICANTs PIGEON FECES-ACCEPTABLE.

54 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G23.MAIN STEAM LOOP B OUTSIDE CV (CONT.)DRAWINGS: B-10A Summary Number 601430 SN-VT MSU-18 (SOUTH)MECHANICAL SNUBBER Item Categ Number Component Component Type AUG NDE Exam VT 96 VT r SETTING 2 1/2 9 S/N 7 1 97 6 NO RECORDABLE

&INSIGNIFICANT S PIGEON FECES-ACCEPTABLE.

601432 SN-FT----, MSU-18 (SOUTH)MECHANICAL SNUBBER AUG FT 96-FTr TEST REQUIRED DUE TO FUNCTIONAL TEST FAILURE IN 1996.SNUBBER TESTED OPERABLE.601439 SN-VT----MSU-19 (NORTH)MECHANICAL SNUBBER AUG VT 96 VTr SETTING 3 6 S/N 9369f NO RECORDABLE

&INSIGNIFICANTS PIGEON FECES ACCEPTABLE.

601440 SN-VT----MSU-19 (SOUTH)MECHANICAL SNUBBER AUG VT 96-VT;SETTING 2 7/8", S/N=9372, NO RECORDABLE

&INSIGNIFICANT

-PIGEON FECES-ACCEPTABLE.

601441 SN-FT----MSU-19 (NORTH)MECHANICAL SNUBBER AUG FT 96-FTr'UNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.601442 SN-FT----MSU-19 (SOUTH)MECHANICAL SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.55

,

R.E~GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Znterval, Second Period, Fourth Outage (1996)l.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (Zf Req.)N/A 5.Commercial Service Date~cul 1970 6.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT.)G23.MAZN STEAM LOOP B OUTSZDE CV (CONT.)DRAWINGS: B-10A Summary Number Item Categ Number Component Component Type NDE Exam 601450 SN-VT MSU-22 MECHANICAL SNUBBER AUG VT 96 VTa SETTING 2 1/8 f S/N 9357 9 NO RECORDABLE

&INSZGNI FZCANTf PIGEON FECES-ACCEPTABLE.

601451 SN-FT----MSU-22 MECHANICAL SNUBBER AUG 96-FTr FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.601460 SN-VT----MSU-25 MECHANICAL SNUBBER VT 96-VT;SETTING 1 3/4", S/N=1465, NO RECORDABLE

&INSIGNIFICANT, PIGEON FECES-ACCEPTABLE.

601469 SN-VT----MSU-26 (TOP)MECHANICAL SNUBBER AUG VT 96-VT;SETTING 5", S/N=9355, NO RECORDABLE

&INSIGNIFICANT, PIGEON FECES ACCEPTABLE..

601470 SN-VT----MSU-26 (BOTTOM)AUG VT MECHANICAL SNUBBER 9 6 VT r SETTING 4 3/4 f S/N 468 69 NO RECORDABLE

&INS IGNI FZ CANT 9 PIGEON FECES-ACCEPTABLE.

601480 SN-VT----MSU-27~MECHANICAL SNUBBER AUG VT 96-VT;SETTING 1", S/N=9398, NO RECORDABLE

&INSIGNIFICANT, PIGEON FECES ACCEPTABLE.

56

,l R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G23.MAIN STEAM LOOP B OUTSIDE CV (CONT.)DRAWINGS: B-10A Summary Number Exam Item Categ Number Component Component Type 601490 SN-VT----MSU-29 AUG VT MECHANZCAL SNUBBER 96-VT;SETTING 4 1/4", S/N=1469, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

601500 SN"VT----MSU-31 MECHANICAL SNUBBER AUG VT 96 VTr'ETTING 2 1/2 9 S/N 93569 NO RECORDABLE INDICATIONS ACCEPTABLE 601510 SN-VT----MSU-32 MECHANICAL SNUBBER AUG VT 96-VTr'ETTING 2 3/8", S/N=1093, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

G24.MAIN STEAM LOOP A OUTSIDE CV DRAWINGS: B-9A Summary Number 601520 Exam Ztem Categ Number Component SN-VT----MSU-38 MECHANICAL SNUBBER Component Type AUG NDE Exam VT 96 VTr SETTING 1 5/8 9 S/N 1 0 90 f NO RECORDABLE INDI CAT IONS ACCEPTABLE 601530 SN-VT----MSU-39 MECHANICAL SNUBBER AUG VT 96 VT SETTING 4 3/4 9 S/N 10879 NO RECORDABLE INDICATIONS ACCEPTABLE

~601540 SN-VT----MSU-40 MECHANICAL SNUBBER AUG VT 96-VTa SETTING 4 5/8", S/N=1080, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

57

R.E.GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G24.MAIN STEAM LOOP A OUTSIDE CV (CONT.)DRAWINGS: B-9A Summary Number Exam Categ Item Number Component Component Type Exam 601550 SN-VT MSU-44 MECHANICAL SNUBBER AUG VT 96 VT SETTING 3 1/8 9 S/N 1 4 68 f NO RECORDABLE

&INSIGNI FICANTf SNUBBER SCALE HAS PAINT OVERSPRAY,-ACCEPTABLE.

G25.MAIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS: B-10 Summary Number Exam Item Categ Number Component Component Type 601560 SN-VT MSU-55 MECHANICAL SNUBBER AUG VT 96-VT;REJECT;ACTION REPORT 96-0518 GENERATED.

SNUBBER INSTALLED BACKWARDS.

DCR'S 96-0146/0147 GENERATED, DRAWING TO BE CHANGED TO REFLECT CONFIGURATION.

NO RECORDABLE INDICATIONS

-ACCEPTABLE.

SETTING 2 3/4", S/N=18195.601570 SN-VT----MSU-57 MECHANICAL SNUBBER AUG VT 96 VTa SETTING 3 1/4 f S/N 271829 NO RECORDABLE ZNDZCATIONS ACCEPTABLE.

601571 SN-FT----MSU-57 MECHANICAL SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED DUE TO FAILURE IN 1995.SNUBBER TESTED OPERABLE.58 I: li 0 I R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G26.MAIN STEAM LOOP A ATMOSPHERIC VENT DRAWINGS: B-9A Summary Number mar-ra 601580 Exam Item Categ Number Component KKKBBDKK BB BB BBR~ÃKRR R K RK BB Component Type SN-VT----MSU-58 AUG MECHANICAL SNUBBER VT 96 VTa SETTING 3 1/8 f S/N 181879 NO RECORDABLE INDICATIONS ACCE PTABLE.601581 SN-FT----MSU-58 MECHANICAL SNUBBER AUG FT 96-FT FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.601590 SN-VT----MSU-60 MECHANICAL SNUBBER AUG VT 96-VT;SETTING 2 1/2", S/N=18197, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

G27.MAIN STEAM LOOP B TO AUX FW PUMP TURBZNE DRAWINGS: C-32 Summary Number Exam Item Categ Number Component BB BBM MBB Component Type NDE Exam 601600 SN-VT----MSU-72 AUG MECHANICAL SNUBBER VT 96 VTa SETTING 1 5/8 f S/N 1 57 67 9 NO RECORDABLE INDI CATIONS ACCEPTABLE

~601601 SN-FT----MSU-72 MECHANICAL SNUBBER AUG FT 96-FT'UNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.59 j~

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (Zf Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT".)G27.MAIN STEAM LOOP B TO AUX FW PUMP TURBINE (CONT.)DRAWINGS: C-32 Summary Number Exam Item Categ Number Component Component Type 601610 SN-VT MSU-74 MECHANICAL SNUBBER AUG VT 96 VT SETTING 3 1/4 f S/N 100669 NO RECORDABLE INDICATIONS ACCEPTABLE

~G28.MAIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS'-10 Summary Number 601620 SN-VT MSU-75 MECHANICAL SNUBBER Item Categ Number Component Component Type AUG VT 9 6 VT r SETTZNG 2 9 S/N 8 030 9 NO RECORDABLE I NDI CAT ZONS ACCEPTABLE a G29.MAIN STEAM LOOP A TO AUX FW PUMP TURBINE DRAWINGS: C-32 Summary Number 601630 Exam Item Categ Number~BB MBBM SN-VT Component MSU-78 MECHANICAL SNUBBER Component Type AUG VT 9 6 VT e SETT I NG 3 9 S/N 8 57 9 9 NO RECORDABLE INDICATIONS ACCEPTABLE 601640 SN-VT----MSU-80 MECHANICAL SNUBBER AUG VT 96-VT;SETTING 2 1416", S/N.=18181, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

60 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT.): G29.MAIN STEAM LOOP A TO AUX FW PUMP TURBINE (CONT.)DRAW1NGS: C-32 Summary Number Exam Categ SN Item Number Component Component Type a ar a agama=am NDE Exam 601650 SN-VT MSU-82 MECHANICAL SNUBBER VT 96 VTa SETTING 2 7/8 f S/N 157689 NO RECORDABLE INDICATIONS ACCEPTABLE.

601659 SN-VT----MSU-84 (EAST)MECHANICAL SNUBBER AUG VT 96 VT SETTING 2 1/2 f S/N 101089 NO RECORDABLE INDICATIONS ACCEPTABLE.

601660 SN-VT----MSU-84 (WEST)MECHANICAL SNUBBER AUG VT 96 VTf SETTING 2 1/8 f S/N-101419 NO RECORDABLE INDICATIONS ACCEPTABLE.

601670 SN-VT----MSU-85 MECHANICAL SNUBBER AUG VT 96-VTr'ETTING 3 1/4", S/N=10074, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

G30.6-ZN.RESZD HT REMOVAL TO RPV (LHSZ)DRAWINGS: B-17 Summary Number 601680'RKKKKSSSN BBRSBS RBSR SN-VT RHU-8 MECHANICAL SNUBBER Exam Item Categ Number Component Component Type MSB AUG NDE Exam VT 96-VT: SETTING 2 1/2", S/N=15755, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

61

/

R.E.GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519 3.Plant Unit 1 4.O~ner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G31.RESIDUAL HEAT REMOVAL FROM LOOP A HOT LEG DRAWINGS: A-15 Summary Number Exam Item Categ Number Component Component Type NDE Exam 601690 SN-VT----RHU-30 AUG MECHANICAL SNUBBER VT 96-VTf SETTING 1 1/16", S/N=7065, NO RECORDABLE INDICATIONS ACCEPTABLE.

601700 SN-VT----RHU-33 MECHANICAL SNUBBER AUG VT 96-VT;SETTING 3 1/8".S/N=7064, REJECT: SNUBBER LOCK NUT WRONG WIDTH ACCEPTABLE PER MECH ENG MEMO, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

SNUBBER PROGRAM REQUIREMENTS APPLY.G32.RESIDUAL HEAT REMOVAL LZNE 8B-AC-601 DRAWINGS: B-23 Summary Number 601710 Exam Item Ca teg Number SN-VT Component RHU-36 MECHANICAL SNUBBER Component Type AUG VT 96 VTr SETT ING 2 1/2 9 S/N 1 57569 NO RECORDABLE I NDI CATIONS ACCEPTABLE

~G33.RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS'-25 Summary Number 601720 96 Exam Item Categ Number Component SN-VT----RHU-51 MECHANICAL SNUBBER-VT;SETTING 2 3/8", S/N=15752, NO Component Type AUG VT RECORDABLE INDICATIONS

-ACCEPTABLE.

62

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 B.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G33.RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG (CONT.)DRAWZNGS: '-25 Summary Number Exam Item Categ Number Component Component Type 601730 SN-VT----RHU-53 AUG MECHANICAL SNUBBER VT 96 VTa SETTING 2 5/8 f S/N 15754 f NO RECORDABLE INDICATIONS ACCEPTABLE G34.RESIDUAL HEAT REMOVAL LZNE 6D-AC-601 DRAWINGS: B-26 Summary Number Ztem Categ Number Component Component Type NDE Exam 601740 SN-VT----RHU-61 AUG MECHANICAL SNUBBER VT 96 VT SETTING 2 3/8 f S/N 1 5733 f NO RECORDABLE INDI CATIONS ACCEPTABLE

~G35.RESIDUAL HEAT REMOVAL LINE 10E-AC-601 DRAWINGS: B-20 Summary Number 601749 Exam'Categ SN-VT Item Number Component RHU-63 (NORTH)MECHANICAL SNUBBER Component Type AUG mt NDE Exam VT 96 VTa SETTING 2 3/4 f S/N 16380f NO RECORDABLE INDICATIONS ACCEPTABLE 601750 SN-VT----RHU-63 (SOUTH)MECHANICAL SNUBBER AUG VT 96-VT: SETTING 2 15/16", S/N=16375, NO RECORDABLE INDICATIONS ACCEPTABLE.

