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| | number = ML17262A948 | | | number = ML17262A948 |
| | issue date = 07/31/1992 | | | issue date = 07/31/1992 |
| | title = Rev 0 to Inservice Insp Rept for Third Interval (1990-1999) First Period,Third Outage (1992) at Re Ginna Nuclear Power Plant. | | | title = Rev 0 to Inservice Insp Rept for Third Interval (1990-1999) First Period,Third Outage (1992) at Re Ginna Nuclear Power Plant |
| | author name = | | | author name = |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
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| {{#Wiki_filter:ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUES ROCHESTER'Y 14649 NUCLEAR REGULATORY COMMISSION INSERVZCE INSPECTION REPORT FOR THE THIRD INTERVAL ( 19 9 0 - 199 9 ) | | {{#Wiki_filter:}} |
| FIRST PERIODS THIRD OUTAGE (1992)
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| AT Ro E ~ GINNA NUCLEAR POWER PLANT REVISION 0 JULY 31, 1992
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| R. E ~ GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 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 ISI.Expanded Examinations Snubbers Visual Examinations Functional Testing Erosion/Corrosion (Minwall)
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| Attachment I ISI Program Summary Attachment II Repair, Replacement & Modification Program Summary Attachment III Erosion/Corrosion (Minwall) Program Summary 1 ~
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| Ro E ~ GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 << 1999 Interval, Third Outage 1992 INTRODUCTION AND 8YNOPSIS.
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| Inservice Inspection (ISI) activities during the 1992 Refueling Outage were performed on components within Class 1, 2, 3, High Energy Piping, Steam Generator Tubes and Snubbers. The examinations were initiated on March 16, 1992 and activities concluded on May 8, 1992. Examination methods included Visual Examination (VT), Liquid Penetrant (PT), Magnetic Particle Examination (MT), Ultrasonic Examination (UT), Radiographic Examination (RT), and Eddy Current Examination (ET). Functional Testing (FT) and System Hydrostatic Pressure and Leakage Tests were also performed.
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| Personnel involved included the RG&E Materials Engineering and Inspection Services Section, Southwest Research Institute, NDX Corporation, ABB Amdata Incorporated, Master Lee Services Corporation, Allen Nuclear Associates, Ginna Station Quality Control and the Ginna Station Results/Test Group. Additional Support Personnel involved, included individuals from the following departments: Ginna Station, Insulators, Maintenance, Electricians, Pipe Fitters, Health Physics, Turbine Maintenance, RG&E's General Maintenance and the Mechanical Engineering Group of the Nuclear Engineering Services Department.
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| 8UMMARY OP WORK ACCOMPLISHED:
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| Upon conclusion of the 1992 Outage, 284 of required examinations for the Third Interval ISI Program have been
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| =
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| completed. A detailed component summary of all outage ISI activities with their associated results can be found within "Attachment I".
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| Within last years "Attachment I" 1991 Outage Report, three (3) component supports were inadvertently omitted and one component support summary number contained a typographical error. The summary number identified as 502505 should be 503505. The three (3) component supports omitted were acceptable and are identified as follows; Summary Support Exam. Line ISO Number Number ~T>e Number Number 161110 SIU-83 VT-3 3A-SI-1501 B-37 161260 SIU-76 VT-3 3A-SI-1501 B-37 507100 AFU-221 VT-3 3C-FW-902S-1A C-20
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| Ro E ~ GINNA NUCLEAR POSER PLANT Nuclear Regulatory Commission Znservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 CLASS 1 COMPONENTS A total of 38 Class 1 Components were examined during the 1992 Outage. The examinations for these components consisted of 1 VT-l, 15 VT-3's, 14 PT's, and 9 UT's. A total of 39 required examinations were performed on Class 1 Components.
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| Class 1 examinations were performed on the following items and/or system lines:
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| Item Line Descri tion Plant Line Reactor Pressure'Vessel Interiory Reactor Coolant Pump "A",
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| Integral Attachment; Reactor Coolant Pump "B",
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| Flywheel and Pawls; (See Note)
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| Steam Generator "A" and "B";
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| Regenerative Heat Exchanger; 3" Copes-Vulcan Control Valve; 3" Pressurizer Spray Lines; 3A-RC8-2501-A 3A-RC8-2501-B 3C-RC8-2501 2" Pressurizer Spray Lines; 2-CH5-2501 10" H. P. Safety Injection Line/ 10A-SI2-2501-A 6" Low Head Safety Injection Line; 6A-RCO-2501-B 2>> Letdown Lines; 2A-CH4-2501 2B-CH4-2501 2" Charging Lines; 2D-CH5-2501 2G-CH5-2502 2" Alternate Charging Line; 2F-CH5-2501 2" Excess Letdown Line; 2B-RCO-2501A Note: Credit is being taken this outage for the associated examinations completed in 1990.
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| R E GINNA NUCLEAR POWER PLANT Nuclear Regulatory commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 CLASS 2 COMPONENTS:
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| A total of 87 Class 2 Components were examined. The examinations for these components consisted of 15 VT-1's, 4 VT-2's, 32 VT-3's, 29 PT's, 14 MT's, 3 RTis, and 24 UT's, for a total of 121 examinations.
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| Class 2 examinations were performed on the following items and/or system lines:
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| Item Line Descri tion Plant Line Steam Generator "A"i Circumferential Welds; Seal Water Return Filter, Integral Attachments; Reactor Coolant Filter, Circumferential Welds; Pulse Dampener; Pulse Dampener Lines; 8B-CH-2502 8C-CH-2502 Main Steam Loop A Linesy 30A-MS-600-1A 6A-MS-600-1A Main. Steam Loop B Line; 30B-MS-600-1B Feedwater Loop A Line; 14A-FW-900-1A Feedwater Loop B 'Lines; 14B-FW-900-1B 18B-FW-900-1B
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| 'I 4-IN. H.P. Safety Injection Line; 4D-SI-1501 3-IN. H.P. Safety Injection Lines; 3A-SI-1501 3B-SI-1501 3C-SI-1501 3D-SI-1501 2-IN. H.P. Safety Injection Lines; 2A-SI-1501 2D-SI-1501 2R-SI-2501 2S-SI-2501 2T-SI-2501 2U-SI-2501 8-IN. L.P. Safety Injection Linei 8A-SI-151
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| R. E ~ GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 1999 Interval, Third Outage 1992 CLASS 2 COMPONENTS Cont.
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| Item Line Descri tion Plant Line 6-IN. L.P. Safety Injection Lines; 6A-AC-601 6B-SI-151 10-IN. Residual Heat Removal Lines; 10-AC-601 10A-AC-601 10H-AC-601 8-IN. Residual Heat Removal Lines; 8A-AC-601 8B-AC-601 8F-AC-151 8FF-AC-151 6-IN. Residual Heat Removal Lines; 6D-AC-601 6E-AC-151 6K-AC-151 Residual Heat Exchanger "1A" & "1B' Containment Spray Pump 1; Safety Injection Pump "A"(
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| 3-IN. Standby Auxiliary Feedwater Lines; 3 C-FW-9 02 S-1A 3C-FW-902S-1B CLASS 3 COMPONENTS A total of 36 Class 3 Components were examined by the VT-3 visual technique.
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| Class 3 examinations were performed on the following items and/or system lines:
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| Item Line Descri tion Plant Line'0D-AC5-152 Component Cooling Line; Auxiliary Cooling Lines; 6B-AC6-152 6E-AC6-152 Service Water Lines; 20E-SWO-125-1 16A-SWO-125-1 6B-SWO-125-1 4A-SW-125-1A
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| R E ~ GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 .Interval, Third Outage 1992 CLASS 3 COMPONENTS Cont.
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| Item Line Descri tion Plant Line Auxiliary Feedwater Lines; 3A-FW7-900-1A 3E-FW7-900-1 3G-FW7-900-1 3 J-FW7-900-1 Standby Auxiliary Feedwater Line; 4A-FW8-152S-A 1.5A-FW8-902S Mainsteam supply to Auxiliary Feedwater Pump Turbine Line; ,6A-MS-600-1 HIGH ENERGY COMPONENTS:
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| Components associated with the High Energy Program were examined during the 1992 Outage. The examinations for these items consisted of 17 VT-1's,22 VT-3's, 22 MT's, 4 PT's, 8 RT's, 14 UT's for a total of 87 examinations.
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| High energy component examinations were performed on the following items and/or system lines:
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| Desi n Break Weld Examinations Item Line Descri tion Plant Line Main Steam Turbine Building, Line; 36-MS-600-1 Main Steam Loop "B" Outside Containment, Lines; 36-MS-600-1 30B-MS-600-1B Feedwater Turbine Building, Line; 20-FW-900-1 Feedwater Loop "A", Outside Containment, Line; 20-FW-900-1 Feedwater Loop "B", Outside Containment, Lines; 20-FW-900-1 14B-FW-900-1A
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| R. E ~ GINNA NUCLEAR POWER PLANT Nuclear'Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 HIGH ENERGY COMPONENTS Cont.
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| Conse ential Break Weld Examinations Item L'ine Des'cri tion Plant Line Main Steam Loop >>A", Outside Containment, Line; 30A-MS-600-1A Main Steam Loop "B", Outside Containment, Line; 30B-MS-600-1B Main Steam Turbine Building, Line; 24A-MS-600-1A Feedwater Turbine Building, Lines; 20.-FW-900-1 8-FW-900-1 Feedwater Loop "A", Outside Containment, Line; 14A-FW-900-1A Feedwater Loop ."B", Outside Containment, Line; 14B-FW-900-1B Com onent Su ort Examinations Item Line Descri tion Plant Line Main Steam Line; 36-MS-600-1 24A-MS-600-1A 24B-MS-600-1A Feedwater, Loop "A", Line; 14A-FW-900-1A Feedwater, Loop "B", Line; 14B-FW-900-1B Main Feedwater, Line; 20-FW-900-1
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| 'K 0
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| R E GINNA NUCLEAR POSER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 1999 Interval, Third Outage 1992 STEAM GENERATOR TUBING:
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| Eddy Current Examinations were performed on tubes in the A and B Steam Generators.
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| The following Eddy Current examinations were performed during the 1992 Outage:
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| : 1. Open Generator Tubes, Previous indications greate'r than 204, other than wastage, examined to the extent of degradation as a minimun.
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| : 2. Open Generator Tubes, 20% Minimum, Rotating Random Sample Full Length.
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| : 3. Open Generator Tubes, 100% of all open unsleeved tubes examined to the top of Tubesheet on the Hot Leg Side as a minimum.
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| 4 ~ Sleeved Generator Tubes, 20% Random Sample of each type. Sleeve End to Sleeve End (minimum) .
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| : 5. MRPC of Row 1 U-Bends and Row 2 U-Bends that are a part of the 204 Random Sample Full Length.
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| The following information summarizes the initial pre-outage as well as, the planned and completed Eddy Current work scope for Steam Generators A & B:
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| STEAM GENERATOR A:
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| Steam Generator "A" Ins ection Summar Prior To Correction:
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| Total Tubes 3260 Out of Service (Plugged) 187 Sleeved Tubes 325 Open Unsleeved Tubes 2748
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| "Ro E ~ GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 STEAM GENERATOR TUBING: Cont.
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| Steam Generator "A" Planned and Com leted Work Sco e:
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| Req'd Number Number Min ProcrP 'd ~Xns t'd ~Com 1t'd Hot Leg to TSH (MRPC) 2748 2748 2748 100.0%
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| Full Length (204 Random) 550 596 596 108.4%
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| Previous Ind. > 20% 27 27 27 100.0%
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| Sleeves 65 82 82 126.24 Deplugged Tubes (F/L') 16 16 16 100.04' Per Appendix B Requirement 2 4 Complete = Tubes Inspected/Required Minimum STEAM GENERATOR B~
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| Steam Generator "B" Ins ection Summar Prior To Correction:
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| Total Tubes 3260 Out of Service (Plugged) 323 Sleeved Tubes 939 Open Unsleeved Tubes 1998
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| R. E ~ GINNA NUCLEAR, POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 STEAM GENERATOR TUBING: Cont.
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| Steam Generator "B" Planned and Com leted Work Sco e:
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| Req'd Number Number Min1 Procr'd ~ins t'Com lt'd Hot Leg to TSH (MRPC) 1998 1998 1998 100.04 Full Length (204 Random) 400 446 , 446 111.5%
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| Previous Ind. > 204 18 18 18 100.04 Sleeves 187 212 212 113. 34 Deplugged Tubes (F/L) 30 30 30 100. 04 1 Per Appendix B Requirement 2 4 Complete = Tubes Inspected/Required Minimum Steam Generator Eddy Current Examination details are documented in the Rochester Gas & Electric Report titled "Summary Examination Report for the 1992 Steam Generator Eddy Current Inspection".
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| SYSTEM PRESSURE TESTS:
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| H drostatic Testin Nine (9) Hydrostatic tests and associated VT-2 examinations were performed during the 1992 Outage.
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| The following Hydrostatic tests were performed and credited this Outage.
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| Procedure Descri tion RSSP-15.8.1 Reactor Coolant Pump Seal Water Return.
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| RSSP-15.13 Safety Injection, Accumulator II All
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| R. E. GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 SYSTEM PRESSURE TESTS Cont.
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| Descri tion
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| (
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| Procedure RSSP-15.14 Safety Injection, Accumulator II B fI RSSP-15.29 Reactor Coolant System, Letdown.
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| RSSP-15.31 Reactor Vessel Head Vents.
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| RSSP-15.43 House Heating Steam.
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| RSSP-15.44 Fire Protection System.
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| RSSP-15.47 Demineralizer Water System.
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| RSSP-13.28 Spent Fuel Pool Cooling.
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| (See Note g1) performed after '91 Outage start-up.
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| Leaka e Testin A total of 40 leakage examinations were performed during the 1992 outage. The leakage tests included; one (1) Class 1, Reactor Coolant System (PT-7) examination, and thirty-seven (37)
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| Class 2 and 3 examinations. Credit was taken on 2 leakage examinations, as allowed by ASME Section XI Code, when their associated hydrostatic.,tests were performed this outage.
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| Four (4) scheduled leakage examinations will be performed before 31 December 1992. This action will Interval, First Period requirements as fulfill the Third specified within the Quality Assurance Manual,'ppendix B Program. These examinations will be identified and reported in the 1993 Outage Report.
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| ISI E anded Examinations:
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| During the 1992 Ginna Outage, one (1) component was determined to have an ASME Code "Service Induced" Reject.
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| The component is:
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| ~Ss~te Line Com onent Auxiliary Feedwater 3A-FW7-900-1A AFU-52; Mechanical Snubber Because it was classified as a ASME Code "Service Induced" Reject, additional examinations were performed to conform with the requirements specified within IWF-2430 of ASME Section XI. The results of the additional examinations were acceptable.
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| 10
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| R. E ~ GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 SNUBBER PROGRAM~
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| Visual'Examinations:
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| A total of 149 Snubber components were inspected and required 149 VT-3 examinations. These examinations were performed to satisfy Ginna Station Technical Specification requirements.
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| Snubber examinations were performed on the following items and/or system lines:
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| Item Line Descri tion Plant Line Steam Generator "A";
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| Steam Generator "B";
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| Turbine Driven Auxiliary Feedwater Pump Suction Line; 4A-CD-150-1C 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 3B-FW-900-1A Steam Generator 1B Blowdown Line; 2C-MS-600-1B.
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| Auxiliary Cooling Line; 4S-AC6-1'52 Auxiliary Cooling System from Pump Cooling Outlet to Penetration 126 Line; 3E-AC6-152 Auxiliary Cooling Line; 4T-AC6-152 2-IN. Letdown Line; 2A-CH4-2501 2-IN. Charging Line; 2G-CH5-2502 2-IN. Alternate Charging Lines; 2F-CH5-2501 CVCS Relief Line; 2E-CH-601 Reactor Coolant Pump "1B" Seal Water Line; 2AB-CH-2502 Reactor Coolant Pump "1A" Seal Water Line; 2P-CH-2501 CVCS Letdown Lines; 2H-CH-601 2A-CH4-151 Feedwater Loop "A" Line; 14A-FW-900-1A Feedwater Loop "B" Line; 14B-FW-900-1B Main Steam Loop "A" Line; 30A-MS-600;,1A Main Steam Loop "B" Line; 30B-MS-600-1B 11
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| 1<
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| Ro E ~ GINNA NUCLEAR POWER PLANT Nuclear Regulatory Cammissian Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 SNUBBER PROGRAM Cant.
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| Visual Examinations Cont.
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| Item Line Descri tion Plant Line Main Steam Loop "A", Atmospheric Vent Line; '6B-MS-600-1A Main Steam Loop "B", Atmospheric Vent Line; 6B-MS-600'-1B Main Steam Supply to Auxiliary Feedwater Pump Turbine Lines; 6A-MS-600-1 6A-MS-600-1A 6B-MS-600-1 6B-MS-600-1B Low Head Safety Injection Line; 6-AC-601 Residual Heat Removal Line; 10A-RCO-2501-A Residual Heat Removal Line; 8B-AC-601 Residual Heat Removal Line; 10-AC-601 Residual Heat Removal Line; 6D-AC-601 Residual Heat Removal Line; 10E-AC-601 Residual Heat Removal Line; 10G-AC-601 Residual Heat Removal, Pump "A" Suction Line; 10GG-AC-151 Residual Heat Removal Line; 10D-AC-601 Residual Heat Removal Line; 6K-AC-151 Low Head Safety Injection Liney 10-SI-151 Safety Injection, Pump "A" Suction Line; 4-SI-301 Safety Injection Line; 8H-SI-151 High Pressure Safety Injection Lines; 10A-SI2-2501-A 10A-SI2-2501-B Service Water to A&B Diesel Generator Water Coolers Line; 10B-SWO-125-1 Service Water Line; 8L-SW-125 Service Water-Intermediate Building from 16" Header to Penetrations 312-320, Line; 8A-SWO-125-1 Standby Auxiliary Feedwater from Penetration 123 to B S/G Feedwater Header, Line; 3C-FW-902S-1B Standby Auxiliary Feedwater from Penetration 119 to A S/G Feedwater Header Line; 3C-FW-902S-1A 12
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| R E ~ GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 SNUBBER PROGRAM Cont.
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| Item Line Descri tion Plant Line Pressurizer Relief from Pressurizer to Relief Manifold Lines; 6AP-RC-602 6BP-RC-602 Power Pressurizer Relief Lines; 3BP-RC-602 3B-RC8-2501 Pressurizer Relief Line; 3A-RC8-2501 CVCS Line; 2X-CH-2501 Standby Auxiliary Feedwater Lines; 3C-FW-902S-1A 3C-FW-902S-1B Functional Testin
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| 'I A total of 16 snubbers were scheduled and Functionally Tested (FT) during the 1992 outage. Twelve of the sixteen were Mechanical Snubbers and the remaining four were Hydraulic Snubbers. Snubber MSU-12 was scheduled for functional testing but MSU-27 was substituted during the outage. From the original scheduled tests, nineteen (19) additional (expanded) snubber functional tests were required and performed. An additional four (4) snubbers were functionally tested for operability and., were found to be acceptable.
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| The following list identifies the four (4) additional snubbers tested for operability by component support number.
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| PS-9 N-605 RHU-92 MSU-26 (Bottom)
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| In 1991, three (3) snubbers were functional tested and declared operable. The three snubbers are; PS-2, PS-4 and PS-10.
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| These'hree snubbers were inadvertently omitted from the 1991 report.
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| The following list identifies 1992 inoperable snubbers and the corresponding snubber scope expansion by component. support number.
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| Ino erable Snubber Snubber Ex ansio MSU-74 MSU-55 MSU-72 MSU-84E MSU-57 MSU-75 MSU-84W MSU-58 MSU-78 MSU-85 MSU-60 MSU-80 SWU-308 13
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| R. E. GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 SNUBBER PROGRAM Cont.
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| Functional Testin Cont.
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| Ino erable Snubber Snubber Ex ansion AFU-205 AFU-225 N-601 PS-4 CVU-351 CVU-49 CVU-345 CVU-372 SWU-254 For the 1993 Outage, a total, of twenty-four (24) snubbers will require Functional Testing (FT). From this total number, sixteen (16) snubbers will be required by the normal schedule. The remaining eight (8) snubbers will require retesting to conform to the requirements specified. within the Technical Specifications and ME-256. The eight (8) snubbers requiring retesting are as follows:
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| MSU-26 (Bottom) MSU-57 MSU-60 MSU-74 MSU-84 (East) MSU-84 (West) CVU-351 CVU-372 Snubber Functional Testing (FT) was scheduled and performed on the following items and/or system lines:
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| Item Line Descri tion Plant Line Steam Generator "A" Auxiliary Feedwater Pump Discharge Intermediate Building Line; 3B-FW-900-1A Auxiliary Cooling Line; 4T-AC6-152 2-IN. Alternate Charging Lines; 2F-CH5-2501 CVCS Letdown Lines; 2H-CH-601 2A-CH4-151 Feedwater Loop "B" Line; 14B-FW-900-1B Main Steam Loop "A" Line; 30A-MS-600-1A Main Steam Loop "B" Line; 30B-MS-600-1B Main Steam Loop "A" Atmospheric Vent Line; 6B-MS-600-1A Main Steam Loop "B", Atmospheric Vent Line; 6B-MS-600-1B Main Steam Supply to Auxiliary Feedwater Pump Turbine Lines; 6A-MS-600-1 6A-MS-600-1A 6B-MS-600-1 6B-MS-600-1B 14
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| '4 R. E GZNNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Znservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 SNUBBER FUNCTIONAL TESTING: Cont..