63

'

R.E.GINNA NUCLEAR POWER PLANT Inservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G36.RESIDUAL HEAT REMOVAL LINE 10G-AC-601 DRAWINGS: B-20A Summary Number Exam Item Categ Number Component Component Type NDE Exam 601760 SN-VT----RHU-69 MECHANICAL SNUBBER AUG VT 96 VT SETTZNG 2 1/4/S/N 8 62 9/NO RECORDABLE INDICATIONS ACCEPTABLE

~601769 SN-VT----RHU<<71 (NORTH)MECHANICAL SNUBBER AUG VT 96 VT/SETTING 2 7/16/S/N 1 1466/NO RECORDABLE INDICATIONS ACCEPTABLE

~AUG 601770 SN-VT----RHU-71 (SOUTH)VT MECHANICAL SNUBBER 96-VT/SETTING 2 1/2", S/N=11465, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

G37.RHR PUMP A SUCTION LINE DRAWINGS: B-20A Summary Number 601780 Exam Item Categ Number SN-VT Component RHU-72 MECHANICAL SNUBBER Component Type AUG VT 96 VTJ SETTING 3 1/8/S/N 8606/NO RECORDABLE INDICATIONS ACCEPTABLE 64

R."E.GINNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649.2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G38.RESIDUAL HEAT REMOVAL LINE 10D-AC-601 DRAWZNGS: B-20 Summary Number Item Categ Number Component Component Type Exam 601790 SN-VT RHU-75 MECHANICAL SNUBBER AUG VT 96 VTa SETTING 3 7/1 6 9 S/N 8632 9 NO RECORDABLE

&INS IGNI FICANTS LIGHT CORROSION, MEDIUM TO HEAVY RUST ON BASE PLATE&FLOOR.T/C GENERATED AFTER CLEAN UP-ACCEPTABLE'39.

RESIDUAL HEAT REMOVAL LINE 6K-AC-151 DRAWINGS: B-21 Summary Number 601800 Exam Categ SN-VT Item Number Component RHU-92 MECHANICAL SNUBBER Component Type SN AUG VT 96 VT SETTING 2 1/4 9 S/N 163769 NO RECORDABLE

&INSIGNI FICANTS DRY BORIC ACID RESIDUE ON BASE PLATE~T/C GENERATED.

AFTER CLEAN UP-ACCEPTABLE.

G40.H.P.SAFETY INJECTION LINE FROM RWST DRAWINGS'-1 9 Summary Number Exam Item Categ Number Component Component Type 601810 SN-VT----RHU-109 AUG MECHANICAL SNUBBER VT 96-VT;SETTING 2 1/8", S/N=11463, NO RECORDABLE INDICATIONS

-ACCEPTABLE'01811 SN-FT--RHU-109MECHANiCAL SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.65 l

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A 5.Commercial Service Date~cul 1970 B.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G40.H.P.SAFETY INJECTION LINE FROM RWST (CONT.)DRAWINGS: B-19 Summary Number Item Categ Number Component Component Type 601820 SN-VT RHU-110 AUG MECHANZCAL SNUBBER NDE Exam VT 96-VTr SETTING 2 3/16", S/N=16373, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

G41.H.P.SAFETY INJECTION PUMP A SUCTION LZNE DRAWZNGS: B-16B Summary Number Exam, Z tern Categ Number Component Component Type 601830 SN-VT-;--RHU-119 AUG MECHANICAL SNUBBER VT 96 VTr SETTING 1 3/4 9 S/N 1 57 66 9 NO RECORDABLE ZNDI CAT IONS ACCEPTABLE

~G42.H.P.SAFETY INJECTION LINE 8 J-SZ-151 DRAWINGS B-19 Summary Number Exam Item Categ Number Component SS SS SS SS SS rS rS SSRRSSSS SS Component Type MSSSSSS SS SS 601840 SN-VT RHU-123 MECHANICAL SNUBBER AUG VT 96-VTr'ETTING 2 1/2", S/N=15765, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

601841 SN-FT----RHU-123 MECHANICAL SNUBBER AUG FT 96-FTr FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.v'6 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (Zf Req.)N/A S.commercial Service Date~Cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G43.H.P.SAFETY INJECTION LZNE TO LOOP A COLD LEG DRAWINGS: A-17 Summary Number Exam Item Categ Number Component Component Type 601850 SN-VT----SIU-3 AUG VT MECHANICAL SNUBBER 96-VT;SETTING 3 3/16", S/N=8614, NO RECORDABLE

&INSIGNIFICANT, NO ID TAG-ACCEPTABLE.

G44.H.P.SAFETY ZNJECTZON LINE TO LOOP B COLD LEG DRAWINGS: A-1 6 Summary Number Exam Item Categ Number Component Component Type 601860 SN-VT SZU-47 MECHANICAL SNUBBER AUG VT 96-VT;SETTING 3", S/N=15349, NO RECORDABLE INDZCATIONS

-ACCEPTABLE.

G45.RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: A-14 Summary Number 601870 Item Categ Number Component Component Type aa a ann f a SN-VT----SIU-52 AUG MECHANICAL SNUBBER NDE Exam VT 96 VTa SETTING 2 1/2 f S/N 15348f NO RECORDABLE INDICATIONS ACCEPTABLE.

G46.SVC.WTR.-TO A&B DIESEL GEN.WTR.COOLERS DRAWINGS: C-13 Summary Number 601890 SN-VT~SWU-254 MECHANICAL SNUBBER Item Categ Number Component Component Type AUG NDE Exam VT 96 VTr SETTING 1 1/8 f S/N 12508 f NO RECORDABLE INDICATIONS ACCEPTABLE

~67 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A B.commercial Service Date~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT~): G47.SERVICE WATER LZNE 8L-SW-125 DRAWZNGS: B-SOA Summary Number Item Categ Number Component Component Type 601900 SN-VT SWU-308 MECHANICAL SNUBBER AUG VT 96 VTr SETTING 2 7/8 9 S/N 803 1 f NO RECORDABLE INDICATIONS ACCEPTABLE 601910 SN-VT----SWU-309 MECHANICAL SNUBBER AUG VT 96 VTr SETTING 3 3/8 9 S/N 100739 NO RECORDABLE INDICATIONS ACCEPTABLE G48.SVC.WTR.-INTMD.BLDG.

16" HD.TO PEN 312-320 DRAWZNGS: C-16B Summary Number Item Categ Number Component Component Type Exam 601920 SN-VT----SWU-370 MECHANICAL SNUBBER AUG VT 96 VTr SETTING 2 1/8 9 S/N 1 14649 NO RECORDABLE INDICATIONS ACCEPTABLE G49.STANDBY AUX FW THRU PEN 123 TO B S/G FWHD ZNCV DRAWZNGS: C-24 Summary Number aaaBBaBB 601930 Exam 1 tern Categ Number Component aaaaaaa aaaaa a aaanmaa anna aaaaaaaaaaa SN-VT----AFU-205 (AFW-10)HYDRAULIC SNUBBER Component Type AUG VT 96 VTr SETTING 3 3/1 6 9 S/N 154039 NO RECORDABLE

&ZNSIGNZ FICANTf FLUID LEVEL APPROX.70't-ACCEPTABLE.

68 R.E.GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (Zf Req.)N/A 6.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G49.STANDBY AUX FW THRU PEN 123 TO B S/G FWHD INCV (CONT.)DRAWINGS: C-24 Summary Number Exam Item Categ Number Component Component Type m 601940 SN-VT AFU-208 (AFW-13)HYDRAULIC SNUBBER AUG VT 96 VTS SETTING 1 25/32 f S/N 12902 9 NO RECORDABLE INDICATIONS ACCEPTABLE.

601941 SN-FT----AFU-208 (AFW-13)HYDRAULIC SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED DUE TO FAILURE IN 1995.SNUBBER FAILED FUNCTIONAL TEST.SNUBBER REPLACED.SNUBBER TO BE TESTED IN 1997.GSO.STANDBY AUX FW THRU PEN 119 TO A S/G FWHD INCV DRAW1NGS: C-20 Summary Number Item Exam Categ Number Component Component Type 601970 SN-VT AFU-224 (AFW-28)HYDRAULIC SNUBBER AUG VT 96-VT;SETTING 2 1/2", S/N=12906, NO RECORDABLE

&INSIGNIFICANT, FLUID LEVEL 3/4 FULL-ACCEPTABLE.

601971 SN-FT----AFU-224 (AFW-28)HYDRAULIC SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED DUE TO FAILURE IN 1995.SNUBBER FAILED FUNCTIONAL TEST.SNUBBER WAS RE-BUILT.SNUBBER WILL BE TESTED IN 1997.601980 SN-VT----AFU-226 (AFW-27)HYDRAULIC SNUBBER AUG VT f'6-VT;REJECT;ACTION REPORT 96-0443 GENERATED DUE TO SETTINGS.SETTINGS ACCEPTABLE PER ACTION REPORT&MECH ENG MEMO.SETTINGS HOT=3 5/16'OLD=3 3/4", S/N=12901, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

SNUBBER PROGRAM REQUIREMENTS APPLY.69 R.E.GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A B.Commercial service Date~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G50.STANDBY AUX FW THRU PEN 119 TO A S/G FWHD ZNCV (CONT.)DRAWINGS: C-20 Summary Number 601981 SN-FT AFU-226 (AFW-27)HYDRAULIC SNUBBER Item Categ Number Component NDE Component Type Exam AUG FT 96-FTa FUNCTIONAL TEST REQUIRED DUE TO SCOPE EXPANSZON FUNCTZONAL TEST FAILURE OF AFU-229.SNUBBER TESTED OPERABLE., 601990 SN-VT----AFU-225 (AFW-29)HYDRAULIC SNUBBER AUG VT 96 VTt SETT1NG 1 3/4 6 S/N 129069 NO RECORDABLE

&INSIGNI FICANTf FLUID LEVEL APPROX.60%-ACCEPTABLE.

602000 SN-VT----AFU-227 (AFW-31)MECHANICAL SNUBBER AUG VT 96 VTa SETTING 4 1/8 9 S/N 25594, NO RECORDABLE INDICATIONS

-ACCEPTABLE

~602001 SN-FT----AFU-227 (AFW-31)MECHANICAL SNUBBER AUG FT 96-FTa FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.G51.PRESS.RELIEF PM PRESS.TO RELIEF MANIFOLD DRAWINGS: S-2 Summary Number SOSSSS 602010 Exam Z tern Categ Number Component SN-VT----N601 HYDRAULIC SNUBBER Component Type AUG VT 96-VT;REJECT;ACTION REPORT 96-0285 GENERATED FOR LEAKING OZL&LOOSE NUT.ADJUSTMENTS MADE&OIL CLEANED.'E-EXAM; NO RECORDABLE INDICATIONS ACCEPTABLE.

SETTING 3 9/16" S/N=6565.SNUBBER PROGRAM REQUIREMENTS APPLY.70 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519 3.Plant Unit 1-4.Owner Certificate of Authorization (Zf Req.)N/A 5.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G51.PRESS.RELIEF FM PRESS.TO RELIEF MANIFOLD (CONT.)DRAWINGS: S-2 Summary Number Exam Categ Ztem Number Component Component Type 602020 SN-VT----N602 HYDRAULIC SNUBBER AUG VT 96 VTr SETTING 2 7/16 f S/N 65686 NO RECORDABLE

&INSIGNIFICANTS FLUID LEVEL 3/4 FULL-ACCEPTABLE.

602030 SN-VT----N604 HYDRAULIC SNUBBER AUG VT 96 VTa SETTING 1 3/4 6 S/N 65666 NO RECORDABLE

&ZNSIGNZFICANTS FLUID LEVEL 1/2 FULL-ACCEPTABLE.

602040 SN-VT----N605 HYDRAULIC SNUBBER AUG VT T 96 VTr SETTING 2 3/4 f S/N 6561 6'O RECORDABLE

&INSZGNI FICANTS FLUZD LEVEL AT LEAST 1/2 FULL-ACCEPTABLE.

602050 SN-VT----N607 HYDRAULIC SNUBBER AUG VT 96 VTS SETTING 3 3/4 f S/N 65629 NO RECORDABLE

&INSIGNIFICANTS FLUID LEVEL 1/2 FULL-ACCEPTABLE.

602060 SN-VT----N608 HYDRAULIC SNUBBER AUG VT 96-VTa RE JECTa ACTION REPORT 96-0287 GENERATED FOR LEAKING OIL.RE-EXAM AFTER REPAIRS.NO RECORDABLE INDICATIONS

-ACCEPTABLE.

SNUBBER PROGRAM REQUIREMENTS APPLY.71 P'

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report, 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner Rochester Gas&Electric Cor.,89 East Ave.Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G51.PRESS.RELIEF FM PRESS.TO RELZEF MANIFOLD (CONT.)DRAWINGS: S-2 Summary Number Exam Item Categ Number Component Component Type 602070 SN-VT N615 HYDRAULIC SNUBBER AUG VT 96-VT;REJECT;ACTION REPORT 96-0283 GENERATED TO ADDRESS LEAKING OIL.OIL COMING FROM VENT-USE AS IS.NO RECORDABLE

&INSIGNIFICANT, FLUID LEVEL 1/2 FULL-ACCEPTABLE.

SETTING 2 3/8", S/N=6564.SNUBBER PROGRAM REQUIREMENTS APPLY.602080 SN-VT----N616 HYDRAULIC SNUBBER AUG VT 96-VT;REJECT'CTZON REPORT 96-0621 GENERATED FOR SETTING.SETTINGS ACCEPTABLE PER ACTION REPORT&MECH ENG MEMO.NO RECORDABLE

&INSIGNIFZCANTS FLUID LEVEL 1/2 FULL ACCEPTABLE'ETTINGS HOT 3 5/8 COLD 3 1/4 9'S/N 18193'NUBBER PROGRAM REQUIREMENTS APPLY'02081 SN-FT----N616 AUG HYDRAULIC SNUBBER FT 96-FT;FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE, SNUBBER WAS REPLACED'52.

POWER PRESS.RELIEF LINE DRAWINGS: S-1 Summary Number Item Categ Number Component Component Type 602090 SN-VT BB PS-2 HYDRAULIC SNUBBER AUG VT 96 VT SETTING 4 i/8 9 S/N, PD 87239 12449 NO RECORDABLE

&INSIGNI FICANTr FLUID LEVEL 1/8" RED SHOWING-ACCEPTABLE.

72 R.E.GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)G52.POWER PRESS.RELIEF LINE (CONT.)DRAWINGS: S-1 Summary Number Item Categ Number Component Component Type Exam 602100 SN-VT PS-4 HYDRAULIC SNUBBER AUG VT 96 VTS SETTING 1 3/16 9 S/N PD 86144 1 152 f NO RECORDABLE

&ZNSZGNI FICANTS FLUID LEVEL 1/8 RED SHOWING 3/8 GREEN-ACCEPTABLE.

G53.3-IN.PRESSURIZER RELIEF LINE DRAWINGS: A-12 Summary Number Item Categ Number Component Component Type NDE Exam 602110 SN-VT PS-5 HYDRAULIC SNUBBER AUG VT 96 VTr SETTING 2 3/4 f S/N PD 87238 12469 NO RECORDABLE

&INSIGNIFICANT/

FLUID LEVEL 3/16 RED 1/8 GREEN-ACCEPTABLE.

602120 SN-VT----PS-6 HYDRAULIC SNUBBER AUG VT 96 VTS SETTING 3 1/2 f S/N PD 87767 1239f NO RECORDABLE

&INSIGNZFICANTS FLUID LEVEL 5/8 RED 1/16 GREEN-ACCEPTABLE.

602121 SN-FT----PS-6 HYDRAULIC SNUBBER AUG FT 96-FT FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE..602130 SN-VT----PS-8 HYDRAULIC SNUBBER AUG VT 96 VTS SETTING 2 7/8 f S/N PD 86144 1 1599 NO RECORDABLE

&INSIGNI FICANTJ FLUID LEVEL 1/16 GREEN 1/4 RED-ACCEPTABLE.

73 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G54.POWER PRESS.RELIEF LINE DRAWZNGS: S-1A Summary Number Exam Categ Item Number Component Component Type Exam 602140 SN-VT PS-9 HYDRAULIC SNUBBER AUG VT 96-VT;REJECT;ACTION REPORTS 96-0282&96-0685 GENERATED FOR SETTINGS&NOTIFICATION PROBLEM.RE-EXAM AFTER CORRECTION

-ACCEPTABLE.

SETTINGS ACCEPTABLE PER MECH ENG MEMO.SETTING 3 3/4", S/N=PD 86144-1154.

SNUBBER PROGRAM REQUIREMENTS APPLY.602150 SN-VT----PS-10 HYDRAULIC SNUBBER AUG VT 96-VT;SETTING 3 7/8", S/N=PD 86144-1157, NO RECORDABLE

&INSIGNIFICANT, FLUID LEVEL 1/32 GREEN 1/4 RED-ACCEPTABLE.

602160 SN-VT----'S-11 HYDRAULIC SNUBBER AUG VT 96 VTr'ETTING 2 3/8 9 S/N PD 86144 1 1569 NO RECORDABLE

&INSZGNIFICANTS FLUID LEVEL 1/4 RED 1/8 GREEN-ACCEPTABLE.

G55.SEAL WATER RETURN FROM RCP-B DRAWINGS: S-3 Summary Number 602200 SN-VT CVU-131 MECHANICAL SNUBBER Exam Item Categ Number Component Component Type AUG VT 9 6 VT SETTING 2 1/2 9 S/N 25432 9 NO RECORDABLE INDICATIONS ACCE PTABLE 602201 SN-FT----CVU-131 MECHANICAL SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.TESTED OPERABLE.74 e

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.commercial Service Date~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I I SNUBBER PROGRAM COMPONENTS (CONT.)G55.SEAL WATER RETURN FROM RCP-B (CONT.)DRAWINGS: S-3 Summary Number 602300 Exam Item Categ Number Component Component Type SN-VT----CVU-550 AUG MECHANICAL SNUBBER NDE Exam VT 96-VT;SETTING 2 1/4", S/N=18190, NO RECORDABLE INDICATIONS

-ACCEPTABLE.

G56.STANDBY AUX FW THRU PEN 123 TO B S/G FWHD ZNCV DRAWINGS: C-24 Summary Number Exam Categ 602400 SN-VT Item Number Component AFU-209 HYDRAULIC SNUBBER Component Type AUG NDE Exam VT 96 VTa SETTING 2 5/1 6 9 S/N 12904 9 NO RECORDABLE

&INSZGNZ FICANTS FLUID LEVEL 20%, W/0 TO BE GENERATED TO ADD OIL TO RESERVOIR-ACCEPTABLE.

G57.STANDBY AUX FW THRU PEN 119 TO A S/G FWHD ZNCV DRAWINGS C-20 Summary Number 602500 Exam Categ SN-VT Item Number Component AFU-229 HYDRAULIC SNUBBER Component Type AUG VT 96-VT: REJECT;ACTION REPORT 96-0432 GENERATED DUE TO SETTING.SETTINGS OK PER ACTION REPORT.NO RECORDABLE

&INSZGNZFICANT, FLUID LEVEL 1/2 FULL ACCEPTABLE'ETTINGSS HOT 4 1/8 f COLD 2 13/16 9 S/N 12900 SNUBBER PROGRAM REQUIREMENTS APPLY.75 0'

R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor., 89 East Ave., Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (Zf Req.)N/A S.commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.): G58.STANDBY AUX FW THRU PEN 119 TO A S/G FWHD ZNCV DRAWINGS: C-20 Summary Exam Number Categ Item Number Component Component Type Exam 602501 SN-FT AFU-229 HYDRAULIC SNUBBER AUG FT 96-FT;FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM.SNUBBER FAILED FUNCTIONAL TESTS SCOPE EXPANSION REQUIRED TO INCLUDE AFU 2269 SNUBBER WAS REPLACED, SNUBBER WILL BE FUNCTIONAL TESTED IN 1997.H.SEZSMZC SUPPORTS: H1 CVCS LETDOWN S PEN 1 12 TO REG HT~EXCH~DRAWINGS: B-32 Summary Number 700100 Exam Categ SS-CS Item Number Component~F1.20R CVU-84 GUIDE&INTEGRAL ATTACHMENT Component Type OE VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

H2.MAZNSTEAM DRAWINGS: B-9A Summary Number 700450 Exam Categ 245SBRRBBQ SS-CS Ztem Number Component*F1.20R MSU-59 RIGID SUPPORT&INTEGRAL ATTACHMENT Component Type OE VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

76 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner Rochester Gas&Electric Cor.,89 East Ave.,Rochester NY 14649 2.Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z SEISMIC SUPPORTS (Cont.)H2.MAZNSTEAM (CONT.)DRAWINGS: B-9A Summary Number Exam Categ Item Number Component Component Type Exam 700500 SS-CS*F1.20R MSU-54 RIGID SUPPORT&INTEGRAL ATTACHMENT VT 96 VT f NO RECORDABLE

&INSIGNE FZCANTf LOCKNUTS OBSERVED TO BE LOOSE 9 ADJUSTMENTS MADE 6 NOT SERVICE INDUCEDf SEE 1 994 RESULTS&NCR94 0606 ACCEPTABLE.

700530 SS-CS*F1.20R MSU-49 RIGID SUPPORT&INTEGRAL ATTACHMENT OE VT 96 VTf NO RECORDABLE

&INS I GNZ FI CANT f NE BASE PLATE IS LOOSE f IAW NCR9 4 0 64 9 ATTACHMENT 1 f ITEM 2 f LATERAL RESTRAINT IS NOT REQUIRED ACCEPTABLE

~H3.S/G BLOWDOWN FROM PEN 322&321 TO N/C PIPING DRAWINGS: SS-3 Summary Number Item Categ Number Component Component Type 700680 SS-CS*F1.20A BDU-23 AUG ANCHOR&INTEGRAL ATTACHMENT VT 96-VTf'O RECORDABLE INDICATIONS

-ACCEPTABLE.

700700 SS-CS*F1.20A BDU-27 ANCHOR&INTEGRAL ATTACHMENT OE VT 96-VT;NO RECORDABLE INDICATIONS

-ACCEPTABLE.

77 R.E.GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner Rochester Gas&Electric Cor.89 East Ave.,Rochester NY 14649"2.Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 3.Plant Unit 1 4.Owner Certificate of Authorization (If Req.)N/A S.Commercial Service Date~Jul 1970 S.National Board Number for Unit NIA ATTACHMENT I SEISMIC SUPPORTS (Cont.): 84.SAFETY ZNJECTZON SYSTEM DRAWINGS: A-17 Summary Number Item Categ Number Component Component Type 700710 SS-CS*F1.20R SIU-8 RIGID SUPPORT AUG VT 96-VT;REJECT, ACTION REPORT 96-0445 GENERATED FOR FOREIGN MATERIAL BETWEEN PIPE&SUPPORT USE AS IS PER ACTION REPORTS DRAWING TO BE REVISED TO INCLUDE THIS MATERIAL.NO RECORDABLE INDICATIONS

-ACCEPTABLE.

f 78 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As R uired b the Provisions of the ASME Code Section XI 1.0wnerRochester Gas&Electric Cor Date 13 Se tember 1996 89 East Ave., Rochester, NY 14649 Sheet 1 2.Plant R.E.Ginna Nuclear Power Plant Unit of 27 1503 Lake Road, Ontario NY 14519 Address (*)Repair Organization P.O.No.~Job No., etc.3.Work Performed by Name (*)Type Code Symbol Stamp Authorization No.N/A N/A 4.Identification of System (*)Address (*)Expiration Date N/A E.(a)Applioaeledonarrnoaon Code~19~Edidon~Addenda,~Code dana (b)Applicable Edition of Section XI Utilized for Repairs or Replacements 1 gpss 6.Identi%cation of Components Repaired or Replaced and Replacement Components Name of Com nent Name of Manufacturer Manufacturer Serial No.National Board No.Other Identification Year Build Repaired Replaced or Re lacement ASME Code.Stamped (Yes or No 7.Description of Work 8.Tests Conducted:(')

Hydrostatic C)Pneumatic 0 Nominal Operating Pressure 0 Other 0 Pressure psi Test Temp.'F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1)size is 8-1/2 In.x 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3)each sheet is numbered and the number of sheets is recorded at the top of this form.(')See"ATTACHMENT II" FOR APPLICABLE INFORMATION (12/82)This Form (E00030)may be obtained from the Order Dept., ASME, 345 E.47th St., New York, N.Y.10017 1

FORM NIS-2 (Back)9.Remarks Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this" conforms to the rules of the ASME Code,Section XI.repair or replacement Type Code Symbol Stamp Certificate o Autho'tion No.Signed Ovmer or Ovm r's Designee, Title N/A Expiration Date NIA FA Kle ki I I n in r Dae Se mb r CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by of have inspected the components described in this Owner's Report during the period*~M 9'to xo 4 , and state that to the best of my knowledge and belief, the Ovmer has performed examinations and taken corrective measures described in this Owner's Report in accordance viith the inspection plan and as required by the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Inspector's Signature Date tg 5'~Commissions National Board, State, Province, and Endorsements

(')See"ATTACHMENT II" FOR APPLICABLE INFORMATION

(-)Repair, Replacement or Modification as identified within"ATTACHMENT II" R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Oavner: V 4 4 2.Plant: R,E, Ginna Nuclear Popover Plant 1503 Lake Rd.Ontario.14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

"'EPAIR, REPLACEMENT and MODIFICATION PROGRAM The Repair, Replacement and Modification (RR&M)Program, as identified within the"Inservice Inspection (ISI)Program", identifies component jurisdiction and associated requirements.