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| Item Line Descri tion ~
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| Plant Line Residual Heat Removal Line; 8B-AC-601 Residual Heat Removal Line; 6K-AC-151 Service Water to A&B Diesel Generator Water Coolers Line; 10B-SWO-125-1 Service Water Line; 8L-SW-125 Standby Auxiliary Feedwater from Penetration 123 to B S/G Feedwater Header, Line; 3C-FW-902S-1B Standby Auxiliary Feedwater from Penetration 119 to A S/G Feedwater Header Line; 3C-FW-902S-1A Pressurizer Relief from Pressurizer to Relief Manifold Lines; 6AP-RC-602 6BP-RC-602 Power Pressurizer Relief Lines; 3BP-RC-602 A
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| Outage.
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| total 'f EROSION CORROSION MINWALL PROGRAM~
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| 161 Components were examined during the The breakdown of this total number are as follows:
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| 1992 Com onent T e Total Number Pipe 74 Elbow 46 Reducer 23 Tee 15 Component thickness measurements were performed on the following systems:
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| DWG ~
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| NO SYSTEM M-3 HEATER 4A/B DRAIN TO HEATER DRAIN TANK.
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| M-7B CONDENSATE PUMP & HEATER DRAIN TANK DISCHARGE TO FEEDWATER SUCTION.
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| M-12B MSR 2A,2B 2ND PASS DRAIN TO 5B H.P.H. & CONDENSER.
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| M-15A MSR 1A 4TH PASS TO 5A HEATER.
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| M-16 MSR 1A & 1B 4TH PASS TO CONDENSER.
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| 15
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| R E. GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 EROSION CORROSION MINWALL PROGRAM Cont.
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| DWG.
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| NOi SYSTEM M-18 MSR 2A & 2B 4TH PASS TO CONDENSER.
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| M-21 STEAM EXTRACTION TO PRESEPARATOR B & 4B L.P.H.
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| M-22 STEAM EXTRACTION TO PRESEPARATOR A & 4A L.P.H.
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| M-31 MSR 1A & 1B TO HEATER DRAIN TANK.
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| M-'3 2 MSR 2A & 2B TO HEATER DRQIN TANK.
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| M-33 MSR 1Ag 1Bg" 2A & 2B TO HEATER DRAIN TANK M-4 1A 5A H.P.H.DRAIN TO 4A L.P.H.
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| M-45 PRESEPARATOR A/B TO HEATER DRAIN TANK C CONDENSER.
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| M-46A PRESEPARATOR A/B TO HEATER DRAIN TANK & CONDENSER.
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| M-46B PRESEPARATOR A/B TO HEATER DRAIN TANK.
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| M-75 STEAM EXTRACTION TO 5A & 5B H.P.H.
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| M-82 FEEDWATER DISCHARGE; INTERMEDIATE BUILDING.
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| M-83 FEEDWATER DISCHARGE; INTERMEDIATE & FACADE.
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| M-88D S/G BLOWDOWN TO FLASH TANK (TURBINE, BLDG. ).
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| M-88E S/G BLOWDOWN (INTERMEDIATE BLDG. ).
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| M-89A S/G 1A BLOWDOWN (CONTAINMENT BLDG. ).
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| M-89B S/G 1B BLOWDOWN (CONTAINMENT BLDG. ).
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| M-89C S/G 1A BLOWDOWN (CONTAINMENT BLDG. ) TO PEN. 322.
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| M-92 MAIN FEEDWATER PUMP BYPASS.
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| M-93 FEEDWATER HEADER BYPASS.
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| M-94 S/G BLOWDOWN TO CONDENSER.
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| M-96 REHEATER EXCESS STEAM TO CROSS UNDER.
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| M-97 STEAM EXTRACTION FROM BLOWDOWN TANK TO 3A L.P. HEATER.
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| M-98 S/G BLOWDOWN TANK TO CONDENSER.
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| 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.
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| Prepared by: 7-3) -g Frank A. Klepack1 Date ISI Engineer 16
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| R>> E ~ GINNA NUCLEAR POWER PLANT Nuclear Regulatory Commission Inservice Inspection Report 1990 - 1999 Interval, Third Outage 1992 Certificate of Inservice Ins ection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspections and employed !by The Hartford Steam Boiler Inspection and Insurance Company have inspected and/or verified the components described within this 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.
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| Reviewed By:
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| ANII's Signature Date Approved By:
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| Mxchae J. Saporito Manager, Materials Engineering NDE Level III 17
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| FORM NIS-I ONER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules I. Owner Rochester Gas & Electric Corp., 89 East Ave., Rochester N.y. 14649, (Name and Address of Owner)
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| R.E. Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, N.y., 14519
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| : 2. Plant (Name and Address of Plant)
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| : 3. Plant Unit' 4. Owner Certificate of Authorization (if required) N/A
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| : 5. Commercial Service Date Y 6. National Board Number for Unit N/A
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| : 7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
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| (8) SEE "ATTACHMENTI" Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) size is 8'n. x l I in.,
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| (2) information in items I 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.
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| (12/86) This form (E00029) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007 2300.
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| FORM NIS-I (Back),
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| : g. Examination Dates 3/16/92 to 5/8/92 9. Inspection interval from ~ting to
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| .* i* *. '<<- **- ll 1
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| : 11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. (g) 1
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| : 12. Abstract of Conditions Noted.
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| (e)
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| : 13. Abstract of Corrective Measures Recommended and Taken.
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| We certify that the statements made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the ASME Code, Section XI.
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| Certificate of Authorization No. (if applicable) N/A Expiration Date
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| ~
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| N/A Date 31 July 19 92 Signed j By Frank A. Kle acki Owner ISI Engineer 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 ~~ ~ <0 ~
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| of
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| ~rtH~oNB t 7- have inspected the components described in this Owner's Report during the period has performed examinations and taken corrective measures described in this Owner's Report in accordance with the inspection plan and as required by the ASME Code, Section XI.
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| 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.
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| Date P'9 inspector's Signature
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| $ W Commissions
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| .
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| W N+9~ ~~ < <~~ C~, i A National Board, State, Province, and Endorsements
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| (+) SEE "ATTACHMENTI"
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| R>> E>> GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SS I COMPONENTSt REACTOR PRESSURE VESSEL DRAWINGSt A-1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 000700 B-N-1 B13.10 R.P.V. ASME VESSEL INTERIOR 92 NO RECORDABLE INDICATIONS. EXAMINEDy REACTOR VERTICAL WALL, VESSEL TO FLANGE WELD'OZZLES IN VESSELS'ASKET SURFACE 6 GROOVEg CORE BARREL OUTLET NOZZLE~ ALIGNMENT PINS~ TOP OF CORES'ARREL FLANGE CORE HOLD DOWN SPRING. ACCEPTABLE.
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| A2>> STEAM GENERATORS DRAWINGSt A-5 Summary Exam Item NDE Number Cate g Number Component Component Type Exam 005900 B-D B3.140 INLET NOZZLE ASME UT INLET NOZZLE INSIDE RADIUS SECTION 92 INLET NOZZLE. NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 006100 B-D . B3.140 OUTLET NOZZLE ASME UT OUTLET NOZZLE INSIDE RADIUS SECTION 92 OUTLET NOZZLE, NO RECORDABLE INDICATIONS ACCEPTABLE.
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| A3>> REGENERATIVE HEAT EXCHANGER DRAWINGS t A-8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 007700 B-B B2.60 RHE-I ASME UT SHELL TO HEAD WELD (TUBE SIDE) 92 LIMITED EXAM FROM 11 1/2" TO 12 I/2" DUE TO RESTRICTION.
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| GREATER THAN 90t WELD COVERAGE OBTAINED. NO RECORDABLE INDICATIONS - ACCEPTABLE.
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 1 COMPONENTS CONT.
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| REGENERATIVE HEAT EXCHANGER (CONT+) DRAWINGS t A-8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 007800 B-B B2.80 RHE-2 ASME UT SHELL-TO-SHELL WELD (SHELL SIDE) 92 NO EXAMINATION ON TUBE SHEET SIDE" DUE TO CONFIGURATION. GREATER THAN 90't WELD COVERAGE OBTAZNED ACCEPTABLE~
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| 008000 F-B F2.00 RHE-2-PR1 ASME VT-3 HANGER 92 - NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 008100 F-B F2.00 RHE-2-PR2 ASME VT-3 SUPPORT 92 - NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 008200 B-B B2.60 RHE-3 ASME UT SHELL TO HEAD WELD (SHELL SIDE) 92 GREATER THAN 90% WELD COVERAGE OBTAINED'O RECORDABLE INDICATIONS ACCEPTABLE.
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| 008600 F-C F3. 00 RHE-5-PR1 ASME HANGER 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 008700 F-B F2.00 RHE-5-PR2 ASME SUPPORT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 009300 F-B F2.00 RHE-8-PR2 ASME SUPPORT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 4 R. E. GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 1 COMPONENTS CONT.
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| REGENERATIVE HEAT EXCHANGER (CONT+) DRAWINGSt A-8 Summary'Exam Item NDE Number Categ Number Component Component Type Exam 009600 B-D B3.150 RHE-N2 ASME UT VESSEL-TO-NOZZLE WELD 92 GREATER THAN 90 h WELD COVERAGE OBTAINED@ NO RECORDABLE INDICATIONS ACCEPTABLE.
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| A4 ~ 3-ZN. PRESSURIZER SPRAY LINE DRAWINGS c A-9 A-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam 016600 F-C F3.00 RCU-20 ASME VT-3 RIGID RESTRAINT 92 NO RECORDABLE INDICATIONS ACCEPTABLE
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| (
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| 019100 F-C F3.00 RCU-2 ASME VARIABLE SPRING 92 SIZE 5 g TEMPERATURE 70 DEGREES F ~ g SETTZNG 4 286'NSIGNIFICANTj LOCKNUTS DO NOT HAVE FULL THREAD ENGAGEMENT - ACCEPTABLE.
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| 021100 B-J B9.21 DSW-3 ASME PT ELBOW-TO-ELBOW WELD 92 NO RECORDABLE INDZCATZONS ACCEPTABLE.
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| A5o 2-IN+'PRESSURIZER SPRAY LINE DRAWINGS! A-1 1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 023300 F-C F3.00 CVU-70 OE VT-3 RIGID RESTRAINT 92 RESOLUTION OF NCR 91-221. NO RECORDABLE INDICATIONS ACCEPTABLE ~
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| Ro E ~ GZNNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 1 COMPONENTS CONT.
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| A6. H.P ~ SAFETY INJECTION LINE TO LOOP B COLD LEG DRAWINGS i A-16 Summary Exam Item NDE Number Categ Number Component Component Type Exam 033650 F-C F3.00 SIU-47 ASME MECHANICAL SNUBBER 92 SERIAL NUMBER 15349 I TEMPERATURE 60 DEGREES F g SETTING 3 g PSA 3 ACCEPTABLE.
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| 033950 B-J '9.11 Gl TRANSITION-TO-PIPE
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| 'SME UT PT WELD 92 PT/UT: NO RECORDABLE INDICATIONS, ROOT GEOMETRY ACCEPTABLE.
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| A7o 6-IN+ SAFETY INJECTION SYSTEM (LOW HEAD) DRAWINGS'-18 Summary Exam Item NDE Number Categ Number Component Component Type Exam 036200 B-J B9.11 J ASME UT 852B VALVE-TO-PIPE PT WELD 92 PTg NO RECORDABLE INDICATIONS ACCEPTABLE ~ UT LAMINATION NO UPSTREAM EXAM DUE TO VALVEg NO RECORDABLE SCAN'IMITATION:
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| INDICATIONS DOWNSTREAM ACCEPTABLE.
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| AS ~ 2-ZN o LETDOWN LINE DRAWINGS I A-23 A-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 044000 B-J B9.40 12 ASME PT PIPE-TO-TEE WELD 92 NO RECORDABLE INDICATIONS ACCEPTABLE'
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| 'i 0
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| 4
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| R E. GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 1 COMPONENTS CONT.
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| 2-IN+ LETDOWN LINE (CONT. ) DRAWINGS'-23 Summary Exam Item NDE Number Categ Number Component Component Type Exam 044400 B-J B9.40 16 ASME PT PIPE-TO-COUPLING WELD 92 NO RECORDABLE INDICATIONS - ACCEPTABLE.
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| 047200 - F-C F3.00 CVU-27 ASME VARIABLE (SPRING) 92 TEMPERATURE 65 DEGREES F ~ g SETTING EXAMINATION ACCEPTABLE.
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| '/8 14lgg SIZE 3 g REMOTE 048216 B-J B9.40 6 ASME PT PIPE-TO-TEE WELD 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 048244 B-J B9.40 18 ASME PT ORIFICE-TO-PIPE WELD 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 048270 B-J B9.40 28 ASME PT PIPE-TO-ELBOW 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
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| E' R>> Ee GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Inservt.ce 1999 Interval, Thi.rd Outage 1992 ATTACHMENT I CLASS 1 COMPONENTS CONT ~ g A9 ~ 2-IN+ CHARGING LZNE DRAWINGS'-29 A-30 Exam Item NDE 'ummary Number Categ Number Component Component Type Exam 050830 F-C F3.00 CVU-43 ASME U-BOLT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 050857 F-C F3.00 CVU-46 ASME VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 23517 g TEMPERATURE 62 DEGREES F ~ SETTING 2 g PSA 1/2 g ACCEPTABLE.
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| 050933 F-C F3.00 CVU-54 ASME VT-3 RIGID RESTRAINT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 050966 F-C F3.00 CVU-59 ASME VT-3 RIGID RESTRAINT 92 NO RECORDABLE INDICATIONS ACCEPTABLE+
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| A10 ~ 2-ZNo ALTERNATE CHARGING LINE: DRAWINGS+ A-27 Summary Exam Item NDE Number Categ Number Component Component Type Exam
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| , 054600 B-J B9.40 7 ASME PT TEE-TO-PIPE WELD 92 INSIGNIFICANT: PORE 1/64" DIAMETER) IRREGULAR UNDERCUT < 1/32" DEEP.
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| REJECT: ARC STRIKE 3/4" LONG. NCR 92-183 GENERATED FOR CORRECTIVE ACTION.
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| REEXAM - PTg NO RECORDABLE INDZCATIONS ACCEPTABLE+ FINAL UT THICKNESS
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| - NO NOTICEABLE WALL LOSS. ALL INDICATIONS RECORDED ARE CONSTRUCTION - NOT SERVICE INDUCED.
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| Ro E. GZNNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 1 COMPONENTS CONT 2-ZN. ALTERNATE CHARGING LINEi (CONT.) DRAWINGS'-27 Summary Exam Item NDE Number Categ Number Component Component Type Exam 054800 B-J B9.40 9 ASME PT FLANGE-TO-PIPE WELD 92 INSIGNIFICANT: SLAG INCLUSION. REJECT: ROUGH CAPg REEXAM AFTER WELD
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| -
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| BLENDING FOR ZSZ" ACCEPTABLE. ALL INDICATIONS ARE FROM FABRICATION PROCESS'OT SERVICE INDUCED.
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| All, 2-IN+ EXCESS LETDOWN LINE DRAWINGS! A-22 Summary Exam Item NDE Number Categ Number Component Component Type Exam 055800 B-J B9.40 4 ASME PT PZPE-TO-VALVE 541 WELD 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
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| A12 ~ REACTOR COOLANT PUMP A: DRAWINGS! A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 057030 B-K-1 B10.20 SUPPORT P3 OE PT INTEGRAL ATTACHMENT 92 INSIGNIFICANT: RANDOM ROUNDED INDICATION <1/16" DIAMETER. UNABLE TO ACCURATELY LOCATE INDICATIONS DUE TO INABILITY TO TOTALLY ACCESS WELD DUE TO CLOSENESS OF WALL 6 INSULATZON. ZNNER WEB VIEWED 75% THROUGH MIRROR.
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| THE REMAINING 25't VIEWED DIRECTLY ACCEPTABLE'
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| Re E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Znterval, Third Outage 1992 ATTACHMENT I'LASS 1 COMPONENTS CONT.
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| A13 o REACTOR COOLANT PUMP B DRAWINGSt *****
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| Summary Exam Item Number Categ Number Component Component Type 058100 FLYWHEL'RG-1.14 FLYWHEEL AUG PT S/N 212-3D19156-Gol-02 UT 92 REMOVED ZN 1990 AND REPLACED WITH "SPARE" (ID 212-3D19156-G01-02). UT 6 PT ON SPARE ACCEPTABLE BEFORE REPLACEMENT IN RCP "B" IN 1990'AKING CREDIT THIS OUTAGE FOR EXAMINATIONS.
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| 058110 FLYWHEL RG-1.14 ANTI-ROTATION PAWLS AUG PT PAWLS (11) 92 REMOVED ZN '90 AND REPLACED WITH SPAREg IDP'8 252g253~ 254 WITH 2 PAWLS NO ID k. TAKING CREDIT THIS OUTAGE FOR EXAMINATIONS'14
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| ~ VALVES . DRAWINGS! A-9 Summary Exam Item NDE Number Categ Number Component Component Type Exam 060300 431A, COPES-VULCAN OE VT-1 CONTROL VALVE 92 BASELINE EXAMS FOR NEW STUDS AND NUTS' STUDS 1 1/4"-8 X 6" LONG, SA-453GR660. 8 NUTS 1 1/4"-8, SA-193GRB6. ACCEPTABLE.
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| Re Ee GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I B, CLASS 2 COMPONENTS'l
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| ~ STEAM GENERATOR A DRAWINGS i B 1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 070900 C-A C1.10 LST-A ASME UT LOWER SHELL-TO- UT TRANSZTZON WELD 92 NO RECORDABLE 6 GEOMETRY SPOT ZNDICATZONS. I-98 AND MANUAL UT EXAMINATIONS PERFORMEDi GREATER THAN 90't OF EXAMINATION COVERAGE OBTAINED ACCEPTABLE'71100 C-A C1.20 USH-A, UPPER UT SHELL-TO-HEAD WELD UT 92 NO RECORDABLE ZNDICATZONSi OTHER) WELD INCLUSIONS. I-98 AND MANUAL UT EXAMZNATZONS PERFORMED. MID-VOLUME INDICATION 1.125" X .250"i EVALUATED PER ASME SECTION XIi IWC 3510 li 1986 EDITION ACCEPTABLE'2o SEAL WATER RETURN FILTER DRAWINGS s B-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 072580 L4 OE VT-3 SUPPORT LEG ¹ 4 92 REJECTi LINEAR INDZCATZON ZN START/STOP AREA OF LOWER SUPPORT WELD/ 1/8 LONG ON LEFT ATTACHMENT WELD, 1/8" LONG ON LOWER RIGHT ATTACHMENT WELD.
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| OTHER: REJECT EVALUATED PER ASME SECTION XZ, 1986 EDITION STANDARDS OF IWC-3500 ACCEPTABLE. REJECT NOT SERVICE INDUCED'72900 L4 OE PT SUPPORT LEG ¹'
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| 92 RE JECT i LINEAR INDICATIONS IN START/STOP AREA OF LOWER SUPPORT WELD i 1 /8 LONG AT LEFT ATTACHMENT WELD i 1 /8 LONG LOWER RIGHT ATTACHMENT WELD ~
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| REJECT EVALUATED PER ASME SECTION XZi 1986 EDITION STANDARDS OF IWC-3510-3 ACCEPTABLE. REJECT NOT SERVICE INDUCED+
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| e 0
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| Ro E>> GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT ~
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| B3o REACTOR COOLANT FILTER DRAWINGS ! B-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 074300 FUHRCF, FLANGE- OE UT TO-UPPER HEAD WELD 92 NO RECORDABLE INDICATIONS) WELD CROWN GEOMETRY'EAD SIDE ONLY, DUE TO
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| ,
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| CONFIGURATION OF HEAD. GREATER THAN 90't EXAMINATION COVERAGE OBTAINED ACCEPTABLE.
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| B4 ~ PULSE DAMPENER DRAWINGS i B-6 Summary Exam Number Categ Item Number Component'DE Component Type Exam 075200 C-B C2.21 CF-N1 ASME PT NOZZLE WELD UT 92 PT/UT LIMITED EXAMINATIONS FROM 21" TO 31" DUE TO WELDED SUPPORT BRACKET INTERFERENCE. 70% OF EXAMINATION COVERAGE CAN ONLY BE OBTAINED+ RELIEF REQUEST f19 GENERATED TO ACCEPT THIS "AS BUILT" CONDITION, NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 075250 C-B C2.22 CF-N1 ASME UT NOZZLE INSIDE RADIUS 92 - UT: LIMITATION NO EXAMINATION FROM 21" TO 31" DUE TO COMPONENT CONFIGURATION/WELDED SUPPORT. 70t OF EXAMINATION COVERAGE CAN ONLY BE OBTAINED. RELIEF REQUEST f19 GENERATED TO ACCEPT THIS "AS BUILT" CONDITION.
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| NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 075400 C-B C2.21 CF-N3 OE PT NOZZLE WELD UT 92 PT: NO RECORD INDICATIONS ACCEPTABLE'T!NO RECORDABLE EXAMINATION DUE TO CONFIGURATION (CLOSENESS OF CF-N2 NOZZLE).
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| INDICATIONS'IMITED 80 7t OF EXAMINATION COVERAGE CAN ONLY BE OBTAINED. RELIEF REQUEST if19 GENERATED TO ACCEPT THIS "AS BUILT" CONDITION. NO RECORDABLE INDZCATZONS-ACCEPTABLE.
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| 10
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| Ro E ~ GZNNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT, PULSE DAMPENER (CONT.) DRAWINGS! B-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 076200 C-F-1 C5.11 1 OE PT CAP-TO-PIPE WELD UT 92 PT: NO RECORD INDICATIONS ACCEPTABLE. UT! LIMITATIONS ONLY 11-1/2" OF WELD ACCESSZBLE DUE TO GRATING & PIPE SUPPORT. NO RECORDABLE INDZCATIONS
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| & GEOMETRY - ACCEPTABLE.
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| 076900 C-F-1 C5.11 3 OE PT ELBOW-TO-PIPE WELD 'UT 92 PT/UT: NO RECORDABLE INDICATIONS ACCEPTABLE.
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| 077600 F-B F2.30 CVU-412 OE VT-3 RIGID RESTRAINT 92 I RE JECT ~ ARC STRIKES g WELD UNDERS ZE g STAINLESS STEEL PLATE IS LIFTED FROM LOWER SUPPORT PADS & PLATES'OT SERVICE INDUCED BUT CONSTRUCTION.
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| NCR92-163 GENERATED FOR RESOLUTION. ENGINEERING USE-AS-IS FOR ITEMS g 1, 2i 4 & 5. ITEM P3, TIGHTEN NUT TO CLOSE GAP ON PLATE BUT CANNOT TIGHTEN NUT.
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| INTERIM USE AS IS APPROVED'XPIRES JUNE 94 ~ REEXAMINATIONS NO RECORDABLE INDICATIONS & REJECTABLE DUE TO LOOSE ANCHOR STUDS. NCR92-241 APPROVED ZNTERZM USE-AS-ISi EXPIRES JUNE '94+
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| GENERATED'NGINEERING B5." MAIN STEAM LOOP A DRAWINGS! B-9 Summary Exam Item NDE Number Categ Number Component Component Type Exam 080800 F-C F3.50 MSU-46 ASME VARIABLE (SPRING) 92 SIZE 16 TEMPERATURE 82 DEGREES F., SETTING 5/8" = 5725 LBS- ACCEPTABLE.
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| 081310 C-C C3.20 MSU-44 ASME STANCHION TO PIPE INTEGRAL ATTACHMENT 92 INSIGNIFICANT: SLIGHT UNDERCUT BETWEEN PASSES DUE TO STRINGER PASS WELD)
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| <1/64" DEEP ACCEPTABLE.
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| 11
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| Re E ~ GZNNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT MAIN STEAM LOOP A (CONT ~ ) DRAWINGS'-9 Summary Exam Item NDE Number Categ Number Component Component Type Exam 081600 F-C F3.50 MSU-42 ASME VT-3 VARIABLE (SPRING) 92 SIZE 17 TEMPERATURE 82 DEGREES F., SETTING 3-3/4" ~ 8554 LBS.
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| INS IGN IF ICANT J 0 CLEARANCE ON ROD g NO WEAR ACCEPTABLE ~
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| 082200 C-F-2 C5.51 G OE UT PIPE-TO-TEE WELD VT-1 MT 92 - VT/MT: INSIGNIFICANT'RC STRIKE <1/32" DEEP AT 62 3/4" OFF CENTER LINE ON TEE ACCEPTABLE'TJ NO RECORDABLE INDICATIONS ACCEPTABLE'82300 C-F-2 C5.51 Gi ASME RT TEE-TO-CAP WELD VT-1 MT 92 VTg INSIGNIFICANT'OUGES g CIRCULAR FROM LINE UP FIXTURE AT 16 g 34 1/2 g 66 1/4 6 83 ~ ALL 1/4 DIAMETERS < 1/36 DEEP ACCEPTABLE ~
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| MT/RT: NO RECORDABLE INDICATIONS ACCEPTABLE.
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| B6 ~ MAIN STEAM LOOP A TO AUX FW PUMP TURBINE DRAWINGS ! B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 083800 C-F-2 C5. 51 G2-BC-1-A ASME RT PIPE-TO-VALVE 3505 MT WELD VT-1 92 VT/MT) NO RECORDABLE INDICATIONS ACCEPTABLE. RTt NO RECORDABLE INSIGNIFICANT'NTERNAL CONCAVITY'OROSITY'XCESSIVE PENETRATION
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| - ACCEPTABLE.
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| 084320 F-C F3.50 MSU-58 OE MECHANZCAL SNUBBER 92 VT PSA 3g SETTING 2 1/8 g TEMPERATURE 350 DEG F~ BASELINE ACCEPTABLE'2
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| R o E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT Z CLASS 2 COMPONENTS
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| ~ CONT. t B7+ MAIN STEAM LOOP B DRAWINGS' 8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 084400 C-F-2 C5.51 A ASME UT NOZZLE-TO-ELBOW WELD VT-1 MT 92 'VT/MT NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS'OOT GEOMETRY) RADIOGRAPHS FROM PAST YEARS HAVE BEEN REVIEWED AND SHOW A DEFINITE ROOT AND COUNTERBORE CONDITION - ACCEPTABLE' 087650 F-C F3 '0 MSU-26 MECHANICAL SNUBBER ASME 92 VT RE JECT j INDICATOR TUBE LOOSE g APPEARS TO BE PHYSICAL ABUSE ~ NOT SERVICE INDUCED. NCR92-223 GENERATED AND SNUBBER REPLACED WITH PSA-35.
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| VT RE-EXAMINATION) TOP SERIAL NUMBER 9355 TEMPERATURE 137 DEGREES F.i SETTING 3 3/8"y BOTTOM SERIAL NUMBER 4686) TEMPERATURE 137 DEGREES Fog SETTING 3 1/4" ACCEPTABLE PER ENGINEERING. RE-LOOK AT TEMPERATURE, ACCEPTABLE AT 425 DEGREES F g SETTING 1 9/16 TOP 6 1 1/8 BOTTOM 087655 C-C C3.20 MSU-26 ASME MT STANCHION TO PIPE . PT INTEGRAL ATTACHMENT 92 MT'IMITED EXAMINATION ON TOP 6 BOTTOM INTEGRAL ATTACHMENT~ PTi COMPLETED COMPLETED EXAMINATIONS ON RESTRZCTED AREAS. MT 6 PTg NO RECORDABLE
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| -
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| INDICATIONS ACCEPTABLE.
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| 088200 F-C F3.50 ,MSU-30 ASME VARIABLE (SPRING) 92 - SIZE 19. TEMPERATURE 70 DEGREES F., SETTING 13597 LBS. ACCEPTABLE.
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| 13
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| Ro E. GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT, t MAIN STEAM LOOP B (CONT.) DRAWINGS i B-8/10/10A Summary Exam Item NDE Number Categ Number Component Component Type Exam 088830 F-B F2.40 MSU-33 ASME VT-3 GUIDE 92 REJECTS UNABLE TO ROTATE NORTHWEST CORNER BOLTS (6) BY HAND ~
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| NORTHWEST CORNER PLATE NOT GROUND PER DRAWING. REJECT NOT SERVICE INDUCED+
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| NCR 92-141 GENERATED) BOLTS WERE REMOVED, CLEANED AND REINSTALLED. RE-EXAMINATION ACCEPTABLE FOR BOLTS P'S 1 6 3. BOLTS f'S 2g 4g 5 6 6 CAN BE ROTATED WITH A WRENCH. ACCEPTABLE PER IOC 5/4/92 PARA 3~ USE-AS-ZS ~
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| 088835 C-C C3.20 MSU-33 OE MT GUSSET TO PIPE VT-1 INTEGRAL ATTACHMENT 92 MT: NO RECORDABLE INDICATIONS. LIMITED EXAM DUE TO COMPONENT SUPPORT.
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| ALL ACCESSIBLE AREAS EXAMINED AND ACCEPTABLE. VT: SUPPLEMENTAL EXAM OF INTEGRAL ATTACHMENT, LIGHT RUST, ACCEPTABLE 089600 C-F-2 C5.81 L3-BC-1 OE MT 6" BRANCH WELD VT-1 92 VT/MT! NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| B8. FEED WATER LOOP A DRAWINGS'-12 Summary Exam Item NDE Number Categ Number, Component Component Type Exam 093100 F-C F3.50 FWU-2 ASME VARIABLE (SPRING) 92 REJECTS BENT HANGER ROD NEAR TOP, NO MEASUREMENT OBTAINED DUE TO REMOTE EXAM. NCR92-147 GENERATED, ENGINEERING FIELD INSPECTION DETERMINED THAT ROD DEFORMATZON IS MINIMAL AND APPEARS TO HAVE ORIGINATED FROM CONSTRUCTION ACTIVITIES'OT SERVICE INDUCED'SE AS IS PER ENGINEERING'-F-2 094300 C5.51 EE OE UT ELBOW-TO-NOZZLE WELD VT-1 MT 92 MT/VT: NO RECORDABLE ZNDICATIONS ACCEPTABLE. UT: OTHER)
| |
| EXAMINED FOR THICKNESS AND COVERAGE PROFILE ONLY. NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 14
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| | |
| I R. E ~ GZNNA NUCLEAR POWER PLANT
| |
| 'i 1 Inspection Report 1990 - Znservt.ce 1999 Interval, Thi.rd Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT.
| |
| B9 ~ FEED WATER LOOP B DRAWINGS'-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 094500 C-F-2 C5.51 L ASME RT, 3992 VALVE-TO-PIPE VT-1 MT 92 VT/MT: NO RECORDABLE INDICATIONS ACCEPTABLE. RT: INSIGNIFICANT:
| |
| BACKING RING WASHOUT, 15" TO 24" & 38" TO 40" SIGNS OF EROSION ACCEPTABLE.
| |
| 095200 F-B F2.30 FWU-45 ASME VT-3 RIGID RESTRAINT 92 INSIGNIFICANT: GREASE FITTINGS PAINTED OVER ON STRUT RESTRAINT.
| |
| STRUT PIPE ZS AGAINST STEEL BEAM PLATFORM - ACCEPTABLE+ NO APPARENT WEAR. NEW ID TAG INSTALLED BY MEIS.
| |
| 095900 F-B F2.30 FWU-49 ASME VT-3 RIGID RESTRAINT 92 INSIGNIFICANT: PIGEON FECES ACCEPTABLE.
| |
| . 096300 F-C F3.50 FWU-51 ASME VT-3 MECHANICAL SNUBBER 92 INSIGNIFICANT: PIGEON FECES. SERIAL NUMBER 7483'EMPERATURE 140 DEGREES F~ ~ SETTZNG 3 1/8 g PSA 35 ACCEPTABLE'96305 C-C '3.20 FWU-51 ASME MT GUSSET TO PIPE INTEGRAL ATTACHMENT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 096525 F-C F3.50 FWU-54 OE VT-3 MECHANICAL SNUBBER 92 VT PSA 35 g SETTING 3 7/8 ~ TEMPERATURE 350 DEG F g PIGEON FECES ON HOUSING, NO ID TAG BASELINE ACCEPTABLE+
| |
| 15
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| Ro E ~ GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT $
| |
| FEED WATER LOOP B (CONT.) DRAWZNGS$ B-13/14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 096600 F-B F2 '0 FWU-55 RIGID HANGER OE 92 NO RECORDABLE ZNDICATIONS$ THE CHANGE IN HOLE SIZE FROM 1-3/4" TO 2" COMPLETED FOR NCR92-012 AMENDED DISPOSITION INSIGNIFICANT$ PIGEON FECES '- ACCEPTABLE.
| |
| 098100 F-C F3.50 FWU-11 ASME VT-3 VARIABLE (SPRING) 92 - REJECT: LACK OF THREAD ENGAGEMENT BY 3 THREADS ZN LOWER CLAMP BOLTS UPPER LUG ATTACHMENTS BOTTOM OF BEAMED SPREAD OUT NCR92 142 GENERATED FOR RESOLUTION 6 REWORK PERFORMED. REEXAMINATION PERFORMED, INSIGNIFICANT)
| |
| UPPER LUG ATTACH STILL SPREAD OUTi USE-AS-IS PER ENGINEERING+ ALL ZNDZCATZONS ARE FROM CONSTRUCTION/FABRICATION PROCESS, NOT SERVICE INDUCED ACCEPTABLE.
| |
| 099000 F-C F3.50 FWU-7 ASME VT-3 VARIABLE'(SPRING) 92 SIZE 13, TEMPERATURE 65 DEGREES F., SETTING 4 5/8"= 2498 LBS ACCEPTABLE.
| |
| 099005 C-C C3.20 FWU-7 ASME MT GUSSET TO PIPE INTEGRAL ATTACHMENT 92 INSIGNIFICANT/ WELD SPATTER - ACCEPTABLE. UNDERCUT: < 1/32" DEEP X 3/16" LONG 6 3/64" DEEP X 1/8" LONG. EVALUATED PER ASME SECTION XI, TABLE ZWB-3514-1, -ACCEPTABLE.
| |
| 099900 C-F-2 C5.51 BB AUG VT-1 ELBOW-TO-NOZZLE WELD MT UT 92 VT/MT$ NO RECORDABLE INDZCATIONS ACCEPTABLE. UT$ GEOMETRY'D:ROOT GEOMETRY UPSTREAM 6 ZD COUNTERBORE DETECTED'O DOWNSTREAM EXAMINATIONDUE TO NOZZLE CONFIGURATION ACCEPTABLE.
| |
| 16
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| Ro E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Third Outage 1992-ATTACHMENT I CESS 2 COMPONENTS CONT. t B10o 6-ZN. SAFETY INJECTION SYSTEM (LOW HEAD) DRAWINGS' 18 Summary Exam Item NDE Number Categ Number Component Component Type Exam 111100 F-B F2 '0 RHU-11 RIGID HANGER ASME VT-3 92 NO RECORDABLE INDICATIONS -
| |
| ACCEPTABLE'11500 F-B F2.30 RHU-15 ASME VT-3 RIGID RESTRAINT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 111550 F-C F3.50 RHU-16 ASME VT-3 VARIABLE (SPRING) 92 SZ ZE 8 ~ SETTZNG 3/4 g LOAD 6 1 4'CCEPTABLE ~
| |
| 112300 F-B F2.10 RHU-19 ASME VT-3 U-BOLT 92 RESOLUTION OF NCR 91-162. INSIGNIFICANT! GAP ON PRINT SHOWS "0" TYPICAL".
| |
| ACTUAL IS 0.037" ON RIGHT AND 0.042" ON LEFT - ACCEPTABLE.
| |
| Bile RESIDUAL HEAT REMOVAL LINE 8FF-AC-151 DRAWINGS! B-20 Summary Exam Item NDE Number. Categ Number Component Component Type Exam 126700 9 OE PT TEE-TO-CAP WELD 92 PTg NO RECORDABLE INDICATIONS ACCEPTABLE ~ UT j PIPE ZS SCHEDULE 80 g NO CAL BLOCK AVAILABLE~ RESCHEDULE TO 1 9 93 AIGO o 17
| |
| | |
| Re E ~ GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT.
| |
| B12 ~ RESIDUAL HEAT REMOVAL LINE 6E-AC-151 DRAWINGS t B-21 Summary Exam Item NDE Number Categ Number Component Component Type Exam 128125 RHU-83 OE VT-3 RIGID RESTRAINT 92 - ZNSZGNIFICANT: NO CLEARANCE ON NORTH ENDi 1/8" GAP ON SOUTH END ACCEPTABLE.
| |
| 128150 RHU-84 OE GUIDE 92 - INSIGNIFICANT'O CLEARANCE ON NORTH SIDE OF GUZDEg 1/8" CLEARANCE ON SOUTH SIDE - ACCEPTABLE. EXAM AFTER BORIC ACID REMOVAL) INSIGNIFICANT:
| |
| GENERAL CORROSION ON BASE PLATE~ SLZGHT CORROSION ON STUDS 6 NUTS CAN' BE TURNED BY HANDq SECURE IN FLOOR. ZNDZCATZONS NOT SERVICE INDUCED ACCEPTABLE.
| |
| B13o RESIDUAL HEAT REMOVAL LINE 8F-AC-151 DRAWINGS! B-20A Summary Exam Item NDE
| |
| .Number Categ Number Component Component Type Exam 128700 6 OE PT PIPE-TO-TEE WELD 92 PT g NO RECORDABLE INDZCATIONS ACCEPTABLE ~ UT PIPE IS SCHEDULE 80 g NO CAL BLOCK AVAILABLE, RESCHEDULE TO 1993 AZGO.
| |
| 128800 7 OE PT TEE-TO-CAP WELD 92 PTj NO RECORDABLE INDICATIONS ACCEPTABLE'Tg PIPE IS SCHEDULE 80/
| |
| NO CAL BLOCK AVAILABLE, RESCHEDULE TO 1993 AIGO.
| |
| 18
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| Ro Eo GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT.
| |
| B14o RESIDUAL HEAT REMOVAL LINE 6K-AC-151 DRAWINGS'-21 Summary Exam Item NDE Number Categ Number Component Component Type Exam, 129950 RHU-94 OE GUIDE 92 REEXAM AFTER REMOVAL OF BORIC ACZD RESIDUE. INSIGNIFICANT; GENERAL CORROSION ON BASE PLATE, ORIGINAL PAINT ON PLATE. SOME SLIGHT CORROSION ON STUDS 6 NUTS, CAN'T BE TURNED BY HAND, SECURE IN FLOOR, NOT SERVZCE INDUCED ACCEPTABLE.
| |
| B15 ~ RESIDUAL HEAT REMOVAL LINE 10A-AC-601 DRAWINGS'-20A Summary Exam Item, NDE Number Categ Number Component Component Type Exam 135500 F-C F3.50 RHU-81 ASME VT-3 VARIABLE SPRING 92 SIZE 12 g TEMPERATURE 102 DEGREES F g SETTING 1/8 g LOAD 1469 LBS ACCEPTABLE.
| |
| B16o RESIDUAL HEAT REMOVAL LINE 8B-AC-601 DRAWINGS'-23 Summary Exam Item NDE Number Categ Number Component Component Type Exam 138800 C-F-1 1A OE PT 6" FLANGE-TO-REDUCER UT WELD 92 PT/UTg NO RECORDABLE INDZCATIONS ACCEPTABLE B17 ~ RESIDUAL HEAT REMOVAL LINE 10H-AC-601 DRAWINGS t B-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 140925 F-B F2.30 RHU-40 ASME VT-3 ANCHOR 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 19
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| 0 0
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| | |
| R. E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT.
| |
| RESZDUAL HEAT REMOVAL LINE 108-AC-601 (CONT+) DRAWINGS'-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 140930 C-C C3.20 RHU-40 ASME PT LUG WELDS INTEGRAL ATTACHMENTS 92 NO RECORDABLE INDICATIONS - ACCEPTABLE. (TEMPERATURE/PT VERIFIED WITH COMPARATOR BLOCK .005".)
| |
| B18 ~ RESIDUAL HEAT REMOVAL LINE SA-AC-601 DRAWINGS'-26 Summary Exam Ztem NDE Number Categ Number Component Component Type Exam 145500 C-F-1 1F OE PT PIPE-TO-ELBOW WELD UT 92 PT: LIMITATION FROM 4" TO 10" CW FROM TOP OF WELD Ec NO BACKSIDE EXAMINATION. UTg ONE SIDED EXAMINATZONi LIMITATION ELBOW SIDE RESTRICTED ACCESS'T 6t UTi NO RECORDABLE INDZCATIONS ACCEPTABLE'19 o RESIDUAL HEAT REMOVAL LINE 6D-AC-601 DRAWINGSt B-26 Summary Exam Item NDE Number Categ Number Component Component Type Exam 147900 F-B F2.30 RHU-95 ASME VT-3 ANCHOR 92 NO RECORDABLE INDICATIONS ACCEPTABLE. OTHER'S LUGS WELDED ON PIPE DO NOT SHOW ON DRAWING.
| |
| 147910 C-C C3.20 RHU-95 ASME PT ANCHOR VT-1 INTEGRAL ATTACHMENTS 92 PT INTEGRAL ATTACHMENTSi NO RECORDABLE INDICATIONS ACCEPTABLE ~ PT LUGS ON PIPE - REJECT) COLD LAP 6 SLAG CAUSZNG LINEAR INDICATIONS 6 ARC STRIKES. NCR92-127 GENERATED Ec REPAIRS PERFORMED'NDICATIONS ARE NOT SERVICE INDUCED BUT ARE CONSTRUCTIONS REEXAMINATIONi VT INDICATIONS ACCEPTABLE. PT: LINEAR INDICATIONS, USE-AS-IS PER li NO RECORDABLE ENGINEERING ACCEPTABLE.
| |
| 20
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| Ro Ee GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Znterval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT. t
| |
| "
| |
| B20+ RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS t B-25 J
| |
| Summary Exam Item NDE Number Categ Number Component Component Type Exam 152800 F-C F3.50 RHU-53 ASME VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 1 5754 g TEMPERATURE 73 DEGREES F ~ SETTING 2 5/8 PSA-3 ACCEPTABLE.
| |
| 152820 9A OE PT 3/4" BRANCH WELD TO VALVE 958 92 NO RECORDABLE ZNDZCATZONS, ACCEPTABLE.