Applicable Repair, Replacement or Modification activities have been performed in accordance with ASME Section XI Code, 1986 edition, no addenda.When an item under the rules and requirements of the"Inservice Inspection (ISI)Program" is found deficient, an Engineering"use-as-is" evaluation may result.This determination is indicated within the ISI Program Summary,"Attachment I", for the applicable component within this report.If the deficiency results in a Code Repair, Replacement or Modification; the deficiency will be classified as one of three category types.These category types shall consist of a"Code Service Induced Rejectable Indication", a"Code Rejectable Indication" and a"Corrective Action Activity".

A"Code Service Induced Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be"Service Induced"."Service Induced" indications, stemming from Inservice Inspection Examinations (ISI), shall require additional expanded examinations.

The associated expanded examinations shall be performed in accordance to the requirements of the ASME Section XI Code.A"Code Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be not"Service Induced".This category includes but is not limited to items such as welding discontinuities from a modification identified during ISI preservice examinations or component damage caused by human involvement.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner:~.e V 4 2.Plant: R E Ginna Nuclear Power lant 1503 La!e Rd.ntario.45 9 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda'TTACHMFNT II F A"Corrective Action Activity" may occur when a component under the RR&M Program requires corrective action.This corrective action may be a result from a maintenance operation that identifies a need to perform a Code Repair, Replacement or Modification.

This category includes but is not limited to items such as machining a component to correct an identified problem or the removal and later reapplication of hardface material on pressure boundary surfaces.The following groups have performed applicable Repair, Replacement and Modification activities during the 1996 Outage.Each group has been identified by a number and will correspond to the groups'ame and address.Rochester Gas and Electric, Ginna Station departments will not be identified as like contractors but by generic name.In the below listing of Repairs, Replacements or Modifications; the work group will be identified by a number within the component discussion.

1.Rochester Gas&Electric, Ginna Station 1A.Rochester Gas&Electric, Laboratory

&Inspection Services 2.NPS Energy Services 280 King of Prussia Road Radnor, Pa.19087'3.Bechtel Power Corporation 9801 Washington Boulevard Gaithersburg, Maryland 20878-5356 4.Team Leak, Inc., Syracuse, New York 5.Babcock&Wilcox Canada R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: c i~.ec'c ve s 4 2.Plant: R.E.Ginna Nuclear Power Plant 1503 Lake Rd.Ontario N.Y.14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

The following information will report applicable Repairs, Replacements or Modifications performed at R.E.Ginna Nuclear Power Plant during this reporting period as required by ASME Section XI Code.ASME Class: 1~Sstem: Pressurizer GORR Mo.: 96-E-001 3A-RC8-2501 Construction Code: ASME Section III'86;Work Performed B: 2 Name of Com onent: V430, V431C Plugs&Cages Work Descri tion/Remarks:

A Replacement activity was initiated for plugs&cages associated with Valves 430&431C.This activity was controlled by WO¹'s 19504164 ,19503981; and PCR 96-032.Upon activity conclusion, a VT-2 Leakage Examination was performed&acceptable under PT-7 (01.1).2.ASME Class: 2~S stem: SI GORR No: 95-E-012 Construction Code: ASME Section III'86;Work Performed B: 1 Name of Com onent: V891C Weld Repair Work Descri tion/Remarks:

An ASME Section XI Code Repair was performed on the upstream socket weld at Valve 891C that was found leaking.This activity was controlled by WO¹19501520&NCR 95-052.Construction Surface (PT)&Visual (VT)examinations were performed and acceptable.

Upon conclusion of the Repair Cycle, a Hydrostatic Test and accompanying VT-2 Examination was performed&acceptable.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: R n v 4 4 2.Plant: R.Ginna uclear Power Plant 1503 Lake d.Ontario N.Y 145 9 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda 3.TTACHMF.ASME Class: 2~Ss tern: RHR GORR No.: 96-001 Construction Code: B31.1'55, SP-5291, ASME III'86 Work Performed B: 1 Name of Com onent: FE-673 Studs&Nuts Work Descri tion/Remarks:

A Replacement activity was initiated for studs&nuts associated with FE-673.This activity was controlled by WO¹19501415.Upon reinstallation, an ASME Section XI VT-2 Leakage examination was performed and acceptable.

4.ASME Class: 2~S stem: SAFW GORR No.: 96-002 Construction Code: ASME III, NF 1974 Work Performed B: 1 Name of Com onent: AFU-123 Snubber Replacement Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support AFU-123.This activity was controlled by WO¹19404238 and Action Report 95-0232.Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

5.ASME Class: l~Sstem: Steam Generators GORR No.: 96-003 Line: N/A Construction Code: B31.1'55, SP-5291 Work Performed B: 1 Name of Com onent: S/G"B" Snubber (SGB-3)Replacement Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support SGB-3 on S/G"B".This activity was controlled by WO¹19404251 and Action Report 95-0232.Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Iriterval, Second Period, Fourth Outage (1996)l.Owner: V 4 2.Plant: R.E Ginna Nuclear Power Plant 1503 I.ake Rd.ntario.Y.14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda TTACHME I 6.ASME Class: 2~S stem: CVCS-Letdown GORR No.: 96-004 Construction Code: ASME III NF'74 Work Performed B: 1 Name of Com onent: CVU-80 Snubber Replacement Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support CVU-80.This activity was controlled by WO¹19404240 and Action Report 95-0232.Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

7.ASME Class: 2~S stem: CVCS GORR No.: 96-005 Construction Code: ASME III NF'74, SP-5291, ME-318 Work Performed B: 1 Name of Com onent: CVU-372 Snubber Replacement Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support CVU-372.This activity was controlled by WO¹19404241 and Action Report 95-0232.Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

8.ASME Class: 3~S stem: AFW GORR No.: 96-006 Construction Code: ASME III NF'74, SP-5291, ME-318 Work Performed B: 1 Name of Com onent: AFU-34 Snubber Replacement Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support AFU-34.This activity was controlled by WO¹19404236.Upon reinstallation, a VT-3 Preservice (Baseline) exam'.nation was performed and acceptable.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: ve 2.Plant: R,F.Ginna Nuclear Power Plant 150 ake Rd, Ontario N Y 14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda 9.ASME Class: 2~S stem: MS GORR No.: 96-008 Construction Code: ASME III NF'74, SP-5291, ME-318 Work Performed B: 1 Name of Com onent: MSU-60 Snubber Replacement Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support MSU-60.This activity was controlled by WO g 19501414 and NCR 95-039.Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

10.ASME Class: 3~S stem: SW GORR No 96-009/Construction Code: B31.1'55, Gilbert Spec R0-2204, SP-5291 Work Performed B: 1 Name of Com onent: PSW01D, SW Pump D Bowl Ass'y&Shaft Work Descri tion/Remarks:

A Bowl assembly with shaft Replacement activity was initiated for Service Water Pump"D" with previously rebuilt items.This activity was controlled by WO 5 19500529, PCR 95-023 and NCR 95-061.Upon reinstallation, a VT-3 Preservice (Baseline)

'examination was performed and acceptable on the associated Rigid Restraint.

Also, a VT-2 Leakage examination was performed and acceptable under PT-2.7.1 ASME Class: 2~S stem: MS GORR No.;96-010"v Construction Code: B31.1'55, SP-5291 Work Performed B: 4 Name of Com onent: V3517 Nuts Work Descri tion/Remarks:

A Replacement activity was initiated for Valve 3517 Cap Nuts.This activity was controlled by WO 5 19503340 and TM 95-045.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner: e ter~~c V e 4 4 2.Plant: R.E.Ginna Nuclear Power Plant 1503 I.ake Rd.Ontario N.Y.14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda TTACHMFNT I 12.ASME Class: 3~S stem: SW GORR No.: 96-011 Construction Code: B31.1'55, SP-5291, ASME III'86 Work Performed B: 1 Name of Com onent: ACA05, Piping&Fittings Work Descri tion/Remarks:

A Replacement activity was initiated for Penetration Cooler ACA05, Piping&Fittings.This activity was controlled by WO¹19404349 and Action Report 96-0115.Construction Code VT examinations were performed and acceptable on the Soldered Copper joints.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

13.ASME Class: 3~Sstem: Aux.FW GORR No.: 96-013"v Construction Code: B31.1'55, SP-5291, ASME III'86, B16.34 Work Performed B: 1 Name of Com onent: V4009 Disc Replacement Work Descri tion/Remarks:

A Replacement activity was initiated for the Disc associated with Valve 4009.This activity was controlled by WO¹'s 19600808, 19600964.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.'4.

ASME Class: 3~S stem: SW GORR No: 96-014/Construction Code: SP-5291, ASME III'86 Work Performed B: 1 Name of Com onent: ESW08A, ESW09A Bolting Work Descri tion/Remarks:

A Replacement activity was initiated on bolting associated with D/G"A" Jacket Water and Lube Oil Heat Exchangers (Shell&Tube sides)as well as a 1/2" bolt on ESW09A-West Base Support.This activity was controlled by WO¹19501745.Construction Code VT examinations were performed and acceptable on ESW09A-West Base Support.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: v e 4 4 2.Plant: R.E.Ginna Nuclear Power Plant 15031 ake Rd.Ontario N.Y, 14519 3.Applicable Edition of Section Xl Utilized for Repairs, Replaccmcnts or Modifications:

1986 No Addenda TT CHME I 15.ASME Class: 2~S stem: SI GORR No.: 96-015 Construction Code: B31.1'55, SP-5291, ASME III'86 Work Performed B: 1 Name of Com onent;Piping&Fittings upstream of V891C Relief Re uest: RR¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for 1 1/2" piping&fittings upstream of Valve 891C to the 3" Header.This activity was controlled by WO¹19501554 and Action Report 95-0394.Construction Code VT and PT examinations were performed and acceptable.

Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31.16.ASME Class: 2~S stem: MS GORR No.: 96-017 Construction Code: ASME III'77/'86 Work Performed B: 2 Name of Com onent: V3504A;Disc, Stem&Bonnet Bolting Work Descri tion/Remarks:

A Replacement activity was initiated for the Disc, Stem&Bonnet Bolting associated with Valve 3504A.This activity was controlled by WO¹19504931.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable..

17.ASME Class: 2~S stem: CVCS GORR No.: 96-019 Line: 3G-CH-151 Construction Code: B31.1'5, G-676262, SP-5291 Work Performed B: 1 Name of Com onent: V313 Disc Work Descri tion/Remarks:

A Replacement activity was initiated for the Disc associated.

with Valve 313.This activity was controlled by WO¹19502488.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was.performed and acceptable.