| |
| B21. L+Po SAFETY INJECTION LINE 6B-SZ-151 DRAWZNGSt B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 159700 C-F-1 7 OE PT TEE-TO-PIPE WELD UT 92 PT/UTg NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| B22. L.P. SAFETY INJECTION LINE 8A-SI-151 DRAWZNGSt B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 160460 C-F-1 4 OE PT ELBOW-TO-FLANGE WELD UT 92 PT/UTI NO RECORDABLE ZNDZCATIONS ACCEPTABLE.
| |
| 21
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| 0 Ro Eo GZNNA NUCLEAR POWER PLANT 1990 - Znservice,Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT.
| |
| B23 ~ HoP ~ SAFETY INJECTION LINE 3A SZ 150 1 DRAWINGS'-37 Summary Exam Item NDE Number Categ Number Component Component Type Exam 161000 C-F-1 C5.21 1 ASME PT SZ PUMP "A", OUTLET UT FLANGE TO ELBOW WELD 92 PT/UTg NO RECORDABLE INDICATIONS - ACCEPTABLE+
| |
| B24 ~ 8 P. SAFETY INJECTION LINE 4D-SI-1501 DRAWINGS: B-38 Summary Exam Item NDE Number Categ Number Component Component Type Exam 161520 F-B F2.30 SIU-41 ASME VT-3 RIGID RESTRAINT 92 REJECT) BENT ROD. NCR 92-245 GENERATED FOR RESOLUTION. ENGINEERING RESOLUTION OF NCR INDICATED THAT THE SUPPORT IS ONLY USED TO 301L OF OVERALL CAPACITY. BENT CONDITION APPEARS TO BE FROM CONSTRUCTION ACTIVITIES 6 NOT SERVICE INDUCED. USE-AS-IS PER ENGINEERING ACCEPTABLE.
| |
| 161570 C-F-1 C5.21 40 ASME PT PIPE-TO-ELBOW WELD UT 92 PT/UTp NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| B25 ~ H+P, SAFETY ZNJECTZON LINE 2T-SZ-2501 DRAWINGS! B-39 Summary Exam Item NDE Number Categ Number Component Component Type Exam 161760 C-F-1 C5.30 6 OE PT PIPE-TO-TEE WELD 92 REJECTS ARC STRIKES ON TEE AND PIPE. NCR 92-182 GENERATED FOR RESOLUTION.
| |
| INDICATIONS NOT SERVICE INDUCED BUT CONSTRUCTION. REWORK PERFORMED'RC STRIKES REMOVED. REEXAMINATION) NO RECORDABLE INDICATIONS Sc NO NOTICEABLE WALL LOSS ACCEPTABLE.
| |
| 161830 F-B '2.10 SIU-34 U-BOLT ASME VT-3 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 22
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| | |
| Ro Ee GZNNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT ~
| |
| H.PE SAFETY ZNJECTZON LINE 2T-SZ-2501 (CONT+) DRAWZNGSt B-39 Summary Exam Item NDE Number Categ Number Component Component Type Exam 161850 C-F-1 C5.30 14 ASME PT ELBOW. TO PIPE 92 - REJECT'RC STRIKES'CR92-184 GENERATED FOR RESOLUTION. RE-EXAMINATION
| |
| 'AFTER REWORK NO RECORDABLE ZNDZCATIONS - ACCEPTABLE. INITIAL FINAL UT THICKNESS - NO NOTICEABLE WALL LOSS.
| |
| B26. HAP+ SAFETY INJECTION LINE 2A-SI-1501 DRAWINGS! B-39 Summary Exam Item NDE Number Categ Number Component Component Type Exam 162000 C-F-1 C5.30 20 OE PT 2" REDUCING TEE-TO-PZPE WELD 92 REJECT: ARC STRIKES, NCR92-185 GENERATED FOR RESOLUTION. RE-EXAMINATION AFTER REWORK - NO RECORDABLE INDICATIONS - ACCEPTABLE. INITIAL Ec FZNAL UT THICKNESS NO NOTICEABLE WALL LOSS.
| |
| B27 ~ H,P, SAFETY INJECTION LINE 2U-SZ-2501 DRAWZNGSS B-39 Summary Exam Item NDE .
| |
| Number Categ Number Component Component Type Exam 162160 C-F-1 C5". 30 35 ASME PT ELBOW-TO-PIPE WELD 92 NO RECORDABLE INDICATIONS'IU-31 HANGER OVER WELD WAS MOVEDg PAINT WAS REMOVED FOR THE EXAMINATION UNDER WOE 9250073 ACCEPTABLE.
| |
| B28 ~ H o P ~ SAFETY INJECTION LINE 3B SZ 150 1 DRAWINGS'-40 Summary Exam Item NDE Number Categ Number Component Component Type Exam 162690 C-F-1 C5.21 13 ASME PT EIBOW-TO-PIPE WELD UT 92 PT/UTy . NO RECORDABLE INDICATIONS. UT LIMITATION 1.5" TO 5" DUE TO INSIDE RADIUS OF, ELBOW. 100t OF COVERAGE OBTAINED FROM PIPE SIDE ACCEPTABLE.
| |
| 23
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| 0 Ro Eo GINNA NUCLEAR POWER PLANT Znservice Inspection Report, 1990' 1999 Interval, Third Outage 1992 ATTACHMENT I CKASS 2 COMPONENTS CONT B29 ~ 8+P+ SAFETY INJECTION LINE 3C-SZ-1501 DRAWINGS i B-41 Summary Exam Item Number Categ 'umber. Component Component Type 163020 F-B F2.10 SZU-85 ASME VT-3 RIGID SUPPORT 92 REJECT) LOCKING NUT ON TOP INSTEAD OF BOTTOM PER PRINT, NCR92-118 GENERATED FOR RESOLUTION. EVALUATION INDICATED THAT THE JAM NUT LOCATION ZS ACCEPTABLE 6 THAT THE LOCKING NUT ON TOP ZS PERFORMING THE INTENDED FUNCTIONS OPERABILITY NOT IMPAIRED, USE-AS-IS PER ENGINEERING. THE REJECT IS NOT SERVICE INDUCED ACCEPTABLE.
| |
| 163021 C-C C3.20 SIU-85 ASME PT LUG-TO-PIPE INTEGRAL ATTACHMENT 92 REJECTS COLD LAP INDICATIONS ON NORTH 6 SOUTH SIDES, 3/4" LONG 6 AT BOTTOM OF LUG. NCR 92-130 GENERATED FOR RESOLUTION. REPAIRS WERE PERFORMED, RE-EXAMINATION INDICATED NO RECORDABLE INDICATIONS ACCEPTABLE. INDICATIONS WERE NOT SERVICE INDUCED BUT CONSTRUCTION.
| |
| B30o H.PE SAFETY INJECTION LINE 3D-SZ-1501 DRAWINGSt B-41 Summary Exam Item NDE Number Categ Number Component Component Type Exam 163290 F-B F2.30 SZU-71 ASME VT-3 RIGID SUPPORT 92 NO RECORDABLE INDICATIONS - ACCEPTABLE.
| |
| 163291 C-C C3.20 SIU-71 ASME PT LUG-TO-PIPE INTEGRAL ATTACHMENT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| B31 ~ 8+PE SAFETY INJECTION LINE 2D-SZ-1501 DRAWINGS t B-44 Summary Exam Item NDE Number Categ Number Component Component'ype Exam 164500 C-F-1 C5.30 1 OE PT TEE-TO-PIPE WELD 92 NO RECORDABLE INDICATIONS ACCEPTABLE. EXAM TEMPERATURE QUALIFIED WITH COMPARATOR BLOCK.
| |
| 24
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| Ri E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT. t B32 ~ HoP ~ SAFETY INJECTION LINE 2S-SZ-2501 DRAWINGSt B-44 Summary Exam Item NDE Number Categ Number Component Component Type Exam 164600 C-F-1 C5.30 10 ASME PT PIPE-TO-TEE WELD 92 NO RECORDABLE INDICATIONS ACCEPTABLE. EXAM TEMPERATURE QUALIFIED WITH COMPARATOR BLOCKh B33 h H.P ~ SAFETY INJECTION LINE 2R-SI-2501 DRAWINGS'-45 Summary Exam Item NDE Number Categ Number Component Component Type Exam 164910 C-F-1 C5.30 11 OE PT PIPE-TO-ELBOW WELD 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| B34h RESIDUAL HEAT EXCHANGER 1A DRAWINGS c B-109 Summary Exam Item NDE Number Categ Number Component Component Type Exam 169040 C-B C2.33 ZNSRHE-1A ASME VT-2 INLET NOZZLE-TO-SHELL 92 NO RECORDABLE INDICATZONS TEST SATISFACTORY.
| |
| 169050 C-B C2. 33 ONSRHE-1A ASME VT-2 OUTLET NOZZLE-TO-SHELL h
| |
| 92 NO RECORDABLE INDICATIONS TEST SATISFACTORY.
| |
| 169190 ---- ---- 1A-BT OE VT-1 BOLTING UT 92 VT-1; INSIGNIFICANT, HEAVY SURFACE RUST - NO STUD/NUT DEGRADATION.
| |
| BORON DEPOSITS AT FLANGE INTERFACE WITH 3/16" MAXIMUM GAP. TOP SIDE 2 STUDS SHOW 1/2 THREAD, 6 STUDS SHOW 1 THREAD ACCEPTABLE UTg 'O RECORDABLE INDICATIONS ACCEPTABLE'5
| |
| | |
| Ro Ee GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Third Outage 1992, ATTACHMENT I CLASS 2 COMPONENTS CONT.
| |
| B35e RESIDUAL HEAT EXCHANGER 1B DRAWINGS! B-109 Summary Exam Item Number Categ Number Component 'Component Type 169240 C-B C2.33 ZNSRHE-1B OE INLET NOZZLE-TO-SHELL 92 - NO RECORDABLE INDICATIONS TEST SATISFACTORY.
| |
| 169250 C-B C2.33 ONSRHE-1B OE VT-2 OUTLET NOZZLE-TO-SHELL 92 NO RECORDABLE INDICATIONS TEST SATISFACTORY'36
| |
| ~ CONTAINMENT SPRAY PUMP 1 DRAWINGS t N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 172010 SIAPSC1-ZFB OE UT INLET FLANGE BOLTS VT-1 92 UTg NO RECORDABLE INDICATIONS ACCEPTABLE'T ll INSIGNIFICANT@ LIGHT CORROSION ON STUDS BETWEEN FLANGES. STUDS/NUTS THREADS RANGE FROM FLUSH TO 1 THREAD UNDER, ACCEPTABLE.
| |
| 172020 SIAPSC1-OFB OE UT OUTLET FLANGE BOLTS VT-1 92 VT-lg INSIGNIFICANT, LIGHT CORROSION ON STUDS BETWEEN PIPE 6 PUMP FLANGE/
| |
| WITH 2 OF 8 STUDS ARE FLUSH WITH 1 THREAD UNDER THE NUT ACCEPTABLE. UTI NO RECORDABLE INDICATIONS ACCEPTABLE+
| |
| B37 ~ SAFETY INJECTION PUMP A DRAWINGS! B-16B/-37 Summary Exam Item NDE Number Categ Number Component Component Type Exam 172320 ---- ---- SIAPSZ-1 OE UT INLET FLANGE BOLTS VT-1 P
| |
| 92 VT-INSIGNIFICANT: LIGHT SURFACE RUST ON STUDS 6 NUTS. UT~ VT ACCEPT+ UT - IN PLACE EXAM NO RECORD ZNDIC. OTHER! MT ONLY WHEN BOLTS REMOVED - NOT REMOVED 26
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| | |
| R o E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 2 COMPONENTS CONT. t SAFETY INJECTION PUMP A (CONT+) DRAWINGS'-16B/-37 Summary Exam Item NDE Number Categ Number Component Component Type Exam 172340 SZAPSI-1 OE UT OUTLET FLANGE BOLTS VT-1 92 - VT, INSIGNIFICANT'NE STUD HAS ONE END PROTRUDING 1/2 THREAD PAST THE NUT ACCEPTABLE. UTp NO RECORDABLE INDICATIONS ACCEPTABLE 172360 ---- -- SIAPSZ-1 OE VT-1 PUMP BODE BOLTING 92 - VTp INSIGNIFICANT'IGHT CORROSION ON BOLT f12. LIMITED EXAM ON BOLT 14 WITH FOREIGN MATERZAL ON BOTTOM OF BOLT ACCEPTABLE.
| |
| B38 ~ STANDBY AUX FW THRU PEN 119 TO A S/G FWHD DRAWINGS t C-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 176221 AFU-222 (AFW-24) OE PT GUZDEg ZNTEGRAL ATTACHMENT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 176240 AFU-223 (AFW-32) OE VT-3 GUIDE 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| B39 ~ STANDBY AUX FW THRU PEN 123 TO B S/G FWHD DRAWINGS ! C-24
| |
| 'Summary Exam . Item NDE Number Categ Number Component Component Type Exam 176440 AFU-200 (AFW-05) OE VT-3 GUIDE 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| ~
| |
| 176441 AFU-200 (AFW-05) OE MT GUIDE INTEGRAL ATTACHMENT 92 MT PERFORMED ZN LIEU OF PT. PT; NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 27
| |
| | |
| Ro Eo GZNNA NUCLEAR POWER PLANT 1990 - Znservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I C. CLASS 3 COMPONENTSt Clo COMP ~ COOL+PUMPS DZSCH.TO COMP.COOL~HT EX DRAWINGS'-2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500240 D-B D2.20 CCU-90 ASME RIGID RESTRAZNT INTEGRAL ATTACHMENT 92 RE JECT UNDERSIZE WELDS i BOTTOM EAST Ec WEST ~ Ec NORTHWEST QUADRANT SLAG ZN WELDS NE g NWi SE g SWi BOTTOM EAST 6 WEST i CORROSZON ~ NCR92-13 1 GENERATED 6 REPAIRS INITIATED. ZNSIGNIFICANT: DUE TO STRINGER PASS 6c UPHAND WELDING, SLIGHT UNDERCUT BETWEEN PASSES WERE NOTED. REPAIRS ACCEPTABLE.
| |
| NOT SERVICE INDUCED.
| |
| 500245 F-A Fl. 00 CCU-90 ASME VT-3 RIGID RESTRAINT 92 INSIGNIFICANT: LIGHT CORROSION ON WELD AREA ACCEPTABLE'2
| |
| ~ AUX ~ COOLING WTR o FROM NON REG ~ HT ~ EXCH ~ DRAWINGSt C-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500300 D-B D2.20 CCU-102 ASME VT-3 RIGID HANGER INTEGRAL ATTACHMENT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 500305 F-C F3.00 CCU-102 ASME RIGID HANGER 92 - NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 500330 D-B D2.20 CCU-107 ASME VT-3 RIGID. RESTRAINT IA 92 ZNSZGNZFICANTi WEST SZDE NO SHIM, GAP ( 1/16"-
| |
| ACCEPTABLE'00335 F-C . F3.00 CCU-107 ASME RIGID RESTRAINT 92 - NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 28
| |
| | |
| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 3 COMPONENTS CONT. t C3 ~ AUX~ COOLING WTR o TO NON REG o HT ~ EXCH ~ DRAWINGSt C-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500465 F-C F3.00 CCU-179 OE VT-3 VARIABLE SPRING 92 RE-EXAM AFTER REWORK TO MOVE CONDUZT AWAY FROM ROD THAT WAS PERFORMED ON WR/TR 9100477 'EMPERATURE 58 DEGREES"F kg SETTING 0 587 LBS kg SIZE 9 ~
| |
| SUPPORT ROD HAS SMALL AMOUNT OF PAINT REMOVED AND SHOWS SIGNS OF CONTACT WITH CONDUIT. NOT ZN CONTACT NOW, NOT SERVICE INDUCED - ACCEPTABLE.
| |
| 500470 D-B D2.20 CCU-180 ASME VT-3 GUIDE INTEGRAL ATTACHMENT 92 INSIGNIFICANT) LIGHT RUST ACCEPTABLE. NEW ID TAG INSTALLED BY MEIS ~
| |
| 500475 F-A F1.00 CCU-180 ASME VT-3 GUIDE 92 - INSIGNIFICANT) LIGHT RUST ACCEPTABLE. NEW ZD TAG INSTALLED BY MEIS ~
| |
| C4. SVC WTR ~ ZNTERMED ~ BLDG 16 8 20 HDRS ~ DRAWINGS'-16 Summary Exam Item NDE Number Categ Number Component Component Type Exam 502790 D-B D2.20 SWU-323 ASME VT-3 GUIDE INTEGRAL ATTACHMENT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 502795 F-A F1.00 SWU-323 ASME VT-3 GUIDE 92 NO.RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 29
| |
| | |
| l g '
| |
| 0
| |
| | |
| Ro E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 3 COMPONENTS CONT.
| |
| C5 ~ SVC o WTR o PUMPS Ag Bg C & D DISCH ~ SCR @HOUSE DRAWINGS t C-17 Summary Exam Item NDE Number Categ Number Component Component, Type Exam 503320 D-B D2.20 SWU-618 (N729) ASME VT-3 GUIDE INTEGRAL ATTACHMENT 92 BASELINE EXAM g NO ZNTEGRAL ATTACHMENTg NO DAMAGE FROM NEW INSTALLATZON~
| |
| ITEM TO BE DELETED - NOT REQUIRED BY CODE.
| |
| 503325 F-A F1.00 SWU-618 (N729) OE GUIDE 92 BASELINE EXAM g NO INTEGRAL ATTACHMENTS NEW ID TAG INSTALLED BY MEZS ITEM TO BE DELETED NOT REQUIRED BY CODE ACCEPTABLE.
| |
| ,P 503420 D-B D2.20 SWU-628 (N739) OE VT-3 GUIDE IA 92 NO ZNTEGRAL ATTACHMENT VISIBLE ON PIPE. ITEM TO BE DELETED NOT REQUIRED BY CODE ACCEPTABLE.
| |
| CODEX'6 503425 F-A F1.00 SWU-628 (N739) OE VT-3 GUIDE MT 92 - VT'RACK IN PAINT AT TOE OF FILLET WELD. MT (AUGMENTED EXAM.) INSPECTION PERFORMED ON FILLET WELD AT PAINT CRACKS NO RECORDABLE INDICATIONS ACCEPTABLE'TEM TO BE DELETED'OT REQUIRED BY
| |
| ~ SVC.WTRe-INTERMED+BLDG.TO A & B CHZLLERS DRAWINGS t C-18 Summary Exam Item NDE Number Categ Number Component Component Type Exam 503680 D-B D2.20 SWU-390 ASME RIGID RESTRAINT GUIDE INTEGRAL ATTACHMENT 92 - NO.RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 503685 F-A F1.00 SWU-390 ASME VT-3 RIGZD RESTRAINT GUIDE 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 30
| |
| | |
| Ro E ~ GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 3 COMPONENTS CONT.
| |
| C7 ~ AUX ~ FW PUMPS DZSCH ZNTERMED ~ BLDG ~ DRAWZNGSt C-1A/1B/1D ll Summary Exam Item NDE Number Categ Number Component Component Type Exam 505390 D-B D2 ~ 20 AFU-41 ASME VT-3 GUIDE RIGID RESTRAINT INTEGRAL ATTACHMENT I
| |
| 92 NO RECORDABLE INDICATIONS ACCEPTABLE 505395 F-A Fl. 00 AFU-41 ASME VT-3 GUIDE RIGID RESTRAINT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 505490 F-C F3.00 AFU-51 ASME(ADDITIONAL) VT-3 VARIABLE(SPRING) 92 TEMPERATURE 72 DEGREES F., SETTING 3/4" ~ 200$ . SIZE 4 CONDUIT TOUCHZNG WELDED BEAM ATTACHMENT. NO OBSTRUCTION TO ACCEPTABLE'NSIGNIFICANT)
| |
| OPERATION. ADDITIONAL EXAM TO RESOLVE NCR92-131.
| |
| 505510 F-A F1.00 AFU-53 ASME(ADDITIONAL) VT-3 GUIDE 92 NO RECORDABLE ZNDlCATZONS ACCEPTABLE ADDITIONAL EXAM TO RESOLVE NCR 92-131.
| |
| 505540 D-B D2.20 AFU-56 ASME VT-3 GUIDE INTEGRAL ATTACHMENT 92 INSIGNIFICANT'AP ON EAST SIDE 1/8"i GAP ON WEST SIDE TOUCHING ACCEPTABLE'05545 F-A F1.00 AFU-56 ASME VT-3 GUIDE 92 - NO RECORDABLE INDICATIONS, ACCEPTABLE.
| |
| 505870 D-B D2.20 AFU-96 ASME VT-3 RIGID RESTRAINT INTEGRAL ATTACHMENT 92 - NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 31
| |
| | |
| Ro E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 3 COMPONENTS CONT. t AUX ~ FW PUMPS DISCH ZNTERMED ~ BLDG o ( CONT o ) DRAWINGSs C-lA/1B/1D Summary Exam Item NDE Number Categ Number Component Component Type Exam 505875 F-C F3.00 AFU-96 ASME VT-3 RIGID RESTRAINT 92 INSIGNIFICANT) ZD TAG INSTALLED BY MEZS ACCEPTABLE 505960 D-B D2.20 AFU-112 ASME VT-3 ANCHOR INTEGRAL ATTACHMENT 92 -'NSIGNIFICANT'REVIOUS INTEGRAL ATTACHMENT SUPPORT HAS BEEN CUT AND LEFT ON TOP OF PIPE, NOT SHOWN ON DRAWING ACCEPTABLE.
| |
| 505965 F-A F1.00 AFU-112 ASME VT-3 ANCHOR 92 .INSIGNIFICANT'IGHT RUST ON PIPE INSIDE 6" X 6" TUBING - ACCEPTABLE.
| |
| CS ~ STANDBY AUX FW FRM PEN 119 - AUX FW PUMP C DRAWINGS'-22 Summary Exam Item NDE Number Categ Number Component Component Type Exam 507480 F-A F1.00 AFU-157 (AFW-118) ASME ANCHOR 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 507481 D-B D2.20 AFU-157 (AFW-118) ASME ANCHOR INTEGRAL ATTACHMENT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 32
| |
| | |
| Ro E ~ GZNNA NUCLEAR POWER PLANT 1990 - Znservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 3 COMPONENTS CONT. t C9o MOTOR DRIVEN AUX ~ FW PUMP SUCTION DRAWINGS! C-33 Summary Exam Item NDE Number Categ Number Component Component Type Exam 508620 F-C F3.00 SWU-286 OE U-BOLT 92 INSULATION REMOVED,'-BOLT INSPECTED. NO RECORDABLE INDICATIONS
| |
| 'ACCEPTABLE.
| |
| C10 ~ STANDBY AUX>> FW~ SW SUPPLY TO SAFW PUMP C DRAWZNGSt C-28 Summary Exam Item NDE Number Categ Number Component Component, Type Exam 508845 D-B D2.20 SWU-596 (SW-128) ASME VT-3 GUIDE INTEGRAL ATTACHMENT 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 508847 F-A F1.00 SWU-596,(SW-128) ASME VT-3 GUIDE 92 NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| C 1 1 ~ STANDBY AUX~ FW g SW SUPPLY TO SAFW PUMP D DRAWZNGSt C-27 Summary Exam Item NDE Number Categ Number Component Component Type Exam 508870 SWU-502 (SW-90) OE VT-3 GUIDE INTEGRAL ATTACHMENT 92 INSIGNIFICANT) LIGHT CORROSION IN WELD AREA - ACCEPTABLE.
| |
| 508873 SWU-502 (SW-90) OE GUIDE 92 INSIGNIFICANT'IGHT CORROSION AROUND LUGS
| |
| -ACCEPTABLE'3
| |
| | |
| R E ~ GZNNA NUCLEAR POWER PLANT 1990 - Znservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I CLASS 3 COMPONENTS CONT. t C12o MAIN STEAM SUPPLY TO AUX FW PUMP TURBINE DRAWINGS t C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 509220 D-B D2.30 MSU-84 ASME VT-3 MECHANICAL SNUBBER-ZNTEGRAL ATTACHMENT 92 OTHERs LUG FILLET WELDS BURIED ZN WALL - INACCESSIBLE'ERIAL NUMBER 18182'EMPERATURE 134 DEGREES F g SETTING 2 1/2 g EAST PSA 3 ~ SERIAL NUMBER 18183@ TEMPERATURE 134 DEGREES F kg SETTING 2 g WEST PSA *3)
| |
| ACCEPTABLE.
| |
| 509225 F-C F3 F 00 MSU-84 ASME VT-3 MECHANZCAL SNUBBER 92 OTHER: LUG FILLET WELDS BURIED IN WALL - INACCESSIBLE. SERIAL NUMBER 18182, TEMPERATURE 134 DEGREES F., SETTING 2 1/2"~ EAST - PSA-3. SERIAL NUMBER 18183@ TEMPERATURE 134 DEGREES F g SETTING 2 g WEST PSA 3j ACCEPTABLE.
| |
| DE HIGH ENERGY Dlo MAIN STEAM TURBINE BUILDING DRAWINGSI HE-7 COMPONENTS'ummary Exam Item NDE Number Categ Number Component "Component Type Exam 200025 HE-DB L2 AUG RT TEE-TO-PIPE WELD MT VT-1 UT p INS IGNIFZCANT g SLAG AT 1 6 1 /4 6 53 5/8
| |
| - 1/2 WASHOUT IN BASE 92 ~ 34 ~
| |
| METAL ON THE TEE SIDE FROM 74" TO 78" ACCEPTABLE. MT Ec VT PERFORMED 1991 6c ACCEPTABLE'
| |
| | |
| e R~ Eo, GINNA NUCLEAR POWER PLANT 1990 - Inservice Znspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT ~
| |
| D2 MAIN STEAM LOOP B OUTSIDE CV DRAWINGS! HE 2/2A Summary Exam Item Number Categ 'umber Component Component Type 200035 HE-DB Hl AUG VT-1 PIPE-TO-ELBOW WELD UT MT 92 VT/MTg PERFORMED 1991 & ACCEPTABLE. UTg NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 200045 HE-DB ---'- Pl AUG VT-1 REDUCER-TO-TEE WELD RT MT 92 VTy INSIGNIFICANT'OUGES FROM LINE-UP FIXTURE & SCORING - ACCEPTABLE.
| |
| MT) NO RECORDABLE INDICATIONS ACCEPTABLE. RTg INSIGNIFICANT'AMMERMARK ZN BASE METALL'O APPARENT CHANGE IN WELD SINCE LAST INSPECTION ACCEPTABLE.
| |
| D3 ~ FEED WATER TURBINE BUILDING DRAWINGS! HE-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200050 HE-DB ---- M3 AUG VT-1 PIPE-TO-TEE WELD UT MT 92 VTg" INSIGNIFICANT'RZNDING GOUGE LOCATED FROM 42 5/8 TO 44 g 1 3/8 LONG X 7/16" WIDE X 1/32" DEEP ACCEPTABLE. MTg NO RECORDABLE ZNDICATIONS ACCEPTABLE. UTg PAST RADIOGRAPHS SHOW COUNTERBORE & ROOT GEOMETRY ACCEPTABLE.
| |
| D4. FEED WATER LOOP A OUTSIDE CV DRAWINGS! HE-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200055 HE-DB M4 AUG VT-1 TEE-TO-REDUCER WELD UT MT 92 - VT-lg INSIGNIFICANT, GRIND MARKS 1/64" DEEP - ACCEPTABLE'Tg NO RECORDABLE INDICATIONS- ACCEPTABLE. VT & MT LIMITATIONS, ACHIEVED > 90%
| |
| COVERAGE. UTy NO RECORDABLE INDICATIONS & GEOMETRY ACCEPTABLE. UT LIMITATIONS, ACHIEVED 92.3% COVERAGE.
| |
| 35
| |
| | |
| Ro E ~ GZNNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT.
| |
| D5 ~ FEED WATER LOOP B OUTSIDE CV DRAWINGS< HE-4/5 Summary Exam Item NDE Number Categ Number Component Component; Type Exam 200075 HE-DB Al AUG VT-1 TEE-TO-REDUCER WELD UT MT PT 92 UT j GEOMETRY'OUNTERBORE g > 90't EXAMINATIONCOVERAGE OBTAINED ACCEPTABLE VTI NO RECORDABLE INDICATIONS~ LIMITATION FROM 28" TO 35 3/8" DUE TO SUPPORT CONTACT ACCEPTABLE'T 6 PTg LIMITATION SAME AS FOR VTg > 90't EXAMINATION COVERAGE OBTAINED ACCEPTABLE.
| |
| 200085 HE-DB N AUG VT-1 3994 VALVE-TO-ELBOW MT WELD RT 92 RTg INSIGNIFICANT POROSITY I UNDERCUT/ SLAG 6 INTERNAL CONCAVITY~ NO CHANGE IN WELD SINCE LAST INSPECTION ACCEPTABLE. VT/MT) PERFORMED ZN 1991 ACCEPTABLE'AKING CREDIT THIS OUTAGE.
| |
| D6o MAIN STEAM LOOP A OUTSIDE CV DRAWINGS'E-1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200125 HE-CB AUG VT-1 PIPE-TO-ELBOW WELD MT RT UT 92 VT/MT PERFORMED ZN "1991 ACCEPTABLE, TAKING CREDIT THIS OUTAGE. UT NO RECORDABLE INDICATIONS ON WELD - ROOT GEOMETRY. UT INDICATIONS WERE RADZOGRAPHED AND FOUND TO BE ROOT CONCAVITY AT 17 3/4" 6 POROSITY AT 23 5/8 ACCEPTABLE'00135 HE-CB AUG VT-1 Gl'EE-TO-CAP WELD RT MT 92 VT 6 MT'O RECORDABLE, INDICATIONS ACCEPTABLE. RTg NO RECORDABLE INDICATIONS'EE
| |
| | |
| ==SUMMARY==
| |
| NUMBER 082300 FOR RT EXAMINATION RECORD ACCEPTABLE.
| |
| 36
| |
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| 'i Ro E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990 >> 1999 Interval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT MAIN STEAM LOOP A OUTSIDE CV (CONT+) DRAWINGS s HE-1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200140 HE-CB G2 AUG VT-1 TEE-TO-PIPE WELD UT MT PT 92 VTg NO RECORDABLE INDICATIONSg LIMITATION OF 1 ADJACENT TO WELD ACHIEVED GREATER THAN 90't COVERAGE - ACCEPTABLE MT & PTg NO RECORDABLE INDICATIONS ACCEPTABLE. UTg NO RECORDABLE INDICATIONS AND THAN 90% COVERAGE OBTAINED ACCEPTABLE.
| |
| GEOMETRY'REATER D7o MAIN STEAM LOOP B OUTSIDE CV DRAWZNGSt HE-2/2A Summary Exam Item NDE Number Categ Number Component Component Type Exam 200185 HE-CB K AUG VT-1 ELBOW-TO-PIPE WELD UT MT 92 VTy INSIGNIFICANT'IGHT RUST ACCEPTABLE. UT & MT; NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 200195 HE-CB ---- Ll AUG VT-1 TEE-TO-CAP WELD RT MT 92 VT-lg INSIGNIFICANT, LIGHT SURFACE RUST ACCEPTABLE'T NO RECORDABLE INDICATIONS ACCEPTABLE'Tg INSIGNIFICANT'OROSITY & SLAG SPOTS ACCEPTABLE.
| |
| 200200 HE-CB -- L2 AUG VT-1 TEE-TO-PIPE WELD UT MT 92 VT ZNSZGNIFZCANT: UPSTREAM RANDOM PITS < 1" FROM WELD, MINOR GOUGES IN BASE METAL AND CHISEL MARK - ITEMS NOT LINEAR DURING MT EXAMINATION ACCEPTABLE. MT) NO RECORDABLE INDICATIONS, LIMITATION DUE TO MSU-33 ACCEPTABLE. UT: NO RECORDABLE INDICATIONS -
| |
| ACCEPTABLE'7
| |
| | |
| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Znservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT DS ~ MAIN STEAM TURBINE BUILDING DRAWINGS'E-7A Summary Exam Item NDE Number Categ Number Component Component Type Exam 200250 HE-CB D AUG VT-1 ELBOW-TO-PIPE WELD UT MT PT 92 VT-1 ZNSZGNZFICANTi SLIGHT GRZND MARKS ACCEPTABLE. MT REJECTs LINEAR INDICATION, PT PERFORMED TO CONFIRM ZNDZCATION. NCR92-208 GENERATED TO INITIATE REWORK. RE-EXAM AFTER REWORK USING VT 6 MT, NO RECORDABLE ZNDZCATIONS ACCEPTABLE. UT! NO RECORDABLE INDICATIONS AND GEOMETRY DUE TO COUNTERBORE ACCEPTABLE. ALL NOTED INDICATIONS ARE CONSTRUCTION AND NOT SERVICE INDUCED.
| |
| 200255 HE-CB D1 AUG VT-1 PIPE-TO-ELBOW WELD MT UT 92 VT 6 MT; NO RECORDABLE INDICATIONS ACCEPTABLE. UTg GEOMETRY: ROOT CONFIGURATION, ZD GEOMETRY 6 COUNTERBORE ACCEPTABLE.
| |
| D9o FEED WATER TURBINE BUILDING DRAWINGS! HE-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200305 HE-CB ---- Ll AUG VT-1 PIPE-TO-ELBOW WELD UT MT 92 MT 6 VTp INSIGNIFICANT, SLIGHT EXTERNAL UNDERCUT THAT IS BLENDED IN BASE MATERIALS ALL <1/32 ACCEPTABLE'Tg GEOMETRY'LL INDICATIONS ARE ACCEPTABLE'ADIOGRAPHS OF PREVIOUS EXAMS HAVE BEEN REVIEWED'00350 HE-CB ---- F AUG VT-1 PIPE-TO-ELBOW WELD UT MT PT 92 VT-li NO RECORDABLE INDICATIONS 6 OTHER: EXTERNAL UNDERCUT < 1/32"-
| |
| ACCEPTABLE+ MT) SHOWED EDGES OF WELD - ACCEPTABLE PT: SUPPLEMENTAL EXAMZNATIONi NO RECORDABLE INDICATIONS ACCEPTABLE. UTy NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 38
| |
| | |
| Re E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservtce 1999 Interval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT ~ t D10 ~ FEED WATER LOOP A OUTSIDE CV DRAWINGS'E 3 Summary Exam Item NDE Number Categ Number Component Component, Type Exam 200435 HE-CB Y AUG VT-1 PIPE-TO-VALVE 3995 RT WELD MT 92 VT & MT) NO RECORDABLE INDICATIONS ACCEPTABLE. RTg
| |
| & UNDERCUT ACCEPTABLE.
| |
| INSIGNIFICANT'SLAG'OROSITY Dll, FEED WATER LOOP B OUTSIDE CV DRAWINGS! HE-4 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200535 HE-CB H2A AUG VT-1 PIPE-TO-FLANGE WELD UT MT 92 VT & MT'O RECORDABLE INDICATIONS ACCEPTABLE+ UTg NO RECORDABLE INDICATIONS & GEOMETRY (FLANGE ID) ACCEPTABLE.
| |
| 200550 HE-CB K AUG VT-1 PIPE-TO-VALVE 3992 MT WELD UT 92 VT & MT) NO RECORDABLE INDICATIONS ACCEPTABLE. UT NO RECORDABLE ZNDZCATIONS, GEOMETRY & OTHER-MODE CONVERSION SIGNAL FROM SEAL WELD ACCEPTABLE.
| |
| 200555 HE-CB ---- L AUG VT-1 ~
| |
| 3992 VALVE-TO-PIPE RT WELD MT 92 VT-1 & MTy NO RECORDABLE INDICATZONS ACCEPTABLE. RTg INSIGNIFICANT BACKING RING WASHOUT ACCEPTABLE.
| |
| 39
| |
| | |
| %I Ro E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT. s D12 ~ MAIN STEAM DRAWINGS! HE-7/7A Summary Exam Item NDE Number Categ Number Component ~ Component Type Exam 201050 HE-CS MS-47 (S3) OE VT-3 RIGID HANGER 6c MT INTEGRAL ATTACHMENT 92 EXAM FOR EWR 5114.
| |
| ,
| |
| VT'O RECORDABLE ZNDICATIONS ACCEPTABLE. MT) NO RECORDABLE INDICATIONS, EXAM OF NEW WELD ATTACHMENT TO I-BEAM AND INTEGRAL ATTACHMENT ACCEPTABLE. PCAQ 92-018 GENERATED TO RESOLVE DRAWING DZSCREPANCZES.
| |
| 201060 HE-CS ---- MS-59 (S4) OE RIGID HANGER 92 EXAM FOR EWR 5114. VTg INSIGNIFICANT: (1) SEE PRINT AND REFERENCED FCR 5114-11, NEW DRAWING HAS BEEN CHANGED (2) ITEMS INDICATED ON PRINT ARE DIFFERENT FROM WHAT IS INSTALLED. PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES ACCEPTABLE.
| |
| 201100 HE-CS -- . MS-36 (S5) OE VT-3 VARIABLE SPRING 92 - EXAM FOR EWR 5114. VTy TEMPERATURE 135 DEGREES F.i SETTING 2" = 6434 P'S, PCAQ 92-018 GENERATED TO RESOLVE DRAWZNG DISCREPANCIES ACCEPTABLE'T-3 201120 HE-CS MS-37 (S6)
| |
| VARIABLE SPRING 92 EXAM" FOR P'Si PCAQ EWR 5114. 'T; 1 TEMPERATURE 135 DEGREES F.g SETTING 2 1/4" = 6859 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES ACCEPTABLE.
| |
| 201140 HE-CS ---- MS-150 (S7) OE VT-3 HYDRAULIC SNUBBER MT INTEGRAL ATTACHMENT 92 - VT NO RECORDABLE INDICATIONS: SERIAL NUMBER 11945, TEMPERATURE 70 DEGREES F g SETTING 2 1/4 ~ SPECIFICATION SETTING 2 1/2 +/, 3/4 g GRINNELL P/N
| |
| -
| |
| 201. INSIGNIFICANT: OZL RESERVOIR 7/8 FULL, OIL ON BODY DOES NOT APPEAR TO BE LEAKING ACCEPTABLE. MT; NO RECORDABLE INDICATIONS ACCEPTABLE.
| |
| 40
| |
| | |
| Ro Eo GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT t MAIN STEAM (CONT.) DRAWINGS'E 7/7A Summary Exam Item NDE Number Categ Number Component Component Type Exam 201160 HE-CS MS-38 (SB) OE VT-3 VARIABLE SPRING 92 EXAM FOR EWR 5114. VT'EMPERATURE 135 DEGREES F., SETTING 2 3/8" = 7000 g'Si HOT SETTING: 2 7/16" = 7071 f''S. PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES ACCEPTABLE.
| |
| 201180 HE-CS ---- MS-39 (S9) OE VT-3 VARIABLE SPRING 92 EXAM FOR EWR 5114. VTi OTHER: RE-EXAM PER ENGINEERING INSIGNZFZCANT: ROD BENT AT EYEi NO RECORDABLE INDICATZONS~ TEMPERATURE > 500 DEGREES F ~
| |
| SETTING 1/8" ~ 7424 g'S. PCAQ 92-018 GENERATED TO RESOLVE DRAWZNG DISCREPANCIES - ACCEPTABLE.
| |
| 201220 HE-CS ---- MS-40 (S11) VT-3 VARIABLE SPRING 92 EXAM FOR EWR 5114. VT; TEMPERATURE 135 DEGREES F.g SETTING 1 1/8" = 7424 g'S. PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES ACCEPTABLE.
| |
| 201240 HE-CS ---- MS-41 (S12 ) OE VT-3 VARIABLE SPRING 6 MT INTEGRAL ATTACHMENT 92 EXAM FOR EWR 51 14 ~ VTi TEMPERATURE 135 DEGREES F i SETTING 3/4 6859 jf S ~
| |
| PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES ACCEPTABLE'T NOT PERFORMED, RESCHEDULE FOR SECOND PERIOD-THIRD INTERVAL+
| |
| 201300 HE-CS ---- MS-42 (S15) OE VT-3 VARIABLE SPRING 92 EXAM FOR EWR 5114. VTg TEMPERATURE > 500 DEGREES F., SETTING 2" ~ 4945 f'S.
| |
| PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES -,ACCEPTABLE
| |
| | |
| Ro E ~ GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Inservt.ce 1999 Znterval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT.
| |
| MAIN STEAM (CONT, ) DRAWINGSt HE-7/7A Summary Exam Item Number Categ Number Component Component Type Exam 201320 HE-CS MS-43 (S16) OE VT-3 VARIABLE SPRING 92 - EXAM FOR EWR 5114. VTy TEMPERATURE 161 DEGREES F.g SETTZNG 3/4" ~ 5158 f'S.
| |
| PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES ACCEPTABLE'01380 HE-CS ---- MS-44 (S19) OE VARIABLE SPRING VTg TEMPERATURE > 500 DEGREES F., SETTING 1
| |
| - 7/8" 92 EXAM FOR EWR 5114. ~ 6434 g'S, PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES ACCEPTABLE'01420 HE-CS -- MS-45 (S21) OE VT-3 VARIABLE SPRING 92 EXAM FOR EWR 5 1 14 ~ VTg TEMPERATURE 145 DEGREES F ~ g SETTING P'S..PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES -13/16 ACCEPTABLE+
| |
| 5228 201440 HE-CS MS-46 (S22) OE VT-3 VARIABLE SPRING MT INTEGRAL ATTACHMENT 92 EXAM FOR EWR 5 1 1 4 ~ VT g TEMPERATURE 1 32 DEGREES F ~ g SETTING 3/4 6859 g S ~
| |
| PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES ACCEPTABLE.
| |
| D13o FEED WATER LOOP A DRAWINGS! HE-3/5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 201500 HE-CS FWU-16 AUG VARIABLE SPRING 92 EXAM PERFORMED ZN JULY 1991 g SEE
| |
| | |
| ==SUMMARY==
| |
| 891201500g BASELINE AFTER I
| |
| MOD ZFZCATZON VT g INS IGN IF CANT PZ PE CLAMP INSULATED ~ BERGEN PATTSON VS 2 g TEMPERATURE 394 DEGREES F., SETTING 1/2" = 4875 if'Si SPECIFICATION HOT SETTING 5060 P'S ACCEPTABLE.