10 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.2.3.Owner: e~z s V Plant: R..Ginna Nuclear Power Plant 1503 Lake Rd, Ontario.Y 14519 Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

ATTACHMENT II 18.ASME Class: 1~S stem: RCS GORR No.: 96-024 Construction Code: B31.1'55, MSS-SP-69, ASME III'86 SP-5291 Work Performed B: 2 Name of Com onent: V431B Internals Work Descri tion/Remarks:

A Replacement activity was initiated for Valve 431B Plug, Cage and Spacer.Also, the Bonnet gasket area was modified to allow for the installation of a thicker gasket.This activity was controlled by WO¹19601119, Action Report 96-0375, PCR 96-041 and TE 91-515.Construction Code PT examinations were, performed and acceptable on the closure and seat surfaces, and Bonnet.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with PT-7 (01.1).19.20.ASME Class: 3~S stem: Diesel Generators GORR No.: 96-026 Line: N/A Construction Code: B31.1'55, SP-5291, ASME III'86 Work Performed B: 1 Name of Com onent: ESW08B, ESW09B Bolting Replacement Work Descri tion/Remarks:

A'olting Replacement activity was initiated on ESW08B&ESW09B Heat Exchangers.

This activity was controlled by WO¹19501746 and Action Report 96-0041.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

ASME Class: 1~S stem: RCS/Pressurizer GORR No.: 96-027 3A-RC8-2501-B Construction Code: ASME III'86 Work Performed B: 2 Name of Com onent: Valves 431A&431B Gasket Seat Repairs Work Descri tion/Remarks:

A Repair by metal removal was initiated on the Bonnet gasket seating surface for Valves 431A and 431B.This activity was controlled by WO¹19601119 and PCR 96-041.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with PT-7 (01.1).11 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: t v e 4 2.Plant: R.E.Ginna Nuclear Powe Pla t l 3 ake d.Ontario Y 45 9 3.Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

l986 No Addenda GORR No 96-028 Corrective Action Activity 21.ASME Class: 3~Sstem: CCW 3H-AC6-152 Construction Code: B31.1'55, G-676262, ASME III'86/'92 Work Performed B: 1 Name of Com onent: FIC 609/613, Valves 762A/B&Piping Relief Re uest: RR¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for FIC-609, FIC-613, Valves 762A&762B, and associated piping.This activity was controlled by WO¹19320707 and TE 94-552.Construction Code Final Surface (PT/MT)examinations were performed and acceptable.

Root Pass Surface examinations were also performed and acceptable.

Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31.22.ASME Class: 3~S stem: AFW GORR No.: 96-029 1~"'y Construction Code: ASME VIII, B31.1'55 Work Performed B: 1 Name of Com onent: EAF02A, EAF02B Tube Ass'y Replacement Work Descri tion/Remarks:

A Replacement activity was initiated for the Shell and Tube Assembly associated with EAF02A&EAF02B Aux.Feedwater Lube Oil Coolers.This activity was controlled by WO¹19503511 and EWR ME-JEB-A.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

12

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: e e ras v e 4 2.Plant: R.E.Ginna Nuclearpower Plant 1503 1 ake Rd.Ontario.Y.14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda 23.ASME Class: 2~Sstem: MS GORR No.: 96-030 Construction Code: B31.1'55, SP-5291, ASME III'86 Work Performed B: 1 Name of Com onent: Valve 3516 Bolting Replacement

&Flange Modification.

Work Descri tion/Remarks:

A bolting Replacement activity was initiated on Valve 3516.Also, the valve body flange area was machined.This activity was controlled by WO¹19502008.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

24.ASME Class: 3~Sstem: CCW GORR No.: 96-031 Construction Code: B31.1'55,, G-676262, SP-5291, B16.5 Work Performed B: 2 Name of Com onent: Valve 815A Replacement

&Spacer Modification.

Work Descri tion/Remarks:

A bolted Replacement activity was initiated on Valve 815A as well as the installation of a new spacer.This activity was controlled by WO¹19400501 and TSR 96-563.A Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

25.ASME Class: 2~Sstem: MS GORR No.: 96-032 Construction Code: B31.1'55, SP-5291, B16.5'67 Work Performed B: 2 Name of Com onent: Valve 3517 Bolt Modification.

Work Descri tion/Remarks:

A Modification activity was initiated on Valve 3517 to replace an existing 1 3/4" Bonnet stud with a new"step stud.This activity was controlled by WO¹19502007 and PCR 96-043.A Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

13 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Olvner: c V 4 2.Plant: R F.pinna Nuclear Power Plant 150 al'e Rd.Ontario N.Y, 14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda 26.ATTACHMFNT I ASME Class: 2~S stem: Standby.Aux.FN GORR No.: 96-033 3C-FW-902S-1B Construction Code: ASME III NF'74/'86, SP-5291/ME-318 Work Performed B: 1 Name of Com onent: AFU-229&AFU-208 Snubber Replacements Work Descri tion/Remarks:

Snubber Replacement activities were initiated for support AFU-229 and AFU-208.These activities were controlled by WO¹'s 19503968, 19503966 and Action Reports 96-0302, 96-0307.Upon reinstallation, a VT-3 Preservice (Baseline) examinations were per formed and acceptable.

27.ASME Class: 1~S stem: S/G GORR No.: 96-034 Line: N/A Construction Code;ASME III NF'86, SP-5291/ME-318, SP-5378 Work Performed B: 3 Name of Com onent: SGB-4 Snubber Replacements Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support SGB-4 on S/G"B" Ring Support Assembly.This activity was controlled by WO¹19505112 and SM-10034.4.17.

Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

28.ASME Class: 1~Sstem: RCS GORR No.: 96-035 Construction Code: B31.1'55, SP-5291, ME-121 Work Performed B: 1 Name of Com onent: N616 Snubber Replacements Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support N616.This activity was controlled by WO¹19503972, Action Report 96-0621 and EWR 10204.Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

e R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner: es e as 4 4 2.Plant: R.F.Oinna Nuclear Power Plant 1503 I al;e Rd.Ontario N Y 14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda TTACHMFWT I 29.ASME Class: 3~S stem: Aux.FN GORR No.: 96-037 Construction Code: B31.1'55, SP-5291, ASME III'86/'92, B16.34'88.Work Performed B: 2 Name of Com onent: Valve 4007 Replacement Relief Re uest: RR¹31 (Code Case N-416-1)'ork Descri tion/Remarks:

A Replacement activity was initiated for Valve 4007.This activity was controlled by WO¹19601451.Construction Code VT, PT and RT examinations were performed and acceptable.

Root Pa'ss PT was also performed and acceptable.

Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31.30.ASME Class: 3~S stem: Aux.FN GORR No.': 96-038 Construction Code: B31.1'55, SP-5291, ASME III'86/'92, B16.34'88 Work Performed B: 2 Name of Cpm onent: Valve 4008 Replacement Relief Re uest: RR¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for Valve 4008.This activity was controlled by WO¹19601452.Construction Code VT, PT and RT examinations were performed and acceptable.

Root Pass PT was also performed and acceptable.

Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance'ith RG&E Relief Request¹31.15 i

R.E.GINNA NUCLEAR POWER PLANT Inserv ice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Owner: t c V 4 2.Plant: R,F..Crinna Nuclear Power Plant 150 Lake Rd.Ontario N.Y 14519 3.Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

J*ATTACHMENT II 31.ASME Class: 2~S stem: Instrument Air GORR No.: 96-039 a Construction Code: B31.1'55, SP-5291 Work Performed B: 1 Name of Com onent: Valve 5393, Spring&Seat Replacement Work Descri tion/Remarks:

A Replacement activity was initiated for the spring&seat associated with Valve 5393.This activity was controlled by WO¹19601403.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

32.ASME Class: 3~S stem: CCW GORR No.: 96-040 Construction Code: B31.1'55, G-676262, SP-5291, ASME III'86/'92 Work Performed B: 1 Name of Com onent: New 2" Unions-Modification Relief Re uest: RR¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Modification activity was initiated to install new 2" Unions in CCW piping to&from the RHR Pumps.This activity was controlled by WO¹'s 19504169, 19601679 and PCR 96-053.Construction Code VT and PT examinations were performed and acceptable.

Upon completion of this activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31.16

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)1.Osvner: i~c'e.2.Plant: R.F.Ciinna Nuclear Power Plant 1503 I.ai'e Rd.Ontario N.Y.1451 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda ATTACHMENT ll 33.ASME Class: 2~S stem: Biowdown GORR Nowt 96-042 2B-MS-600-1A 2A-MS-600-1B 2B-MS-600-1B Construction Code: B31.1'55, SP-5291, ASME III'86/'92'Work Performed B: 1 Name of Com onent: 2" Blowdown Piping for S/G"A"&"B" Relief Re uest: RR¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Modification activity was initiated to replace existing 2" carbon steel piping with Crome Moly piping from both Steam Generators up to and including the downstream Tee connection.

This activity was controlled by WO¹19504580 and TSR 94-116.Construction Code RT, PT and VT examinations were performed and acceptable.

Upon completion of this activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31 and PT-7 (01.1)procedures.

34.ASME Class: 2/3~S stem: MS GORR No.: 96-043 30A-MS-600-1A 30B-MS-600-1 30A-MS-600-1 Construction Code: B31.1'55, SP-5291, B16.6'67 Work Performed B: 2 Name of Com onent: Valves 3516, 3517, 3518, 3519 Modification Work Descri tion/Remarks:

A Modification activity was initiated to machine the body flange area of valves 3516, 3517, 3518 and 3519 to achieve proper gasket groove depth.A 1 s o;on valve 3517, the retaining bar was reweldecLK Construction Code VT examination was performed and acceptable.

These activities were controlled by WO¹'s 19501739, 19501765, 19502007 and 19502008;Action Reports 96-0417, 96-0590 and PCR 96-059.Upon completion of these activities, ASME Section XI.Leakage Tests and associated VT-2 examinations were performed and acceptable.

17 R.E.GINNA'NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: e V 4 2.Plant: R.F.Oinna Nuclear Power Plant 1503 Lake Rd.Ontario Y.145 9 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

35.ASME Class: 2~S stem: CVCS-Charging GORR No.: 96-044 d'Construction Code: B31.1'55, G-676262, ASME III'86 Work Performed B: lA Name of Com onent: 8" CVCS Weld¹1 Repair Work Descri tion/Remarks:

During an Owner Elected PT examination on weld 8A-CH-2502

¹1, a 3/4" linear indication was identified.

A.Code Repair by metal removal was initiated.

This activity was controlled by WO¹'s 19601798, 19502368, Action Report 96-0412 and PCR 96-061.Upon completion of the Repair Cycle by metal removal, a PT examination was reperformed and acceptable.

UT thickness readings were-also performed and acceptable.

36.ASME Class: l~S stem: RCS GORR No 96-045 4A-RC8-2501B Construction Code: B31.1'55, G-676262 Work Performed B: 1 Name of Com onent: Valves 434, 435 Replacements Work Descri tion/Remarks:

A Replacement activity was initiated on Valves 434 and 435 by mechanical means.This activity was controlled by WO¹'s 19501724 and 19501725.Upon reinstallation; an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with procedure PT-7(01.1).

37.ASME Class: 3~S stem: MS GORR No 96-046 Construction Code: B31.1'55, SP-5291 Work Performed B: 1 Name of Com onent: Valve 3519, Items Replacement Work Descri tion/Remarks:

A Replacement activity was initiated on Valve 3519 for the Shaft, Bushings, Keys and Studs.This activity was controlled by WO¹19501765.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

18

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: v ete.44 2.Plant: R.E.Ginna Nuclea Power lant 150'1.al'e Rd, Ontar'o.Y 14519 3.Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

1986 No Addenda~*"'" 38.ASME Class: 2~S stem: MS GORR No.: 96-047 Constr'uction Code: B31;1'55, SP-5291, ASME III'86/'92 Work Performed B: 1 Name of Com onent: Valve 3504C&Piping Replacement Relief Re uest: RR¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for 1 1/2" piping and Valve 3504C.This activity was.controlled by WO¹19600032 and PCR 96-018.Construction Code VT and PT examinations were performed and acceptable.

Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31.39.ASME Class: 2~S stem: FN GORR No.: 96-048 Construction Code:.ASME III NF'74, SP-5291, ME-318 Work Performed B: 1 Name of Com onent: FWU-3 Snubber Replacement Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support FWU-3.This activity was controlled by WO¹19601790 and Action Report 96-0466.Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

40.ASME Class: 2~S stem: MS GORR No.: 96-049 Construction Code: B31.1/ASME III'77/'78 Work Performed B: 2 Name of Com onent: Valve 3410, Items Replacement Work Descri tion/Remarks:

A Replacement activity was initiated on Valve 3410 for the Pilot Plug and Stem.This activity was controlled by WO¹19504890.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

19

,

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner:~~E'c V 4 4 2.Plant: R.F..Csinna Nuclear Power Plant 150 I.al e Rd.Onta'o N.Y.14519 3.Applicable Edition of Section XI Utilized for Rep'airs, Replacements or Modifications:.

41.ASME Class: 3~Sstem: CCW GORR No 96-050 Construction Code: B31.1'55, G-676262, ASME III'86 Work Performed B: 1 Name of Com onent: FE-651 Bolting Replacement Work Descri tion/Remarks:

A Bolting Replacement activity was initiated on FE-651.This activity was controlled by WO ii 19500555 and Action Report 96-0626.Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

42.ASME Class: 2~S stem: EW GORR Noel 96-051 Construction Code: ASME III NF'74, SP-5291, ME-318 Work Performed B: 1 Name of Com onent: FWU-48 Snubber Replacement Work Descri tion/Remarks:

A Snubber Replacement activity was initiated for support FWU-48.This activity was controlled by WO 8 19601937 and Action Report 96-0646.Upon reinstallation, a VT-3 Preservice (Baseline) examination was p'er formed and acceptable.

43.ASME Class: l~S stem: Steam Generators GORR No.: 96-033/Construction Code: ASME III 1986 Work Performed B: 5 (Installation

=3)Code Stam ed: Yes Name of Com onent: S/G"A&B", EMS01A, EMS01B Relief Re uest: 8 31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A" and"Bue This activity was controlled by EWR'10034.

Applicable Construction Code PT, MT, RT and UT examinations were performed and acceptable.

Construction Code Hydrostatic Test was performed and acceptable.

Applicable ASME Section XI Preservice (Baseline) examinations were performed and acceptable as documented within the 1996 NIS-1"Attachment 1" section.These examinations included Surface, Volumetric and Eddy Current.Upon installation, ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ii31 per procedure PT-7 (01.1)20 R.E.GINNA NUCLEAR POPOVER PLANT Insetvice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: los 4 4 2.Plant:.F.Ginna Nuclear Power Plant 1503 Lal e Rd.Ontario N.Y.14519 3.Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

1986 No Addenda I 44, ASME Class: 1~S stem: Steam Generators GORR No.: 96-054 Line: N/A Construction Code: AWS Dl.l, ASME III NF'74, SP-5378 Work Performed B: 3 Name of Com onent: S/G"A&B", Lower Supports Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A", and"B" Lower Supports for the Steam Generator Replacement Project.This activity was controlled by WO ii's 19600798, 19600802, EWR 10034 and SM's 10034-4.23, 10034-4.15

.Construction Code MT examinations were performed and acceptable.

ASME Section XI Preservice (Baseline)

VT-3 examinations were performed and acceptable.

45.ASME Class: 1~Sstem: Steam Generators GORR No.: 96-055 Line: N/A Construction Code: AWS Dl.l, ASME III NF'74, SP-5378 Work Performed B: 3 Name of Com onent: S/G"A&B", Intermediate Supports Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A" and"B" Intermediate Supports for the Steam Generator Replacement Project.This activity was controlled by WO I's 19600798, 19600802, EWR 10034 and SM's 10034-4.23, 10034-4.15

.Construction Code VT examinations were performed and acceptable.

ASME Section XI Preservice (Baseline)

VT-3 examinations were performed and acceptable.

46.ASME Class: 1~S stem: Steam Generators GORR No.: 96-056 Line: N/A Construction Code: AWS Dl.l, ASME III NF'74, SP-5378 Work Performed B: 3 Name of Corn onent: S/G"A&B", Upper Restraint Rings Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A" and"B" Upper Restraint Rings for the Steam Generator Replacement Project.This activity was controlled by WO 5's 19600574, 19600575, EWR 10034 and SM's 10034-4.22, 10034-4.21

.,Construction Code MT examinations were performed and acceptable.

ASME Section XI Preservice (Baseline)

VT-3 examinations were performed and acceptable.

21 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report*1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owticr:~e v 4 4 2.Plant: R.F.Ginna nclear Popover Plant 1503 Lake Rd,'ntario N.Y.14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda ATTACHMENT I 47.ASME Class: l~S stem: RCS GORR No.: 9,6-057 Line: N/A Construction Code: ASME III'86/'92, B31.1'55, G-676343, G-676496 Work Performed B: 3 Name of Com onent: S/G"A&B" RCS Attachment Welds Relief Re uest:¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A" and"B" RCS reattachment welds.This activity was controlled by WO¹'s 19600794, 19600799, EWR 10034 and SM's 10034-7.12, 10034-7.13

.Construction Code PT and RT examinations were performed and acceptable.

ASME Section XI Preservice (Baseline)

PT, RT/UT examinations were performed and acceptable as documented within the 1996 NIS-1"Attachment 1" section.ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31 per procedure PT-7 (01.1).48.ASME Class: l~S stem: RCS GORR Noet 96-058/..~.""""I'onstruction Code: ASME III'86;B31.1'55, G-676343, G-676496 Work Performed B: 3 Name of Com onent: S/G"A&B", RCS Hot&Cold Leg Repairs Work Descri tion/Remarks:

A Repair activity by metal removal was initiated for Steam Generators"A" and"B" RCS Hot and Cold Legs on identified piping locations to remove original construction defects, arc strikes, and gouges.This activity was controlled by WO¹'s 19601418, 19601419, and Action Report 96-0272.Upon completion of the Repair Cycle, PT examinations as well as UT thickness readings were performed and acceptable.

22

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: s c V 4 2.Plant: R,E, Cr nna Nuclear Power Plant 1503 I.al'e Rd, Ontario N, Y, 14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

49.ASME Class: 2~S stem: FW GORR Noet 96-059 Line: N/A Construction Code: ASME IXI'86;B31.1'55, SP-5291 Work Performed B: 3 Name of Com onent: S/G"A&B";FW Loops"A&B" Repairs Work Descri tion/Remarks:

A Repair activity by metal removal was initiated for Steam Generators"A" and"B" Feedwater Loops"A&B" on identified piping locations to remove original construction defects, arc strikes, and gouges.This activity was controlled by WO¹'s 19601422, 19601423, and Action Report 96-0269.Upon completion of the Repair Cycle, MT examinations as well as UT thickness readings were performed and acceptable.

50.ASME Class: 2~S stem: FW GORR No.: 96-060 Line: N/A Construction Code: ASME III'86/'92, B31.1'55, SP-5291, ME-318 Work Performed B: 3 Name of Com onent: S/G"A&B" FW Attachment Welds.Relief Re uest:¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for.Steam Generators"A" and"B" Feedwater reattachment welds.-This activity was controlled by WO¹'s 19600849, 19600848, EWR 10034 and SM's 10034-7.06, 10034-7.07

.Construction Code PT/MT and RT examinations were performed and acceptable.

ASME Section XI Preservice (Baseline)

PT/MT, RT/UT examinations were performed and acceptable as documented within the 1996 NIS-1"Attachment 1" section.ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31 per procedure PT-7 (01.1).23 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: s~~V 4 4 2.Plant:.F.Ginna uclear Power Plant 1503 Lake Rd.Ontario.Y 14519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

51.ASME Class: 2~Sstem: MS GORR No.: 96-061 30B-MS-600-1B Construction Code: ASME III NF 1974 Work Performed B: 3 Name of Com onent: MS Support Reinstallations Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A" and"B" Mainsteam Spring Can Support reinstallation.

The reinstallation covers supports MSU-1, MSU-4, MSU-6 and MSU-9.This activity was controlled by WO¹'s 19600800I 19600801I EWR 10034I and SM s 10034 7 10 10034 7.11.Up'on reinstallation, an ASME Section XI Preservice (Baseline)

VT examinations were performed and acceptable.

52.ASME Class: 2~Sstem: MS GORR Noet 96-062 Line: N/A Construction Code: ASME I1I'86;B31.1'55, SP-5291 Work Performed B: 3 Name of Com onent: S/G"A&B";MS Loops"A&B" Repairs Work Descri tion/Remarks:

A Repair activity by metal removal was initiated for Steam Generators"A" and"B" Mainsteam Loops"A&B" on identified piping locations to remove original construction defects, arc strikes, and.gouges.

This activity was controlled by WO¹'s 19601420, 19601421, and Action Report 96-0270.Upon completion of the Repair Cycle, MT examinations as well as UT thickness readings were performed and acceptable.

24 0,

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Osvner.este les v este 4 2.Plant: R F pinna ncle r ower la t 503 1 akc d.tario.14519 3.Applicable Edition of Section XI Utilized for Repairs, Replaccmcnts or Modifications:

1986 No Addenda ATTACHMENT I 53.ASME Class: 2~S stem: MS GORR No.: 96-063 Line: N/A Construction Code: ASME III'86/'92, B31.1'55, SP-5291, ME-318 Work Performed B: 3 Name of Com onent: S/G"A&B" MS Attachment Welds Relief Re uest:¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A" and"B" Mainsteam reattachment welds.This activity was controlled by WO¹'s 19600800, 19600801, EWR 10034 and SM's 10034-7.10, 10034-7.11

.Construction Code PT/MT and RT examinations were performed and acceptable.

ASME Section XI Preservice (Baseline)

MT, RT/UT examinations were performed and acceptable as documented within the 1996 NIS-1"Attachment 1" section.ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31 per procedure PT-7 (01.1).54.ASME Class: 2~S stem: Blowdown GORR No.: 96-064 Line: N/A Construction Code: ASME III'86/'92, B31.1'55, SP-5291, ME-318 Work Performed B: 3 Name of Com onent: S/G"A&B" Blowdown Attachment Welds Relief Re uest:¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A" and"B" Blowdown reattachment welds.This activity was controlled by WO¹'s'9600355, 19600356, EWR 10034.and SM's 10034-6.01, 10034-6.02

.Construction Code MT and RT examinations were.performed and acceptable.

ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31 per procedure PT-7 (01.1).25

,

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996).l.Owner: e sa A t'ete 44 2.Plant: R.E.Ginna Nuclear ower Plant 1503 Lake Rd, Ontario N.Y.4519 3.Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

55.ATTACHKTFNT II ASME Class: 2~S stem: FN GORR No.: 96-065 Line: N/A Construction Code: ASME III'86/'92, B31.1'55, SP-5291 Work Performed B: 3 Name of Com onent: S/G"A&B" Level&Instrumentation Lines, Condensate Pots.Relief Re uest:¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A" and"B" Level&Instrumentation Lines and Condensate Pots.Condensate Pots replaced include SFW01, SFW02, SFW03;SFW04, SFW05, SFW06, SFW07, and SFW08.This activity was controlled by WO¹'s 19600728, 19600727, EWR 10034 and SM's 10034-7.08, 10034-7.09

.Applicable Construction Code MT and RT examinations were performed and acceptable.

ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31 per procedure PT-7 (Ol.l).56.ASME Class: 2~S stem: MS GORR No.: 96-066 Line: N/A Construction Code: ASME III'86/'92,'31.1

'55, SP-5291 Work Performed B: 3 Name of Com onent: S/G"A&B" Condensate Pots to Flow Transmitters Relief Re uest:¹31 (Code Case N-416-1)Work Descri tion/Remarks:

A Replacement activity was initiated for Steam Generators"A" and"B" Condensate Pots to Flow Transmitters.'low Transmitters replaced included SMS03A, SMS04A, SMSOSA, SMS06A, SMS03B, SMS04B, SMS05B, and SMS06B.This activity was controlled by WO¹'s 19600728, 19600727, EWR 10034 and SM's 10034-7.08, 10034-7.09

.Applicable Construction Code MT and RT examinations were performed and acceptable.

ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request¹31 per procedure PT-7 (01.1).