| |
| 42
| |
| | |
| Ro E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 -Znservtce 1999 Interval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT. t FEED WATER LOOP A (CONT,) DRAWINGS'E-3/5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 201600 HE-CS FWU-21 OE VT-3 MECHANZCAL SNUBBER 6 MT INTEGRAL ATTACHMENT 92 - EXAM PERFORMED ZN JULY 1991, SEE
| |
| | |
| ==SUMMARY==
| |
| 891201600, BASELINE AFTER MODIFICATIONS VT & MTJ SERIAL NUMBER 2500 20 38'EMPERATURES 385 DEGREES Fog SETTING 4 1/4"g HSSA-20 ACCEPTABLE'01640 HE-CS FWU-23 AUG VT-3 MECHANICAL SNUBBER 92 - VT: SERIAL NUMBER 8360, TEMPERATURE > 225 DEGREES F., SETTING 2 15/16"i PSA-10 ACCEPTABLE.
| |
| D14. FEED WATER LOOP B DRAWINGS! HE-4 Summary Exam Item NDE Number Categ Number Component Component Type Exam 201800 HE-CS FWU-41 OE VT-3 VARZABLE SPRING MT 92 -BASELINE EXAM. VT-3 GRINNELL SIZE 15, TYPE C TEMPERATURE 73 DEGREES F., SETTING 1 7/16" = 5332.5 P'S. OTHER'PRING CAN LABEL IS B-268Ng "N" NOT ON COMPONENT SUPPORT DRAWING ACCEPTABLE. MT; NO RECORDABLE INDICATIONS - ACCEPTABLE.
| |
| 201860 HE-CS ---- FWU-38 OE VT-3 MECHANICAL SNUBBER 92 VT J SETTING 3 1/8 I TEMPERATURE 240 DEGREES F ~ PSA 35 SERIAL NUMBER 9395, - ACCEPTABLE.
| |
| g ~
| |
| 201880 HE-CS FWU-37 AUG VT-3 VARIABLE SPRING 92 - BASELINE EXAM PERFORMED IN OCT. 1991, ACCEPTABLE'EE SUM. 891201880.
| |
| 43
| |
| | |
| Re E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I HIGH ENERGY COMPONENTS CONT ~ g D15 ~ MAIN FEED WATER LINE DRAWZNGSt HE-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 202120 HE-CS FW-38 (S26) OE VARIABLE SPRING 92 VTg REJECT! DRAWING ZNCORRECTLY SPECIFIES SPRING TYPE AS VS-2. NCR92-143 GENERATED FOR RESOLUTION. DCR 92-0072 INITIATED TO CORRECT DRAWING~
| |
| USE AS ZS PER ENGINEERZNGg NO RECORDABLE INDICATIONS ACCEPTABLE'02220 HE-CS ---- FW-43 (S31) OE VT-3 VARIABLE SPRING 92 EXAM FOR EWR 5 1 1 4 ~ VT p TEMPERATURE 1 35 DEGREES F e g SETTING 8300 g S ~
| |
| PCAQ 92-018 GENERATED TO RESOLVE DRAWING DISCREPANCIES ACCEPTABLE'D LEAKAGE TESTINGt El'YDROSTATIC TESTS CLASS 2 DRAWINGS'/A Summary Exam Item ,
| |
| NDE Number Categ Number Component Component Type Exam 350810 C-H IWC5222 RSSP-15.8.1 RCP ASME VT-2 SEAL WATER RETURN 92 VT: TEST PASSED. OTHER! BORIC ACID RESZDUE ON VALVES 312'86 6 293B. STUDS ON HEAD BONNET OF HX ECH04 - SEVERE CORROSION'OME THREADS MISSING. WATER LEAKS ON BONNET GASKET FOR VALVES 315A 6 316A. FILTER ECH03 HEAD FLANGE LEAKS. T/C WRITTEN.
| |
| 351300 C-H IWC5222 RSSP-15.13 SI ASME VT-2 ACCUMULATOR A 92 VT J TEST PASSED ~ OTHER BORIC ACID RESIDUE ON VALVES@ 834Ag 886Ag 832Ag 855C g 892A/844A J 84 1 g 83 SA g 6 ACCUMULATOR MANWAYo BROKEN GAGE ON REGULATOR 15168 TO V844A. FLOOR PENETRATION "ALL-THREADS" ARE HITTING PIPE ~ T/C WRITTEN.
| |
| | |
| !
| |
| Ro E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I LEAKAGE TESTING CONT HYDROSTATIC TESTS CLASS 2 (CONT,) DRAWZNGSt N/A Summary Exam Item Number Categ Number Component Component Type Exam 351400 C-H ZWC5222 RSSP-15.14 SI ASME ACCUMULATOR B 92 VT J TEST PASSED ~ OTHER BORIC ACID RESIDUES ON VALVES 834Bg 835Bg 892Bg 838B.. LEVEL INSTRUMENTATION LT934 6 LT935 HAVE LEAKS ZN TOP FLANGE PIPE PLUG. T/C WRITTEN.
| |
| 352900 C-H IWC5222 RSSP-15.29 RCS ASME VT-2 LETDOWN 92 VT I TEST PASSED ~ OTHER V 244'ACKING LEAKJ BORIC ACID RESIDUE J PACKING LEAK 9 3 CONNECTION FLANGES; DIAPHRAGM LEAK, RUNNING WATER. T/C WRITTEN.
| |
| 353100 C-H IWC5222 RSSP-15.31 REACTOR ASME VT-2 VESSEL HEAD VENTS 92 LEAKAGE EXAM ACCEPTABLE. OTHERJ PACKING AROUND VALVE 500 IS WET, LESS THAN 1 DROP/MIN. WR/TR WRITTEN.
| |
| 353760 C-H IWC5222 RSSP-15.43 HOUSE 'SME VT-2 HEATING STEAM 92 TEST ACCEPTABLE. OTHERJ PACKING LEAK ON V6165, 1 DROP/MINUTE DIAPHRAGM LEAK ON V6125i RUNNING WATER. WR/TR WRITTEN'53770 C-H IWC5222 RSSP-15.44 FIRE ASME VT-2 PROTECTION SYSTEM 92 TEST PASSED. PACKING LEAKS ON V9225 2 DRIPS/MIN. 6 V9230 - 3 DRIPS/MIN.J ITEMS OUTSIDE INSPECTION BOUNDARY. WR/TR WRITTEN.
| |
| 353800 C-H 1WC5222 RSSP-15.47 DEMIN. ASME WATER SYSTEM 92 TEST WAS SATISFACTORY.
| |
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| R. Eo GZNNA NUCLEAR POWER PLANT 1990 -Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I LEAKAGE TESTING CONT.
| |
| E2 ~ HYDROSTATIC TESTS CLASS 3 DRAWINGS'/A Summary Exam Item Number Categ Number Component Component Type Exam 362800 D-B IWD5223 RSSP-13.28 SPENT ASME FUEL POOL COOLING 92 - EXAM PERFORMED ZN 1991. NO LEAKAGE AT THE PRESSURE RETAINING BOUNDARY.
| |
| EXAM SATISFACTORY. SEE
| |
| | |
| ==SUMMARY==
| |
| f91362800.
| |
| E3 ~ LEAKAGE EXAMINATIONS CLASS lf DRAWINGS! L-43 Summary Exam Item NDE Number Categ Number Component Component Type Exam 411000 B-P IWB5221 PT-7 LEAKAGE TEST OF ASME VT-2 REACTOR COOLANT SYSTEM 92 TEST WAS SATISFACTORY WITH EXCEPTION OF V434i W/R WRITTEN FOR ITEMS AS SHOWN IN REPORT.
| |
| E4 ~ LEAKAGE EXAMINATIONS CLASS 2 5 3 DRAWINGS+ N/A Summary Exam Item Number Categ Number Component Component Type Exam 411100 C-H IWC5221 MAINSTEAM INSIDE ASME VT-2 CONTAINMENT 92 TEST WAS SATISFACTORY.
| |
| 411200 C-H IWC5221 MAINSTEAM OUTSIDE ASME CONTAINMENT 92 TEST WAS SATISFACTORY. PACKING LEAK ON SOUTH PACKING SET VALVES V3516 6 V3517. SMALL PACKING LEAK IN GLAND AREA, VALVE BODY VERY RUSTY - CLEAN-UP V11028. PACKING LEAK, VALVE VERY RUSTY ON V3445B. W/R WRITTEN 46
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| | |
| Re E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservtce 1999 Interval, Third Outage 1992 ATTACHMENT I LEAKAGE TESTING CONT.
| |
| LEAKAGE EXAMINATIONS CLASS 2 5 3 (CONT.) DRAWINGSt N/A Summary Exam 'Item NDE Number Categ Number Component Component Type Exam 411300 D-B IWD5221 MAINSTEAM TO ASME TDAFWP 92 TEST PERFORMED AND ACCEPTABLE.
| |
| 411400 HE-LK - MAINSTEAM HIGH ENERGY AUG VT-2 92 TEST SATISFACTORY.
| |
| 411500 C-H IWC5221 FEED WATER INSIDE ASME VT-2 CONTAINMENT 92 TEST WAS SATISFACTORY. CAP ON LT-462 LEAKING > 2 DROPS/MZN. MAINTENANCE WROTE W/R 411600 C-H IWC5221 FEED WATER OUTSIDE ASME VT-2 CONTAINMENT 92 TEST WAS SATISFACTORY. PACKING LEAKS > 60 DROPS/MZN. ON V3994. PACKING LEAK WET, SOME STEAM ON V3995. MISSING CAP (PIPE) DOWNSTREAM ON V4397.
| |
| W/R WRITTEN.
| |
| 411700 D-B IWD5221 AUXILIARY FEED WATER ASME VT-2 "A" PUMP 92 TEST SATISFACTORY. PACKING GLAND VERY RUSTY ON VALVES V4351 6 V4353. W/R WRITTEN.
| |
| 411800 D-B IWD5221 AUXILIARY FEED WATER ASME VT-2 "B" PUMP 92 TEST SATISFACTORY. NOTE: VALVE'4012 HAS REPAIR INJECTION IN BONNET.
| |
| REQUESTED MAINTENANCE TO DETERMINE STATUS. VALVE WAS REBUILT IN 1981 BUT THE INJECTION VALVES WERE NOT REMOVED. MAINTENANCE WILL REMOVE INJECTION VALVE IN THE 1993 OUTAGE.
| |
| | |
| Ro E ~ GZNNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I LEAKAGE TESTING CONT. t LEAKAGE EXAMINATIONS CLASS 2 & 3 (CONT+) DRAWINGSS N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 411900 D-B IWD5221 AUXILIARY FEED WATER ASME VT-2 TURBINE DRIVEN 92 TEST ACCEPTABLE, VALVE 4004B LEAKS BY SEATi SWAGELOK CAP LEAKING MAINTENANCE TAG. VALVE 5074B & '4005 HAS SMALL PACKING LEAKi V4005 GLAND AREA RUSTY. W/R WRITTEN.
| |
| 412000 D-B IWD5221 STANDBY AUXILIARY ASME VT-2 FEED WATER PUMP "C" 92 TEST SATISFACTORY.
| |
| 412100 D-B IWD5221 STANDBY AUXILIARY ASME VT-2 FEED WATER PUMP "D" 92 TEST SATISFACTORY.
| |
| 412200 HE-LK ----
| |
| I L-7 AUG VT-2 HE FEED WATER 92 TEST WAS SATISFACTORY. VALVE 4396 LEAKS BY 6 DROPS/MIN.- MISSING PIPE CAP VALVE 9502D HAS A PACKING LEAK, 12 DROPS/MIN.. W/R WRITTEN+
| |
| 412300 C-H IWC5221 STEAM GEN BLOWDOWN ASME INSIDE CONTAINMENT 92 TEST WAS SATISFACTORY, PACKING LEAK BLOWING STEAM ON V5704A, CAP DOWNSTREAM OF V5704 LEAKZNG. MAINTENANCE WROTE W/R.
| |
| 412400 C-H IWC5221 STEAM GEN BLOWDOWN ASME OUTSIDE CONTAINMENT 92 TEST WAS SATISFACTORY.
| |
| WRITTEN'8 V-5738 HAS SMALL PACKING LEAK ON VALVE STEM. W/R
| |
| | |
| 0 Ro E. GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I LEAKAGE TESTING CONT ~ t LKQGLGE EXAMINATIONS CLASS 2 & 3 (CONT,) DRAWZNGSt N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 412500 C-H ZWC5221 SAFETY INJECTION "A" ASME VT-2 PUMP ZN/OUT CONTAINMENT
| |
| 'I 92 TEST SATISFACTORY. PACKING LEAK, > 50 DROPS/MZN AT VALVE STEM ON V1817, MAINTENANCE TAG ATTACHED.
| |
| 412600 C-H IWC5221 SAFETY INJECTION "B" ASME VT-2 PUMP
| |
| .IN/OUT CONTAINMENT 92 - TEST SATISFACTORY. VALVE 1802C PACKING LEAK < 1 DROP/MZN AT STEM. BAGGED VALVE WITH RAGS & SPEEDY-DRY IN BAG. VALVE 12403 PACKING LEAK. GLAND AREA BADLY CORRODED WITH BORIC ACID. PIPE SHOP DE-CORRODED VALVE & ADJUSTED PACKING.
| |
| 412700 C-H IWC5221 SAFETY INJECTION "C" ASME PUMP OUTSIDE CONTAINMENT 92 TEST ACCEPTABLE ~ PACKING LEAKg < 1 DROP/MINg ON VALVE 1820B ~ BAG ATTACHED WITH RAGS WITH SPEEDY-DRY INSIDE TO CATCH LEAK.
| |
| 412800 C-H IWC5221 SAFETY INJECTION ASME ACCUMULATOR 1 (A) 92 TEST WAS NOT PERFORMED ~ TAKING CREDIT FOR HYDROg RSSP 15 13 g SEE
| |
| | |
| ==SUMMARY==
| |
| | |
| NUMBER 351300.
| |
| 412900 C-H IWC5221 SAFETY INJECTION ASME ACCUMULATOR 2 (B) 92 TEST WAS NOT PERFORMED ~ TAKING CREDIT FOR HYDROg RSSP 15 14g SEE
| |
| | |
| ==SUMMARY==
| |
| | |
| NUMBER 351400.
| |
| 413000 C-H IWC5221 CONTAINMENT SPRAY ASME VT-2 A PUMP DISCHARGE 92 NO RECORDABLE INDICATIONS. OTHER: PACKING LEAKS, RUSTY FLANGESg IMPROPER THREAD ENGAGEMENT, BORIC ACID RESIDUE, PZPZNG MOVES ENGINEERING TO EVALUATE. WR WRITTEN.
| |
| | |
| Ro E GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I LEAKAGE TESTING CONT ~
| |
| LEAKAGE EXAMINATIONS CLASS 2 & 3 (CONT+) DRAWINGS i N/A Summary Exam Item NDE ~
| |
| Number Categ Number Component Component Type Exam 413100 C-H IWC5221 CONTAINMENT SPRAY ASME B PUMP DISCHARGE 92 TEST SATISFACTORY ~ OTHER PACKING LEAKS@ BORIC ACID RESIDUE@ RUSTg IMPROPER BOLTING'HREAD ENGAGEMENTS WR WRITTEN+
| |
| V 413150 C-H ZWC5221 SPRAY. ADDITIVE ASME VT-2 NOAH TANK 92 TEST WAS SATISFACTORY ~ PACKING LEAKS g NOAH RESIDUE ON V836Ag V836B g V849F g V2852g V2866g V899A MISSING ID TAG ON V1802 ~
| |
| 413200 C-H IWC5221 RHR LOW PRESSURE ASME "A" PUMP 92 TEST WAS SATISFACTORY. BORIC ACID RESIDUE ON RHU-92 SNUBBER. T/C WRZTTEN.
| |
| 413300 C-H ZWC5221 RHR LOW PRESSURE 'SME VT-2 "B" PUMP 92 TEST PASSED ~ BORIC ACID RESIDUE ON VALVE 850B~ BODY TO BONNET AREA 1/4 RESIDUE. T/C WRITTEN+ VALVE 851B FLANGE LEAK T/C BY R&T.
| |
| 413400 C-H ZWC5221 RHR PUMP "A" ASME ZN/OUT CONT.
| |
| 92 TEST PASSED ~ OTHER J PACKING LEAKS'OOSE GLAND NUTS BORIC ACIDS LEAKING FITTINGS'ALVE BODY/BONNET LEAKS g RUSTING STUDS ~ SEE EXAM FOR DETAILS ~
| |
| W/R GENERATED.
| |
| 413500 C-H IWC5221 RHR PUMP "B" ASME VT-2 ZN/OUT CONT.
| |
| 92 TEST PASSED ~ PACKING LEAKS ON V709Bg V706Bg V852Bg & V2747 ~ BODY BONNET LEAK ON V704B. B PUMP DISCHARGE FLANGE HAS A GASKET LEAK, B PUMP COVERED WITH BORIC ACID. B PUMP COOLER LEAKS AT SWAGELOK FITTINGS. WR/TRS WRITTEN.
| |
| 50
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| 0 Ro Eo GINNA NUCLEAR POWER PLANT 1990 -Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I, LEAKAGE TESTING CONT.
| |
| LZULKAGE EXAMINATIONS CLASS 2 & 3 (CONT, ) DRAWINGS i N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 413600 D-B IWD5221 AUX COOLING INSZDE ASME CONTAINMENT 92 - TEST SATISFACTORY. GASKET LEAK ON BOLTED FLANGE ON V2770 & V277lo PACKING LEAK/DECON V11260/11261. PACKING LEAK/MAINT TAG ON VALVE V736A/736B.
| |
| 413700 D-B IWD5221 AUX COOLING OUTSIDE ASME VT-2 CONTAINMENT 92 TEST SATISFACTORY ~ PACKING LEAKg > 1 DROP/MINg ON V771E ~ PACKING LEAK (WEEPS, GLAND AREA) ON V724B. PACKING GLAND AREA VERY RUSTY ON V724A.
| |
| FLANGE DOWNSTREAM OF V-2717 LEAKS. W/R WRITTEN.
| |
| 413800 C-H IWC5221 REFUELING WATER ASME VT-2 STORAGE TANK & PZPING 92 STATIC TEST PASSED. BORIC ACID RESIDUE ON V895 & PACKING LEAK DRY. V-895 DOWN STREAM FLANGE GASKET LEAKS. V-894 PACKING LEAK, OTHERs MANWAY COVER, COVER & GASKET NOT INSTALLED. BOLTS MISSING~ AREA AROUND MANWAY DUSTY & DIRTY'R/TR WRITTEN FOR ABOVE.
| |
| 413900 D-A IWD5221 SERVICE WATER ASME INSIDE CONTAINMENT 92 REJECT: RECIRCULATION MOTOR COOLER DZSCHARGE PIPING ZS WEEPING WATER+
| |
| NCR92-240 GENERATED'ALANCE OF SYSTEM ACCEPTABLE. RE-EXAM AFTER
| |
| -
| |
| MODIFICATION HYDRO OF SPOOL PIECE PER WR 92-0823 SATISFACTORY.
| |
| INSTALLATION OF SPOOL PIECE PER 92-0823 SATISFACTORY. SWAGELOCK DRIPS 1 DROP/PER MIN. WR WRITTEN.
| |
| 414000 D-A IWD5221 SERVICE WATER ASME OUTSIDE CONTAINMENT 92 TEST SATISFACTORY. W/R WRITTEN FOR ITEMS SHOWN IN REPORT.
| |
| 414100 D-A IWD5221 SERVICE WATER TO ASME VT-2 AUX FW PUMP "A" 92 TEST SATISFACTORY.
| |
| 51
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I LEAKAGE TESTING CONT t LKQGLGE EXAMINATIONS CLASS 2 5 3 (CONT.) DRAWINGS! N/A Summary Exam Item Number Categ Number Component Component Type 414200 D-A IWD5221 SERVICE WATER TO ASME VT-2 AUX FW PUMP "B" 92- TEST SATISFACTORY. PACKING LEAK ON V4345. W/R WRITTEN.
| |
| 414400 C-H ZWC5221 RCS OVERPRESSURE ASME VT-2 PROTECTION "A" 92 TEST SATISFACTORY. OTHER: V8609A SWAGELOK FITTING ON VALVE IS LEAKING.
| |
| 'R WRITTEN.
| |
| 414500 C-H IWC5221 RCS OVERPRESSURE ASME VT-2 PROTECTION "B" 92 TEST SATISFACTORY. OTHER: V8611B PACKZNG LEAK. WR WRITTEN.
| |
| 414600 C-H ZWC5221 CHARGING Ec SEAL WATER ASME VT-2 FROM PUMPS (IN/OUT CV) 92 TEST SATISFACTORY ~ PACKING LEAKS ON V2226i V300Ai V300Bi B301Bi V301Ai V303D g V12 1 49H i V277Ai V384Ai Ec V384B ~ MISSING TAG ON V3 1 3 i V384Ci V1822 ~
| |
| BORIC ACID RESIDUE ON FI115A 6 FT128 ~ DOWNSTREAM CAP ON V2224 - WET LEAK.
| |
| W/R WRITTEN.
| |
| 414900 C-H ZWC5221 BORIC ACID TANKS 6 ASME VT-2 PIPING 92 - TEST SATISFACTORY. W/R WRITTEN FOR ITEMS TO BE CORRECTED BY STATION MAINTENANCE'15100 D-B IWD5221 DIESEL GEN. "A" ASME VT-2 92 - TEST PASSED. OTHER! AIR SYSTEM VALVE 5945A HAS PACKZNG LEAK FOUND WITH SNOOP. COOLING WATER SYSTEM OK NO LEAKS. PACKING LEAKS ON VALVES 5937 6 5963. RELIEF VALVE 5959 CAP LEAKING. "A" DAYTANK LEVEL GAGE, BOTTOM CONNECTION LEAKING. WR/TR WRITTEN 415200 D-B IWD5221 DIESEL GEN. "B" ASME VT-2 92 TEST SATISFACTORY. PACKING, BODY TO BONNET 6 COUPLING LEAKS; SEE EXAM RECORD FOR DETAILS, W/R WRITTEN.
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| 52
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I F~ SNUBBER PROGRAM COMPONENTSt F1 ~ STEAM GENERATORS DRAWINGS t A-7F Summary Exam Item NDE Number Categ Number Component Component Type Exam 600080 SN-VT SGA-7 AUG HYDRAULIC SNUBBER 92 SERIAL NUMBER A 7 J TEMPERATURE 69 DEGREES F ~ g SETTING 3 2 3/ 1 6
| |
| 'ACCEPTABLE.
| |
| 600090 SN-VT ---- SGA-8 i,
| |
| AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER 8, TEMPERATURE 67 DEGREES F.g SETTING 3'- 2 1/4" ACCEPTABLE. REJECT'ZL LEAKAGES RE-EXAM AFTER TIGHTENING NUT . NO LEAKAGE SNUBBER ACCEPTABLE. SGA-8 SNUBBER WAS CHANGED OUT WITH f5 DURING 1992 OUTAGE. LEAK WAS FROM FITTING THAT NEEDED TIGHTENING NOT SERVICE INDUCED 600091 SN-FT ---- SGA-8 AUG FT HYDRAULIC SNUBBER 92 - SGA-8 WAS REPLACED USING SPARE SGA-5 ~ POSITION INSPECTED, TESTED. SGA-8 TO BE REBUILT'ESTED 6 PUT ZN SPARE PARTS.
| |
| 600120 SN-VT ,--- SGB-3 AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER B 3g TEMPERATURE 67 DEGREES F g SETTING 39 3/16 g ACCEPTABLE ~
| |
| INSIGNIFICANTj OIL DROP WIPED'ID NO REAPPEAR ACCEPTABLE ~
| |
| 600130 SN-VT ---- SGB-4 AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER B-4~ TEMPERATURE 67 DEGREES F.g SETTING 3' 3 3/8"g ACCEPTABLE+ INSIGNIFICANT; RESERVOZR 5/8 FULL. REJECT) STUD - SOUTH ANCHOR CUT AT AN ANGLEg 2/3 OF THREAD ABOVE NUTS 1/3 IS FLUSH'CCEPTABLE PER ISIM-011 MECHANICAL ENGINEERING LETTER DATED 4/7/92 'EJECT IS NOT SERVICE INDUCED.
| |
| F2 ~ TURBINE DRIVEN AUX ~ FW PUMP SUCTION DRAWZNGSt C-16 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600200 SN-VT AFU-03 AUG VT-3 MECHANZCAL SNUBBER 92 SERIAL NUMBER 20925 g TEMP ~ 69 DEGREES F ~ g SETTING 2 g PSA 1 ACCEPTABLE ~
| |
| 53
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| Ro E. GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
| |
| F3 ~ AUX ~ FW PUMPS DISCH - INTERMED ~ DRAWINGS t C-1E Summary Exam Item NDE Number Categ Number Component Component Type Exam 600220 SN-VT AFU-3 1 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 24452 g TEMPERATURE 68 DEGREES F ~ i SETTING 2 i PSA 1 ACCEPTABLE.
| |
| 600240 SN-VT ---- AFU-34 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 16379 i TEMPERATURE 68 DEGREES F ~ i SETTING 2 13/16 i PSA 1 ACCEPTABLE.
| |
| 600260 SN-VT ---- AFU-52 AUG VT-3 MECHANICAL SNUBBER 92 RE JECT J SNUBBER BASE PLATE i NORTH WEST i NORTH EAST 6 SOUTH WEST BOLTS ARE LOOSEy NCR92-119 GENERATED FOR RESOLUTION ON THIS SERVICE INDUCED REJECT.
| |
| BOLTS WERE TIGHTENED 6 RE-EXAMINED. SERIAL NUMBER 24453i TEMPERATURE 77 DEGREES F., SETTING 1 3/4", PSA-1 ACCEPTABLE.
| |
| 600280 SN-VT AFU-75 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 20294'EMPERATURE 75 DEGREES F i SETTING 2 1/16 i PSA 1 ACCEPTABLE.
| |
| 600300 SN-VT ---- AFU-98 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 24454 i TEMPERATURE "320 DEGREES F i SETTING 1 5/8 i PSA 1 ACCEPTABLE.
| |
| I 600320 SN-VT AFU-101 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 15751, TEMPERATURE 75 DEGREES F.i SETTING 3 1/4", PSA-3
| |
| .ACCEPTABLE.
| |
| 600339 SN-VT ---- AFU-103 (EAST) AUG MECHANICAL 'SNUBBER 92 SERIAL NUMBER 18184'EMPERATURE 239 DEGREES F i SETTING 3 i PSA 3 ACCEPTABLE.
| |
| | |
| Ro Ee GINNA NUCLEAR POWER PLANT 1990 - Znservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. t AUX ~ FW PUMPS DZSCH INTERMED ~ BLDG@ (CONT ~ ) DRAWINGS i C-1E Summary Exam Item NDE Number Categ Number Component Component Type Exam 600340 SN-VT AFU-103 (WEST) AUG MECHANICAL SNUBBER 92 - SERIAL NUMBER 18185, TEMPERATURE 239 DEGREES Fo g SETTING 3 1/2 g PSA 3 ACCEPTABLE.
| |
| 600360 SN-VT ---- AFU-109 AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER 30986 g TEMPERATURE >200 DEGREES F ~ g SETTING 2 3/ 1 6 INSULATION ZN PLACE TUBE IS 3/4 FULL@ SI ZE 1 1/2 g ACCEPTABLE ~
| |
| 600380 SN-VT AFU-ill AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 16377 TEMPERATURE 310 DEGREES F ~ g SETTING 2 PSA 1 g
| |
| ~
| |
| INSULATZON COVERING SADDLE BRACKET TO PIPE - ACCEPTABLE+
| |
| g 600400 SN-VT AFU-123 AUG ~ VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 16378, TEMPERATURE >200 DEGREES F., SETTING 1 3/4"g INSULATION IN PLACEBO PSA lg ACCEPTABLE'00420 SN-VT -- AFU-124 AUG VT-3 MECHANICAL SNUBBER 92 SERZAL NUMBER 2445 1 g TEMPERATURE 72 DEGREES F g SETTING 1 7/8 g PSA 1 g ACCEPTABLE.
| |
| 600421 SN-FT ---- AFU-124 AUG FT MECHANICAL SNUBBER r 92 PACIFIC SCIENTIFIC'ERIAL NUMBER 24451 g ACCEPTABLE ~
| |
| 55
| |
| | |
| Ro B ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. t F4 'TEAM GENERATOR B BLOWDOWN LINE DRAWINGSs B-31 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600460 SN-VT BDU-16 AUG MECHANZCAL SNUBBER 92 SERIAL NUMBER 10182 g TEMPERATURE 69 DEGREES F g SETTING 2 1/2 g PSA 3 g ACCEPTABLE, F5+ AUX.COOL LINE 4S-AC6-152 DRAWINGS t, B-29 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600530 SN-VT CCU-43 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 1 1462 g TEMPERATURE 70 DEGREES F g SETTING 1 3/8 g PSA 1 g ACCEPTABLE.
| |
| F6 'UX COOL SYS.FRM PUMP COOL OUT.TO PEN126 DRAWINGS'-34 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600610 SN-VT CCU-57 AUG MECHANICAL SNUBBER 92 SERIAL NUMBER 10194@ TEMPERATURE 67 DEGREES F ~ g SETTING 2 1/2 g PSA 3 g ACCEPTABLE.
| |
| F7 ~ AUX.COOL LINE 4T-AC6-152 DRAWINGSt B-30 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600710 SN-VT CCU-71 AUG MECHANICAL SNUBBER 92 SERIAL NUMBER 18193 g TEMPERATURE 63 DEGREES F g SETTING 2 1/2 ~ PSA 3 g ACCEPTABLE.
| |
| 600711 SN-FT ---- CCU-71 AUG FT MECHANICAL SNUBBER 92 - PSA 3g SERIAL NUMBER 18193'EMOVED@ TESTED 6 REINSTALLED ACCEPTABLE.
| |
| 56
| |
| | |
| Ro Eo GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT t F8 ~ 2-INo LETDOWN LINE DRAWINGS! A-23 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600880 SN-VT CVU-26 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 20880, TEMPERATURE 68 DEGREES F., SETTING 2", PSA-1g ACCEPTABLE.
| |
| F9 ~ 2-ZN o CHARGING LINE DRAWINGS! A-30 Summary Exam Item NDE Number Categ Number Component 'omponent Type Exam 600900 SN-VT CVU-46 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 33517 ~ TEMPERATURE 62 DEGREES F g SETTING 2 g PSA 1/4 g ACCEPTABLE.
| |
| F10 ' INo ALTERNATE CHARGING DRAWINGS! A-27 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600920 SN-VT CVU-49 AUG VT-3 MECHANICAL SNUBBER 92 REEXAMINE AFTER FUNCTIONAL TESTED, REJECT) SNUBBER TO PIPE CLAMP EAR IS BOUND IN PIPE CLAMP (PADDLE). NCR92-246 GENERATED FOR RESOLUTION.
| |
| REEXAM AFTER REWORKS SERZAL NUMBER 9483~ TEMPERATURE 58 DEGREES Fog SETTING 1 1/2"g PSA-1/2 ACCEPTABLE. REJECT NOT SERVICE INDUCED.
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| 600921 SN-FT CVU-49 AUG FT MECHANICAL SNUBBER 92 PSA 1 /2 g SERIAL NUMBER 9483 g REMOVED g TESTED AND REINSTALLED ACCEPTABLEo 57
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Znservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~
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| Filo CVCS RELIEF LINE TO PRT DRAWZNGSs B 32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600940 SN-VT CVU-80 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 235 1 6 i TEMPERATURE 68 DEGREES F ~ g SETTING 1 1/2 i PSA 1/4 ACCEPTABLE.
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| F12 'C PUMP 1B SEAL WATER DRAWINGS! B-33 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600960 SN-VT CVU-103 AUG VT-3 MECHANICAL SNUBBER 92 SERZAL NUMBER 24450 i TEMPERATURE 53 DEGREES F g SETTING 2 1/16 g PSA 1 g ACCEPTABLE.
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| 600980 SN-VT ---- CVU-104 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 24449 i TEMPERATURE 53 DEGREES F g SETTING 2 1/16 g PSA 1 i ACCEPTABLE.
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| F13+ RC PUMP 1A SEAL WATER DRAWZNGSt B-34 Summary Exam Item NDE Number Categ Number Component , Component Type Exam 601000 SN-VT CVU-186 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 16541 i TEMPERATURE 65 DEGREES F ~ g SETTING 1 3/4 g PSA 1 g ACCEPTABLE. NEW ID TAG INSTALLED BY MEZS.
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| 58
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| Ro E ~ GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT F14 'VCS LETDOWN LINE TO NON-REGEN HTX DRAWINGS t B-35 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601040 SN-VT CVU-345 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 9491 g TEMPERATURE 76 DEGREES F ~ g SETTING 2 g PSA 1/2 f REEXAM AFTER FUNCTIONAL TEST ACCEPTABLE.
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| 601041 SN-FT -- CVU-345 AUG(EXPANDED) FT MECHANZCAL SNUBBER 92 PAS 1/2 g SERIAL NUMBER 949 1 j REMOVED g TESTED AND REZNSTALLED ACCEPTABLE ~
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| 601060 SN-VT ---- CVU-351 AUG VT-3 MECHANICAL SNUBBER 92 EXAMINATIONAFTER FUNCTIONAL TEST DUE TO NCR92-145. THE EXISTING SNUBBER WAS REPLACED'ERIAL NUMBER 2821'EMPERATURE 76 DEGREES F g SETTING 1 1/4 PSA-1/2 - ACCEPTABLE.
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| 601061 SN-FT CVU-351 AUG FT MECHANICAL SNUBBER 92 SNUBBER PSA 1/2 g S/N 12506 FAILED FT ~ SNUBBER REPLACED WITH PSA 1/2 g S/N 2821 ACCEPTABLE.
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| F5 'VCS LETDOWN LINE TO MIX BED DEMIN DRAWINGS'-36 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601080 SN-VT CVU-372 AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 9471, TEMPERATURE 70 DEGREES F g SETTING 1 1/8 g PSA 1/2g ACCEPTABLE'01081 SN-FT ---- CVU-372 AUG(EXPANDED) FT MECHANICAL SNUBBER 92 SNUBBER PSA 1/2 g S/N 12917 FAILED FT ~ SNUBBER REPLACED WITH NEW PSA 1/2 g S/N 9471 ACCEPTABLE.
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| 'I 59
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| Ro E. GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
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| F16 ~ FEED WATER LOOP A DRAWINGSt B-12 Summary Exam Item NDE
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| 'umber Categ Number Component Component Type Exam 601100 SN-VT FWU-3 AUG HYDRAULIC SNUBBER 92 SERIAL NUMBER 2500 10 1 53 i TEMPERATURE 65 DEGREES F i SETTING 4 1/8 HSSA-10, ACCEPTABLE. INSIGNIFICANT: DROP OF OIL ON BOTTOM OF SNUBBER WIPED, DID NOT REAPPEAR. SNUBBER RESERVOIR HIGH - ACCEPTABLE.
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| 601110 SN-VT FWU-5 AUG VT-3 HYDRAULIC SNUBBER 92 SERZAL NUMBER 2500-10-152, TEMPERATURE 65 DEGREES F,, SETTING 2 1/2"i HSSA-10, ACCEPTABLE. INSIGNIFICANT: DROP OF OIL ON BOTTOM OF SNUBBER-WIPED, DID NOT REAPPEAR WR/TR WRITTEN TO FILL RESERVOIR. SNUBBER EXAM ACCEPTABLE.
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| F17. FEED WATER LOOP B DRAWINGS'-13 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601120 SN-VT -- FWU-8 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 8033 i TEMPERATURE 65 DEGREES F ~ i SETTING 3 1/4 g PSA 10 i ACCEPTABLE.
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| 601130 SN-VT FWU-12 AUG VT-3 MECHANZCAL SNUBBER 92 SERIAL NUMBER 8034 g TEMPERATURE 69 DEGREES F ~ i SETTING 3 1/8 i PSA 10/
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| ACCEPTABLE.
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| 60
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| Ro E ~ GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. g F18 'EED WATER LOOP A DRAWINGS' 11 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601140 SN-VT FWU-15 'AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 9358 g TEMPERATURE 228+ DEGREES F g SETTING 2 1/2 g PSA 35 g ACCEPTABLE.
| |
| 601150 SN-VT FWU-17 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 9392 g TEMPERATURE 200+ DEGREES F g SETTING 5 g PSA 35/
| |
| ACCEPTABLE.
| |
| 601160 SN-VT FWU-18 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 7067, TEMPERATURE 200+ DEGREES F., SETTZNG 4 3/4", PSA-35/
| |
| ACCEPTABLE+
| |
| 601170 SN-VT ---- FWU-20 AUG VT-3 MECHANICAL SNUBBER 92 OTHER: ID TAG INSTALLED BY MEIS. SERIAL NUMBER 7049, TEMPERATURE >250 DEGREES F ~ ~ SETTING 1 7/8 I PSA 35'CCEPTABLE'01180 SN-VT FWU-21 AUG HYDRAULIC SNUBBER 92 SERIAL NUMBER 83020052 g TEMPERATURE >250 DEGREES F ~ g SETTING 4 g HSSA 20 g ACCEPTABLE.
| |
| 601190 SN-VT FWU-23 AUG MECHANICAL SNUBBER 92 SERIAL NUMBER 8630 g TEMPERATURE )250 DEGREES F ~ g ~ SETTING 2 1 5/ 1 6 g PSA-10, ACCEPTABLE.
| |
| 601200 SN-VT FWU-24 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 10061 ~ TEMPERATURE >250 DEGREES F ~ g SETTING 3 ~ PSA 10'CCEPTABLE.
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| 61
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| Ro Ee GZNNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
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| FEED WATER LOOP A (CONT+) DRAWINGS! B-ll Summary Exam Item NDE Number Categ Number Component Component Type Exam 601209 SN-VT FWU-26 (EAST) AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 18179 g TEMPERATURE 72 DEGREES F g SETTING 2 1/2 g PSA-3, ACCEPTABLE.
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| 601210 SN-VT ---- FWU-26 (WEST) AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 18180'EMPERATURE 72 DEGREES F ~ g SETTING 2 1/2 PSA-3g ACCEPTABLE.
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| F19 'EED WATER LOOP B DRAWINGS'E-Sg B-14 Summary Exam Item NDE Number Categ Number Component Component. Type Exam 601220 SN-VT FWU-32 AUG VT-3 MECHANZCAL SNUBBER 92 SERIAL NUMBER 7053 ~ TEMPERATURE 72 DEGREES F g SETTING 3 1/8 g PSA 35 g INSIGNIFICANT: DAMAGED I.D. TAG. ACCEPTABLE.
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| 601230 SN-VT FWU-38 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 9395 J TEMPERATURE >176 DEGREES F g SETTING 2 5/8 / PSA 35 g ACCEPTABLE 601240 SN-VT FWU-39 AUG VT-3 MECHANZCAL SNUBBER 92 ACCEPTABLE'ETTING SERIAL NUMBER 9354 g TEMPERATURE 182 DEGREES F o g 3 3/4"g PSA-35/
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| 601250 SN-VT FWU-40 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 7066'EMPERATURE 227 DEGREES F 'g SETTING 3 1/2 g PSA 35'CCEPTABLE.
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| 62
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| R. Eo GINNA NUCLEAR POWER PLANT Inspection Report 1990 -Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT, t FEED WATER LOOP B (CONT+) DRAWINGS! HE-5i B-14 Summary Exam Item NDE Number Categ Number Component Type Exam'omponent 601260 SN-VT FWU-42 AUG VT-3 MECHANICAL SNUBBER 92 OTHER: CANNOT VT LUGS DUE TO INSULATION. SERIAL NUMBER 6159'EMPERATURE 245 DEGREES F kg SETTING 3 3/8 g PSA 35~
| |
| ACCEPTABLE'01270 SN-VT FWU-44 AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER G43864-02-20, TEMPERATURE 75 DEGREES F., SETTING 3 5/8",
| |
| HSSA-30, ACCEPTABLE. INSIGNIFICANT HYDRAULIC RESERVOIR MOUNTED UPSIDE DOWN, ACCEPTABLE.
| |
| 601280 SN-VT FWU-47 AUG VT-3 MECHANICAL SNUBBER 92 INSIGNIFICANT PIGEON FECES SERIAL NUMBER 7474 TEMPERATURE >200 DEGREES F~ ~ I SETT NG 2 3/4 g g
| |
| PSA 3 5 g ACCEPTABLE ~
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| g
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| .601290 SN-VT ---- FWU-48 AUG VT-3 MECHANICAL SNUBBER 92 ZNSIGNIFICANT: PIGEON FECES, SERIAL NUMBER 7475, TEMPERATURE >200 DEGREES F~ ~ SETTING 2 7/8 g PSA 35~
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| ACCEPTABLE'01300 SN-VT ---- FWU-51 AUG VT-3 MECHANICAL SNUBBER 92 INSIGNIFICANT PIGEON FECES g SERIAL NUMBER 7483 g TEMPERATURE 140 DEGREES F g SETTING 3 1/8 g PSA 35 g ACCEPTABLE ~
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| 601310 SN-VT FWU-'52 AUG MECHANZCAL SNUBBER 92 INS IGNIFICANT P IGEON FECES g SERIAL NUMBER 8607, TEMPERATURE 1 40 DEGREES F ~ SETTING 2 5/8 g PSA 10'CCEPTABLE 63
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
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| FEED WATER LOOP B (CONT+) DRAWINGS! HE-5~ B-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601320 SN-VT FWU-54 AUG MECHANICAL SNUBBER 92 NCR92-012 GENERATED TO MODIFY FWU-54 SNUBBER FASTENING BOLT BY DRILLING TAPPING'UPPORT FWU-55 STRUCTURAL TUBE STEEL PREVENTED REMOVAL OF FWU-54 AFTER FUNCTIONAL TESTING, SERIAL NUMBER 7482, TEMPERATURE 57 'XAMINED DEGREES F ~ g SETTING 4 3/8 g PSA 35 ~ ZNSZGNZFZCANT PZGEON FECES ACCEPTABLE.
| |
| 601321 SN-FT - - FWU-54 AUG FT MECHANICAL SNUBBER 92 PSA 35 g SERIAL NUMBER 7482 j REMOVED'ESTED AND REINSTALLED ACCEPTABLE.
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| 601330 SN-VT ---- FWU-57 AUG VT-3 MECHANICAL SNUBBER 92 INSIGNIFICANT! PIGEON FECES. SERIAL NUMBER 10064, TEMPERATURE 140 DEGREES F ~'ETTING 2 7/8 ~ PSA 10'CCEPTABLE'20
| |
| 'AIN STEAM. LOOP A DRAWINGS: B-8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601350 SN-VT MSU-2 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 7048 g TEMPERATURE 65 DEGREES F ' PSA 35 g SETTING 3 5/8 g ACCEPTABLE.