0 R.E.GINNA NUCLEAR POWER PLANT Inserv ice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)l.Owner: cste vas e t'e st 4 4 2.Plant: R.F..Ginna Nuclear Power Plant 150 Lake Rd Ontario N.Y 14519 3.Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

1986 No Addenda ATTACHMENT II 57.ASME Class: 2~Sstem: CS GORR No.: 96-067 Line: N/A Construction Code: B31.1'55, G-676262, ASME III'86;ME-318 Work Performed B: 3 Name of Com onent: Containment Spray Attachment Welds&Supports.Work Descri tion/Remarks:.A Replacement activity was initiated to reinstall Containment Spray-piping welds and Supports that were removed for the Steam Generator Replacement Project.This activity was controlled by WO 8 19600898, EWR 10034, SM 10034-4.01 and Action Report 96-0241.Construction Code PT examinations were performed on the Root/Final welds and were acceptable.

Construction Code VT examinations were performed and acceptable on associated component supports.The supports examined included CSU-98, CSU-99, CSU-100, CSU-105, CSU-106, CSU 1071 CSU 108I CSU 109I CSU 110I CSU 111I CSU 112I CSU 117I CSU-118, CSU-119 and CSU-120.An ASME Section XI Flow Test and accompanying VT-2 examination was performed and acceptable.

58.ASME Class: 2~S stem: FW GORR No 96-068/Construction Code: ASME III'86 Work Performed B: 3 Name of Com onent: FW"B" Loop, Punch Mark Repairs to Welds/Piping.

Work Descri tion/Remarks; A Repair activity was initiated to remove Punch Marks on weld/base metal associated with Welds AA5 and AA4R.This activity was controlled by WO 8 19600848, SM 10034-7.07, Bechtel NCR 069 and Bechtel WP&IR/MTI No.P-FWB-01.Punch Marks on existing welds were removed by metal removal.Punch Marks on piping were removed by metal removal and rewelded.Upon completion of the Repair Cycle, Surface MT examinations were performed and acceptable on both welded and metal removal repairs.Repairs by metal removal were controlled to ensure that minimum wall thickness was maintained.

27 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT m EROSION/CORROSION (MINWALL)PROGRAM

SUMMARY

This section provides Erosion/Corrosion examination details and information corresponding to items inspected during the 1996 Outage.A total of 98 items were examined.The breakdown of this total is as follows: m onentT e Total Number Pipes Elbows Reducers Tees Total 45 39 12 2 98 The following lists identifies systems of examined components, system component result summaries, and component result details.S stems of Examined Com onents: SYSTEMS MSR 1A&1B 2ND PASS TO SA HEATER AND CONDENSER MSR 2A&2B 2ND PASS TO'5B HEATER AND CONDENSER MSR 1B 4TH PASS TO SA HEATER 1A, 2A,&3A L.P.HEATER DRAINS TO CONDENSER STEAM EXT.TO PRESEP.TANK B&4B L.P.HEATER STEAM EXT.TO PRESEP.TANK A&4A L.P.HEATER STEAM EXTRACTION TO 5A&5B HEATERS FEEDWATER DISCHARGE (TURBINE BUILDING)FEEDWATER TO S/G 1A (CONTAINMENT)

FEEDWATER TO S/G 1B (CONTAINMENT)

S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)FEEDWATER CLEANUP (CV-19)FEEDWATER CLEANUP (CV-19)MAIN FEEDWATER PUMP RECIRCULATION GLAND STEAM CONDENSER TO TURB.GEN.&GOV.MAIN GLAND STEAM TO TURB.GEN.&GOV.ENDS F.W.HTR.DRAIN SYS.FROM H.D PUMPS TO H.T.TANK Component thickness measurements were performed on the following systems.DWG.NO.M-12A M-12B M-15B M-19 M-21 M-22 M-75 M-81 M-84 M-85 M-88D-M-91 M-91 M-92 M-99 M-100 M-103

R.E.GINNA NUCLEAR POWER PLANT Inserv ice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT m S stem Com onent Result Summaries:

The following break down by system provides general results on the component types that were examined.DWG.NO.SYSTEM M-12A MSR 1A&1B 2ND PASS TO SA HEATER AND CONDENSER Components Examined: Results (%of Nominal): 4 Pipes 7>88 2 Elbows 1 88-82 3 Reducers 1 70-65 M-12B MSR 2A&2B 2ND PASS TO 5B HEATER AND CONDENSER Components Examined: Results (%of Nominal): 1 Elbow 1 70-65 M-15B MSR 1B 4TH PASS TO 5A HEATER Components Examined: Results (%of Nominal): 3 Pipes 3>88 2 Elbows 2 88-82 M-19 IA, 2A,&3A LP.HEATER DRAINS TO CONDENSER Components Examined: 'esults(%ofNominal):

4 Pipes 9>88 4 Elbows 1 Reducer M-21 M-22 STEAM EXT.TO PRESEP.TANK B&4B L.P.HEATER Components Examined: Results (%of Nominal): 3 Pipes 3>88 STEAM EXT.TO PRESEP.TANK A&4A L.P.HEATER Components Examined: 4 Pipes Results (%of Nominal): 1>88 3<65 R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III SYSTEM STEAM EXTRACTION TO 5A&5B HEATERS Components Examined: 4 Pipes 2 Elbows 1 Tee Results (%of Nominal): 5>88 2 76-70 FEEDWATER DISCHARGE (TURBINE BUILDING)Components Examined: 1 Pipe 1 Reducer 1 Tee Results (%of Nominal): 1>88 1 82-76 1>88 FEEDWATER TO S/G IA (CONTAINMENT)

Components Examined: 1 Pipe 3 Elbows 1 Reducer Results (%of Nominal): 3 Acceptable 2>88 FEEDWATER TO S/G 1B (CONTAINMENT)

Components Examined: 1 Pipe 3 Elbows 1 Reducer Results (%of Nominal): 4 Acceptable 1>88 S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)Components Examined: 3 Pipes 2 Elbows 1 Reducer'esults (%of Nominal): 3>88 1 88-82 2<65 0

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT m , SYSTEM FEEDWATER CLEANUP (CV-19)Components Examined: 1 Reducer Results (%of Nominal): 1>88 MAIN FEEDWATER PUMP RECIRCULATION Components Examined: 6 Pipes 3 Elbows 2 Reducers Results'%of Nominal): 9>88 1 88-82 1 76-70 GLAND STEAM CONDENSER TO TURB.GEN.&GOV.Components Examined: 4 Pipes 8 Elbows Results (%of Nominal): 7>88 3 88-82 1 76-70 1<65 MAIN GLAND STEAM TO TURB.GEN.&GOV.ENDS Components Examined: 4 Pipes 8 Elbows Results (%of Nominal): 3 70-65 9<65 F.W.HTR.DRAIN SYS.FROM H.D PUMPS TO H.T.TANK Components Examined: 3 Pipes 1 Elbow 1 Reducer Results (%of nominal): 5>88 4

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Com onent Result Details: The following list provides examination result details on components by drawing number and system description.

The"Component Type" classification specified in the list below corresponds to the following:

P=Pipe E=Elbow T=Tee R=Reducer/Expander J=Expansion Joint M-12A MSR 1AA1B 2ND PASS TO 5A HEATER AND CONDENSER Summary Comp.Comp.Nominal Nominal Minimum Minimum Number ID T e Wall 1 Wall 2 Allowable Readin Percent NDE Nominal Method 222070 7 R 0.300 0.432 0.134,0.192 0.214,0.352 76-70 UT.222075 7A P 0.432 0.192 0.415>88 UT 222080 8 222090 9 E 0.432 0.432 0.194 0.193 0.403 0.413>88>88 UT UT 0.268 0.423>88 222290 27 E 0.432 222310 29 R 0.432 0.437 0.274,0.203 0.482,0.440

>88 UT UT 222330 31 R 0.337 0.594 0.154,0.284 0.400,0.567

>88 UT 0

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Com onent Result Details(CONTINUED)

M-12B MSR 2A&2B 2ND PASS TO 5B HEATER AND CONDENSER Summary Comp.Comp.Nominal Nominal Minimum Num r ID T Will WII2 All w I Minimum Percent NDE R din N min l h 222890 87 E 0.432 0.198 0.290 70-65 UT 223090 106 P 0.432 0.207 0.271 76-70 UT M-15B MSR 1B 4TH PASS TO 5A HEATER Summary Comp.Comp.Nominal Nominal Minimum Number ID T e Wall 1 Wall 2 Allowable Minimum Percent NDE Readin Nominal Method 227220 74 P 0.300 227230 75 E 0.300 227240 76 P 0.300 227320 84 E 0.300 227330 85 P 0.300 0.168 0.169 0.168 0.171 0.168 0.291 0.283 0.260 0.270 0.260>88>88 88-82>88 88-82 UT UT UT UT UT

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Com onent Result Details(CONTINUED)

Summary Comp.Comp.Nominal Nominal Minimum N m er ID T Will Wll2 All w l M-19 1A, 2A,&3A L.P.HEATER DRAINS TO CONDENSER Minimum Percent R in N min 1 NDE Meth d 234010 01 R 0.594 0.500 0.207,0.174 0.567,0.522

>88 UT 234030 03 E 0.500 234040 04 P 0.500 234070 07 E 0.500 234075 07A E 0.500 0.176 0.173 0.174 0.173 0.495 0.484 0.604 0.505>88>88>88>88 UT UT UT UT 234080 08 E 234090 09 P 0.500 0.500 0.174 0.173 0.517 0.484>88>88 UT UT 234280 28 P 0.500 0.175 0.463>88 UT 234290 29 E 0.500 0.177 0.460>88 UT M-21 STEAM EXT.TO PRESEP.TANK B&4B L.P.HEATER Summary Comp.Comp.Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Method 301382 36B P 0 375 301383 36C P 0.375 301384 36D P 0.37'5'0.184 0.184 0.184 0.347 0.363 0.365>88>88>88 UT UT UT R.E.GINNA NUCLEAR PO%ER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Com onent Result Details(CONTINUED)

M-22 STEAM EXT.TO PRESEP.TANK A&4A L.P.HEATER Summary Comp.Comp.Nominal Nominal Minimum Minimum Number ID T e Wall 1 Wall 2 Allowable Readin'ercent NDE Nominal Method 302121 37AA P 0.375 302122 37AB P 0.375 302123 37AC P 0.375 302124 37AD P 0.375 0.184 0.184 0.184 0.184 0.221 0.210 0.229 0.253<65<65<65 70-65 UT UT UT UT M-75 STEAM EXTRACTION TO 5A&5B HEATERS Summary Comp.Comp.Nominal Nominal Minimum Number ID T e Wall 1 Wall 2 Allowable Minimum Percent NDE Readin Nominal Method 303080 08 0.375 0.225 0.336>88 UT 303090 09 T 0.375 303100 10 P 0.375 0.230 0.225 0.392 0.265>88 76-70 UT UT'303110 11 E 0.375 0.234 0.359>88 UT 303120 12 P 0.375 303140 14, E 0.375 0.232 0.225 0.263 0.363 76-70>88 UT UT 8

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Com onent Result Details(CONTINUED)

M-81 FEEDWATER DISCHARGE (TURBINE BUILDING)Summary Comp.Comp.Nominal Nominal Minimum Minimum Percent NDE m r ID T e Will W112 All w 1 Re in N mini eh 390060 06 R 0.844 0.938 0.627,0.631 0.660,0.755

>88 UT 390065 6A P 0.938 390010 01 T 1.281 0.697 0.697 0.877 1.48>88>88 UT UT M-84 FEEDWATER TO S/G 1A (CONTAINMENT)

Summary Comp.Comp.Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Method 393110 11 E 0.938 393120 12 P 0 938 393130 13 E 0 938 0.705 N/A 0.606 0.849 0.703'/A 393150 15 R 0.938 1.156 0.929,1.146 N/A Acceptable VT>88 UT Acceptable VT Acceptable VT 393160 16 E 1.156 0.773 1.026>88 UT 9

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Com onent Result Details(CONTINUED)

M-85 FEEDWATER TO S/G 1B (CONTAINMENT)

Summary Comp.Comp.Nominal Nominal Minimum r ID T e Will W112 11 w le Minimum Percent NDE Re in mini M h 393630 13 E 0.938 393640 14 P 0.938 393650 15 E 0 938 0.700 0.606 0.706 N/A N/A N/A 393670 17 E 0.938 1.156 0.704,0.903 N/A Acceptable VT Acceptable VT Acceptable VT Acceptable VT 393680 18 P 0 938 0.893 1.025>88 N-88D S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)Summary Comp.Comp.Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 All w 1 Rea in N minal Me h 385770 77 P 0.337 0.143 0.308>88 UT 385775 77A R 0.337 0.500 0.143,0.224 0.279,0.467 88-82 UT 385777 77B, P 0.500 0.224 0.476>88 UT 385780 78 385790 79 385820 82 E 0500 P 0500 E 0.500 0.224 0.224 0.224 0.238 0.229 0.461'65 (65>88 UT UT UT 1'

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Com onent Result Details(CONTINUED)

M-91 FEEDWATER CLEANUP (CV-19)Summary Comp.Comp.Nominal Nominal Minimum Num er ID T e Wall 1 Wall 2 All wa 1 Minimum Percent NDE Readin N minal Meth d 300860 40 R 0.432 0.337 0.337,0.236 0.408,0.316

>88 UT M-92 MAIN FEEDWATER PUMP RECIRCULATION Summary Comp.Comp.Nominal Nominal Minimum N m er ID T e Walll W112 All w l Minimum Percent NDE a in N minal M th 281040 04 281050 05 281060 06 281070 07 281110 11 281130 13 E 0.594 P 0.594 0.448 0.375 0.523 0.553>88>88 UT UT UT P 0.337 P 0.337 0.218 0.145 0.343 0.286>88 UT 88-82 UT R 0.337 0.322 0.113,0.169 0.499,0.338

>88 UT E 0.594 0.337 0.466,0.267 0.612,0.612

>88 281200 20B E 0.594 0.337 0.466,0.267 0.420,0.420

<65 UT 281210 21 281250 25 281270 27 281280 28 P 0.337 P 0337 0.218 0.112 0.307 0.307>88>88 P 0322 0.168 0.319>88 R 0.337 0.322 0.113,0.169 0.535,0.372

>88 UT UT UT UT 11 R E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT m Com onent Result Details(CONTINUED)

M-99 GLAND STEAM CONDENSER TO TURB.GE¹4 GOV.Summary Comp.Comp.Nominal Nominal Minimum Minimum N m er ID T e Wall 1 Wall 2 All wa le R din Percent NDE N min l Meh 374426 43B E 0.258 374427 43A P 0.258 0.181 0.18'1 0.103 0.213<65 88-82 UT UT 374440 44 E 0258 0.181 0.241>88 RT 374486 49B E 0 258 374487 49A P 0.258 374500 50 E 0.258 374566 57B E 0.258 374567 57A P 0 258 374580 58 E 0.258 374626 63B E 0 258 374627 63 A P 0.258 374640 64 E 0.258 0.181 0.181 0.181 0.181 0.181 0.181 0.181 0.181 0.181 0.230 0.221 0.236 0.208 0.229 0.267 0.185 0.253 0.244>88 88-82>88 76-70>88>88 76-70>88 88-82 UT UT RT UT UT RT UT UT RT 12

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT m Com onent Result Details(CONTINUED)

M-100 MAIN GLAND STEAM TO TURB.GEN.&GOV.ENDS Summary Comp.Comp.Nominal Nominal Minimum Nm r ID T e Walll Wll2 All w 1 Minimum Percent NDE R in N minal Me h 375222 22B E 0.258 375223'2C P 0.258 375224 22D E 0.258 375322 32B E 0.258 375323 32C P 0.258 375324 32D E 0.258 375412 41B E 0.258 375413 41C P 0.258 375414 41D E 0.258 375502 50B E 0.258'75503 50C P 0 258 375504 50D E 0.258 0.181 0.181 0.181 0.181 0.181 0.181 0.181 0.181 0.181 0.181 0.181 0.181 0.096 0.175 0.129 0.174 0.178 0.155 0.067 0.145 0.092 0.064 0.143 0.122<65 UT 70-65 UT<65 UT<65 UT<65 UT 70-65 UT<65 UT<65 UT<65 UT<65 UT 70-65 UT 76-70 UT 13

.

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Com onent Result Details(CONTINUED)

M-103 F.W.HTR.DRAIN SYS.FROM H.D PUMPS TO H.T.TANK Summary Comp.Comp.Nominal Nominal Minimum m r ID T W111 W112 All w 1 Minimum Percent NDE R in min I eh 325010 01 P 0.216 325020 02 E 0.216 325030 03 P 0.216 0.072 0.072 0.072 0.204 0.201 0.202>88>88>88.UT UT UT , 325310 31 R 0.300 0.432 0.210,0.302 0.311,0.401

>88 UT 325305 30A P 0.300 0.210 0.294>88 UT Additional Ins ections: In addition to the Erosion/Corrosion program, Service Water components were selected to be surveyed from the following drawings;Related S stem C-381-025 Sh 1 C-381-094 Sh 1 C-381-358 Sh1 C-381-024 Sh3 C-381-358 Sh3 C-381-025 Sh4 C-381-358 Sh4 C-381-358 Shs C-381-358 Sh9 C-381-358 Sh13 C'-381-358 Sh14 C-381-358 Sh16 C-381-358 Sh 1 7 C-381-358 Sh22 C-381-358 Sh27 C-381-358 Sh34 SW Suction Line Loop A to Aux.Feedwater AHU-1B Cooling Coils From 4" SW to 20" Return SW From CCHX to Anchor at Wall Col.Q SW Suction Line Loop B AFW Pump Aux.Bldg&SBAFP Bldg.SW Return From CCWHX to Wall Col.Q SW Suction Loop A to AFW Pump Aux Bldg.&SBAFP Bldg.SW From Supply Header to Distribution Manifold SW Return From SFPHX SW IB Above El.253'6" From Pen.308, 315,&323 to Col.7 SW IB Above El.253'6" From 16" Header to Pen.312, 316,&, 320 SW IB Above El.253'6" 16"&20" Header SW IB From 14" Header to Pen.201&209 SW From 20" Header to MDAFW Pumps lA&.1B SW Form Cont.Recirc.Unit 1-C to Pen.315 SW to Cont.Recirc Cooling Unit 1C&1D Motors"A"&"B" SW pumps in Screenhouse

'

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Additional lns ections: (Continued)

~Dw¹C-381-358 Sh35 C-381-358 Sh37 C-381-358 Sh38 C-381-358 Sh39 D-304-695 D-304-696 33013-2027 Related S stem"C" k"D" SW Pumps in Screenhouse SW D/G Bldg."Room A" SW D/G Bldg."Room A 2 B SW D/G Bldg."Room B" Service Water (Auxiliary Building)Service Water (Auxiliary Building)Service Water Supply k Return to SFPHX 82 Service Water Result Details The following list provides examination'result details on service water components by drawing number and system description.

The component ID was provided by engineering support.The"Component Type" classification specified in the list below corresponds to the following:

P=Pipe E=Elbow R=Reducer/Expander C-381-025 Sh1 SW Suction Line Loop A to Aux.Feedwater Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SW251-01 P 0.237 0.095 0.232>88 RT C-381-094 Sh1 AHU-1B Cooling Coils From 4" SW to 20" Return Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SW941-01 P 0.145 0.064 0.151>88 RT

~l, R E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Service Water Result Details CONTINUED C-381-358 Sh1 SW From CCHX to Anchor at Wall Col.Q Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SW01-01 P 0.375 0.150 0.316 84 UT C-381-024 Sh3 SW Suction Line Loop B AFW Pump Aux.Bldg&SBAFP Bldg.Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SW 243-01 P 0.237 0.095 0.231>88 UT C-381-358 Sh3 SW Return From CCWHX to Wall Col.Q Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SW03-01 P SW03-02 P 0.375 0.375 0.150 0.150 0.353 0.328>88 87 UT UT C-381-025 Sh4 SW Suction Loop A to AFW Pump Aux Bldg.&SBAFP Bldg.Comp.ID Comp.T e Nominal Minimum Minimum Percent NDE Wall Allowable Readin Nominal Method SW254-01 P 0.237 0.116 0.191 81 RT 16

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Service Water Result Details CONTINUED C-381-358 Sh4 SW From Supply Header to Distribution Manifold Comp.ID Comp.Nominal Minimum Minimum Percent NDE T e~Wall Allowable Readin Nominal Method SW04-01 P SW04-02 P 0.216 0.216 0.086 0.086 0.149 0.204 70>88 RT RT C-381-358 Shs SW Return From SFPHX Comp.ID Comp.T e Nominal Waii Minimum Allowable Minimum Percent NDE Readin Nominal Method SW05-01 P 0.280 0.242 0.202 72 RT C-3S1-358 Sh9 SW IB Above El.253'6" From Pen.308,315,&323 to Col.7 Comp.ID Comp.T e Nominal Wail Minimum.Minimum Allowable Readin Percent NDE Nominal Method SW09-01.P SW09-02 P SW09-03 E 0.322 0.1'33 0.375 0.129 0.053 0.150 0.302 0.085 0.392>88 75>88 UT RT UT C-381-358 Sh13 SW IB Above El.253'6" From 16" Header to Pen.312, 316,&320 Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SW13-01 P SW13-02 P 0.375 0.280 0.150 0.112 0.347 0.270>88>88 UT UT R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT III Service Water Result Details CONTINUED C-381-358 Sh14 SW IB Above El.253'6" 16"&20" Header Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin'ominal Method SW14-01 E 0.237 0.096 0.190 80 RT C-381-358 Sh16 SW IB From 14" Header to Pen.201&209 Comp.ID Comp.T e Nominal Wail Minimum Allowable Minimum Percent NDE Readin Nominal Method SW16-01 P 0.203 0.143 0.130 (65 RT C-381-358 Sh17 SW From 20" Header to MDAFW Pumps 1A&1B Comp.ID Comp.T e Nominal Wail Minimum Allowable Minimum Percent Readin Nominal NDE Method SW17-01 E SW17-02 P 0.237 0.237 0.130 0.133 0.206 0.177 87 75 RT RT C-381-358 Sh22 SW Form Cont.Recirc.Unit 1-C to Pen.315 Comp.ID Comp.T e Nominal Waii Minimum Minimum Percent NDE Allowable Readin.Nominal Method SW22-01 P 0.237 0.095 0.184 78 RT R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT m Service Water Result Details CONTINUED C-381-358 Sh27 SW to Cont.Recirc Cooling Unit 1C 4 1D Motors Comp.ID Comp.T e Nominal Wall Minimum'llowable Minimum Readin Percent NDE Nominal Method SW27-01 P 0.203 0.081 0.196 UT C-381-358 Sh34"A" 4"B" SW pumps in Screnhouse Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SW34-01 P SW34-02 P 0.322 0.375 0.159 0.185 0.348 0.358>88>88 UT UT C-381-358 Sh35"C" 4"D" SW Pumps in Screenhouse Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SW35-01 P SW35-02 P SW35-03 P 0.237 0.375 0.133 0.117 0.185 0.066 0.383 0.287 0.284>88 76>88 RT UT UT C-381-358 Sh37 SW D/G Bldg."Room A" Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SW37-01 P 0.237 0.095 0.148 (65 UT 19 i

R.E.GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)ATTACHMENT m Service Water Result Details CONTINUED C-381-358 Sh38 SW D/G Bldg."Room A&B Comp.ID Comp.T e Nominal Watt Minimum Allowable Minimum Percent NDE Readin Nominal Method SW38-01 R 0.237 0.126 0.258>88 RT C-381-358 Sh39 SW D/G Bldg."Room B" Comp.ID Comp.T e Nominal Walt Minimum Allowable Minimum Readin Percent NDE Nominal Method SW39-01 P 0.237 0.101 0.229>88 RT D-304-695 Service Water (Auxiliary Building)Comp.ID Comp.T e Nominal Wait Minimum Allowable Minimum Percent NDE Readin Nominal Method SWXX-01 P 0.113 0.079 0.080 71 RT, D-304-696 Service Water (Auxiliary Building)Comp.ID Comp.T e Nominal Waii Minimum Minimum Percent NDE Allowable Readin Nominal Method WXX-02 P 0.065 0.046~0.026 40 RT 33013-2027 Service Water Supply&Return to SFPHX¹2 Comp.ID Comp.T e Nominal Wall Minimum Allowable Minimum Percent NDE Readin Nominal Method SWXX-03 P 0.365 0.146 0.338>88 UT 20

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ML17264A683: Difference between revisions

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