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| 601360 SN-VT -- MSU-3 AUG MECHANICAL SNUBBER 92 SERIAL NUMBER 7060~ TEMPERATURE 65 DEGREES F g SETTING 3 g PSA 35 g ACCEPTABLE.
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| 64
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| 11 R. E ~ GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Integral, Third Outage 1992 ATTACHMENT I, SNUBBER PROGRAM COMPONENTS CONT. t F21 'AIN STEAM LOOP B DRAWINGS i B-8/10/ 10A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601369
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| 'N-VT MSU-7 (TOP/WEST) AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 7051 g TEMPERATURE 73 DEGREES F ~ g SETTING 2 1/2 g PSA 35 g ACCEPTABLE.
| |
| 601370 SN-VT --'-- MSU-7 (BOTTOM/EAST) AUG MECHANICAL SNUBBER 92 SERIAL NUMBER 7047 g TEMPERATURE 73 DEGREES F g SETTING 2 3/4 g PSA 35 /
| |
| ACCEPTABLE.
| |
| 601371 SN-FT ---- MSU-7, (TOP/WEST) AUG FT MECHANICAL SNUBBER 92 PSA-35'ERIAL NUMBER 7051) REMOVED'ESTED AND REINSTALLED ACCEPTABLE.
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| 601372 E
| |
| SN-FT -- . MSU-7 (BOTTOM/EAST) AUG FT MECHANICAL SNUBBER 92 PSA-35, SERZAL NUMBER 7047) REMOVED, TESTED AND REINSTALLED ACCEPTABLE.
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| 601380 SN-VT ---' MSU-8 AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER G20968 1 30 g TEMPERATURE 62 DEGREES F g SETTZNG 3 3/4 g BERGEN PETERSON HSSA-20 ACCEPTABLE. INSIGNIFICANT: SETTING ZS AT MAXIMUM PLUS TOLERANCE+
| |
| 601390 SN-VT MSU-12 AUG VT-3 MECHANICAL SNUBBER 92 EXAM AFTER FUNCTIONAL TEST) SERZAL NUMBER 9400, TEMPERATURE 120 DEGREES F.g SETTING 3 '25~ PSA 35'CCEPTABLE'NSIGNIFICANT PIGEON FECES' 65
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| Ro E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
| |
| MAZN STEAM LOOP B (CONT+) DRAWINGSs B-8/10/10A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601399 SN-VT ,MSU-13 (EAST) AUG MECHANICAL'NUBBER 92 ZNSIGNZFZCANT PIGEON FECES. SERIAL NUMBER 1467'EMPERATURE >400 DEGREES F g SETTING 4 g PSA 100'CCEPTABLE'01400 SN-VT ---.- MSU-13 (WEST) AUG VT-3 MECHANICAL SNUBBER 92 INSIGNIFICANT: PIGEON FECES. SERIAL NUMBER 7464'EMPERATURE >400 DEGREES .
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| F kg SETTING '3 5/8 ~'SA 100'CCEPTABLE' 601409 SN-VT ---- MSU-15 (NORTH) AUG VT-3 MECHANICAL SNUBBER 92 INSIGNIFICANT:,PZGEON FECES. SERIAL NUMBER 7476, TEMPERATURE >400 DEGREES F g SETTING 4 1/4 g PSA 35'CCEPTABLE'01410 SN-VT ---- MSU-15 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 92 - ZNSIGNIFICANT: PIGEON'FECES. SERZAL NUMBER 7477, TEMPERATURE >400 DEGREES F., SETTING 4 1/4"g PSA-35, ACCEPTABLE.
| |
| 601419 SN-VT MSU-16 (NORTH) AUG MECHANZCAL SNUBBER 92 INSIGNIFICANT: PIGEON FECES. SERIAL NUMBER 7481'EMPERATURE >400 DEGREES F.i SETTING 3 3/4", PSA-'35, ACCEPTABLE.
| |
| 601420 SN-VT '--- MSU-16 (SOUTH)
| |
| MECHANICAL SNUBBER AUG VT-3 92 INSIGNIFICANT: PIGEON FECES. SERIAL NUMBER 7480'EMPERATURE >400 DEGREES F kg SETTING 4 3/8 g PSA 35~
| |
| ACCEPTABLE'6
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| Ro Eo GZNNA NUCLEAR POWER PLANT 1990 - Inservice 1999 Interval, Third Outage Inspection Report 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. t MAIN STEAM LOOP B (CONT+) DRAWINQSt B-8/10/10A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601429 SN-VT MSU-18 (NORTH) AUG VT-3 MECHANICAL SNUBBER 92 INSIGNZFZCANT: PIGEON FECES. SERIAL NUMBER 7478, TEMPERATURE >400 DEGREES F ~ ~ SETTING 4 1/4 ~ PSA 35'CCEPTABLE'01430 SN-VT ---- MSU-18 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 92 -'INSIGNZFZCANT: PIGEON FECES. SERIAL NUMBER 7479, TEMPERATURE )400 DEGREES F g SETTING 3 1/2 g PSA 35@
| |
| ACCEPTABLE'01439 SN-VT -- MSU-19 (NORTH) AUG VT-3 MECHANICAL SNUBBER 92 -INSIGNIFICANT: PIGEON FECES. SERIAL NUMBER 9369, TEMPERATURE >400 DEGREES F g SETTZNG 3 7/8 g PSA 35'CCEPTABLE'01440 SN-VT MSU-19 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 92 INSZGNZFZCANT: PIGEON FECES. SERIAL NUMBER 9372, TEMPERATURE >400 DEGREES F ~ g SETTING 3 3/4 g PSA 35'CCEPTABLE'01450 SN-VT ---- MSU-22 AUG VT-3 MECHANZCAL SNUBBER 92 - INSZGNIFZCANT PIGEON FECES. SERIAL NUMBER 9357~ TEMPERATURE 458 DEGREES F g SETTING 4 9/16 g PSA 35'CCEPTABLE'01460 SN-VT MSU-25 AUG VT-3 MECHANICAL SNUBBER 92 ZNSIGNIFZCANT: PZGEON FECES. SERIAL NUMBER 1465, TEMPERATURE 458 DEGREES F g SETTING 4 1/8 g PSA 100'CCEPTABLE'7
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| Ro Eo GZNNA NUCLEAR POWER PLANT 1990 - Znservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT, t MAIN STEAM LOOP B (CONTe) DRAWINGS t B 8/10/10A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601469 SN-VT MSU-26 (TOP) AUG VT-3 MECHANICAL SNUBBER REEXAM AFTER FUNCTIONAL TEST ON MSU-28 (BOTTOM) DUE TO NCR92-233.
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| 'NO RECORDABLE INDICATIONS; SERZAL NUMBER 9355'EMPERATURE 137 DEGREES Foi SETTING 3 3/8 i PSA 35'CCEPTABLE IN HEAT UP TRANSITION@ ENGINEERING REQUESTED RELOOK EXAM AT OPERATING TEMPERATUREi INSIGNIFICANT; PIGEON FECES'ERIAL NUMBER 9355'EMPERATURE 425 DEGREES Fbi SETTING 1 9/16 PSA-35, ACCEPTABLE.
| |
| 601470 SN-VT ---- MSU-26 (BOTTOM) AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST ON MSU-28 (BOTTOM)i NEW SNUBBER INSTALLED DUE TO NCR92-233 RESOLUTION. NO RECORDABLE INDICATIONS) SERIAL NUMBER 4686i .
| |
| TEMPERATURE 137 DEGREES F g SETTING 3 1/4 i PSA 35@ ACCEPTABLE IN HEAT UP TRANSITION. ENGINEERING REQUESTED RELOOK EXAM AT OPERATING TEMPERATURE, INSIGNIFICANT) PIGEON FECES'ERIAL NUMBER 4686i TEMPERATURE 425 DEGREES F ~ g SETTING 1 1/8 i PSA 35'CCEPTABLE'01472 SN-FT ---- MSU-26 (BOTTOM) AUG MECHANICAL SNUBBER 92 EXISTING SNUBBER PSA 35 i S/N 9389 FAILED FT i SNUBBER REPLACED WITH NEW PSA
| |
| -35, S/N 4686 ACCEPTABLE.
| |
| 601480 SN-VT MSU-27 AUG VT-3 MECHANICAL SNUBBER 92 - REEXAM AFTER FUNCTIONAL TESTING. SERIAL NUMBER 9398'EMPERATURE 137 DEGREES Fg SETTING 2 3/8 i PSA 35'N HEAT UP TRANSITION ACCEPTABLE PER ENGINEERING. ENGINEERING REQUESTED RELOOK AT OPERATING'TEMPERATURES INSIGNIFICANT: PIGEON FECES. RELOOK AT OPERATING TEMPERATURE OF 425 DEGREES Fbi SETTING 4 3/4 i SERIAL NUMBER 9398'SA 35i ACCEPTABLE'01481 SN-. FT ---- MSU-27 AUG FT MECHANICAL SNUBBER 92 PSA 35 i SERIAL NUMBER 9398 i REMOVED i TESTED AND REZNSTALLED ACCEPTABLE.
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| 68
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| Ro 8 ~ GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~
| |
| MAIN STEAM LOOP B (CONT+) DRAWINGS'-8/10/10A Summary Exam Item NDE Number Cat.eg Number Component Component Type Exam 601490 SN-VT MSU-29 AUG VT-3
| |
| 'MECHANICAL SNUBBER 92 SERIAL NUMBER 1469~ TEMPERATURE 71 DEGREES F., SETTING 2 1/2"g PSA-100/
| |
| ACCEPTABLE.
| |
| 601500 SN-VT ---- MSU-31 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 9356 g TEMPERATURE 7 1 DEGREES F ~ g SETTZNG 1 1/8 g PSA 35 g ACCEPTABLE.
| |
| 601510 SN-VT -- MSU-32 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 1093 g TEMPERATURE 2 1 1 DEGREES F ~ g SETTING 2 1/2 g PSA 100 /
| |
| ACCEPTABLE'22+
| |
| MAIN STEAM LOOP A DRAWINGS t B-9/9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601520 SN-VT ---- MSU-38 AUG MECHANZCAL SNUBBER 92 SERIAL NUMBER 1090@ TEMPERATURE 253 DEGREES F ~ g SETTING 2 1/2 g PSA 100/
| |
| ACCEPTABLE.
| |
| 601521 SN-FT MSU-38 AUG FT MECHANICAL SNUBBER 92 PSA 100 g SERIAL NUMBER 1090 J REMOVED g TESTED AND REINSTALLED ACCEPTABLE.
| |
| 601530 SN-VT -- MSU-39 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 1087~ TEMPERATURE 75 DEGREES F g SETTING 4 7/8 g PSA 100'CCEPTABLE.
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| 69
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| R. E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice 1999 Interval, Third Outage Inspection Report 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
| |
| MAIN STEAM LOOP A (CONT+) DRAWINGS s B-9/9A i
| |
| Summary Exam Ztem NDE Number Categ Number Component Component Type Exam 601540 SN-VT MSU-40 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 1080 g TEMPERATURE 83 DEGREES F g SETTING 3 3/4 g PSA 100 g ACCEPTABLE.
| |
| 601550 SN-VT -- MSU-44 AUG MECHANICAL SNUBBER 92 SERIAL NUMBER 1468'EMPERATURE 83 DEGREES F ~ g SETTING 3 1/2 g PSA 100'CCEPTABLE.
| |
| F23+ MAIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS! B-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601560 SN-VT MSU-55 AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 18195, TEMPERATURE 72 DEGREES F kg SETTZNG 2 7/8 g PSA 3g ACCEPTABLE'01561 SN-FT MSU-55 AUG(EXPANDED) FT MECHANICAL SNUBBER 92 - PSA-3, SERIAL NUMBER 18195'EMOVED~ TESTED AND REINSTALLED ACCEPTABLE.
| |
| 601570 SN-VT MSU-57 AUG VT-3 MECHANICAL SNUBBER 92 - REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 10161, TEMPERATURE 145 DEGREES Fg SETTING 3 g PSA 3~
| |
| ACCEPTABLE'01571 SN-FT MSU-57 AUG(EXPANDED) FT MECHANZCAL SNUBBER 92 SNUBBER PSA 3 g S/N 15388 'FAILED FTg SNUBBER REPLACED WITH NEW PSA 3 g S/N 10161 ACCEPTABLE.
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| 70
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| I' R. E ~ GZNNA NUCLEAR POWER PLANT 1990 - Inservice 1999 Interval, Third Outage Inspection Report 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. t F24 'AIN STEAM LOOP A ATMOSPHERIC VENT DRAWZNGSt B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601580 SN-VT MSU-58 AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTZONAL TEST. SERIAL NUMBER 18187, TEMPERATURE 79 DEGREES F g SETTZNG 3 1/4 g PSA 3g ACCEPTABLE'01581 SN-FT MSU-58 AUG(EXPANDED) . FT MECHANICAL SNUBBER 92 PSA 3 g SERIAL NUMBER 18187 i REMOVED'ESTED AND REINSTALLED ACCEPTABLE.
| |
| 601590 SN-VT ---- 'SU-60 AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 10107, TEMPERATURE 119 DEGREES F kg SETTING 3 1/4 g PSA 3~
| |
| ACCEPTABLE'01591 SN-FT ---- MSU-60 AUG(EXPANDED) FT MECHANICAL SNUBBER 92 PSA 3 g S/N 18186 FAILED FT~ SNUBBER REPLACED WITH NEW PSA 3 g S/N 10107 ACCEPTABLE.
| |
| F25 ~ MAIN STEAM SUPPLY TO AUX FW PUMP TURBINE DRAWINGS $ B-9A/10 C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601600 SN-VT -- MSU-72 AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 15767, TEMPERATURE 72 DEGREES F kg SETTING 1 3/4 ~ PSA 3g ACCEPTABLE'01601 SN-FT MSU-72 AUG(EXPANDED) FT MECHANICAL SNUBBER 92 PSA 3 g SERIAL NUMBER 1 5767 i REMOVED f TESTED AND REINSTALLED ACCEPTABLE.
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| 71
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| Re E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
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| MAIN STEAM SUPPLY TO AUX FW PUMP TURBINE (CONT,) DRAWZNGSiB-9A/10 C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601610 SN-VT MSU-74 AUG VT-3 MECHANICAL SNUBBER 92 - REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 10066, TEMPERATURE 112 DEGREES F kg SETTING 3 3/8 g PSA 10'CCEPTABLE'01611 SN-FT ---- MSU-74 AUG FT MECHANZCAL SNUBBER 92 -'SNUBBER PSA-10, S/N 10063 FAILED FT. SNUBBER REPLACED WITH PSA-10~ S/N 10066 ACCEPTABLE'01620 SN-VT MSU-75 AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 8030'EMPERATURE 79 DEGREES F g SETTING 3 3/8 g PSA 10/
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| ACCEPTABLE'01621 SN-FT MSU-75 AUG FT MECHANICAL SNUBBER 92 PSA 10 'ERIAL NUMBER 8030 g REMOVED'ESTED AND REINSTALLED ACCEPTABLE.
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| 601630 SN-VT -- MSU-78 AUG VT-3 MECHANICAL SNUBBER 92 .- REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 8576, TEMPERATURE 124 DEGREES F g SETTING 3 1/Bg PSA 10'CCEPTABLE 601631 SN-FT MSU-78 AUG(EXPANDED) FT MECHANICAL SNUBBER 92 PSA 10 g SERIAL NUMBER 8576 g REMOVED g TESTED AND REINSTALLED ACCEPTABLE'01640 SN-VT ---- MSU-80 AUG MECHANICAL SNUBBER 92 - REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 18181, TEMPERATURE 72 DEGREES F g SETTING 2 1/8 ~ PSA 3g ACCEPTABLE'2
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| R. E ~ GZNNA NUCLEAR POWER PLANT 1990 - Znservlce Znspection Report 1999 Integral, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. t MAIN STEAM SUPPLY TO AUX FW PUMP TURB NE I ( CONT o ) DRAWINGStB-9A/10 C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601641 SN-FT MSU-80 AUG(EXPANDED) FT MECHANICAL SNUBBER 92 PSA 3r SERIAL NUMBER 18181) REMOVED'TESTED AND REINSTALLED
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| 'ACCEPTABLE.
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| 601650 SN-VT MSU-82 AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 15768, TEMPERATURE 142 DEGREES F g SETTING 2 3/8 g PSA 3g ACCEPTABLE'T 601651 SN-FT ---- MSU-82 AUG MECHANICAL SNUBBER 92 PSA-3, SERIAL NUMBER 15768; REMOVED, TESTED 6 REZNSTALLED ACCEPTABLE.
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| 601659 SN-VT MSU-84 (EAST) AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 10108, TEMPERATURE 142 DEGREES F ~ SETTING 2 3/4 g PSA 3g ACCEPTABLE+
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| 601660 SN-VT ---- MSU-84 (WEST) AUG VT-3 MECHANICAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 10141, TEMPERATURE 142 DEGREES F.g SETTING 2 1/2"g PSA-3g ACCEPTABLE.
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| 601661 SN-FT ---- MSU-84 (EAST) AUG(EXPANDED) FT MECHANICAL SNUBBER 92 SNUBBER PSA 3g S/N 18182 FAILED FT SNUBBER REPLACED WITH NEW PSA 3g S/N 10108 - ACCEPTED.
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| 73
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| Re E ~ GINNA NUCLEAR POWER PLANT Znsenrice Inspection Report 1990 >> 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT MAIN STEAM SUPPLY TO AUX FW PUMP TURBINE (CONT+) DRAWINGS i B-9A/10 C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601662 SN-FT MSU-84 (WEST), AUG(EXPANDED) FT MECHANZCAL SNUBBER 92 SNUBBER PSA 3 / S/N 18183 FAILED FT ~ SNUBBER REPLACED WITH NEW PSA 3 g S/N 10141 ACCEPTED+
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| 601670 SN-VT MSU-85 AUG VT-3 MECHANiCAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 10074'EMPERATURE 141 DEGREES F kg SETTING .2 5/8 g PSA 10'CCEPTABLE'01671 SN-FT MSU-85 AUG(EXPANDED) FT
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| ~
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| MECHANICAL SNUBBER 92 PSA 10 g SERIAL NUMBER 10074 g REMOVED g TESTED AND REINSTALLED ACCEPTABLE.
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| F26 ~ 6 ZNo SAFETY INJECTION SYSTEM (LOW HEAD) DRAWINGS! B-17 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601680 SN-VT RHU-8 AUG VT-3 MECHANICAL'SNUBBER 92 SERIAL NUMBER 15755 g TEMPERATURE 67 DEGREES F g SETTING 2 5/8 ~ PSA 3 g ACCEPTABLE.
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| F27'0-ZNo RESIDUAL HT REMOVAL (OUT) DRAWINGS i A-15 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601690 SN-VT RHU-30 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 7065 1/16 ACCEPTABLE'4 ~ TEMPERATURE 67 DEGREES F J SETTING 1 g PSA 35 g
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| Ro E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~ !
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| 10-ZNo RESIDUAL HT REMOVAL (OUT) (CONT ~ ) DRAWINGS! A-15 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601700 SN-VT RHU-33 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 7064 g TEMPERATURE 65 DEGREES F ~ g SETTING 3 1/8 g PSA 3 g ACCEPTABLE.
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| F28+ RESIDUAL HEAT REMOVAL LINE 8B-AC-601 DRAWINGS'-23 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601710 SN-VT ---- RHU-36 AUG VT-3 MECHANICAL SNUBBER 92 EXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 15756'EMPERATURE 190 DEGREES F~ g SETTING 2 1/2 g PSA 3I ACCEPTABLE'01711 SN-FT RHU-36 AUG MECHANICAL SNUBBER 92 PSA-3, SERIAL NUMBER 15756), REMOVED~ TESTED AND REZNSTALLED ACCEPTABLE.
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| F29. RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS! B-25 Summary Exam Ztem NDE Number Categ Number Component Component Type Exam 601720 'SN-VT RHU-5 1 AUG MECHANICAL SNUBBER 92 SERIAL NUMBER 15752, TEMPERATURE 73 DEGREES F.g SETTING 2 7/16"g PSA-3g ACCEPTABLE.
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| 601730 SN-VT ---- RHU-53 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 15754@ TEMPERATURE 73 DEGREES F g SETTING 2 5/8 g PSA 3g ACCEPTABLE.
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| 75
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| Ro E GZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservtce 1999 Znterva1, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~ t F30+ RESIDUAL HEAT REMOVAL LINE 6D-AC-601 DRAWZNGSt B-26 Summary Exam Item NDE k Number Categ Number Component Component Type Exam 601740 SN-VT RHU-61 AUG VT-3 MECHANICAL SNUBBER 92 - SERIAL NUMBER 15753, TEMPERATURE 75 DEGREES F.~ SETTING 2 3/8"g PSA-3, ACCEPTABLE, F31. RESIDUAL HEAT REMOVAL LINE 10E-AC-601 DRAWINGS! B-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601749 SN-VT RHU-63 (NORTH) AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 16380'EMPERATURE 67 DEGREES F ~ g SETTING 2 7/8 g PSA 1 g ACCEPTABLE.
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| 601750 SN-VT ---- RHU-63 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 16375, TEMPERATURE 67 DEGREES F.~ SETTZNG 2 7/8", PSA-1g ACCEPTABLE.
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| F32 'ESIDUAL HEAT REMOVAL LINE 10G-AC-601 DRAWINGS! B-20A Summary Exam Item NDE Number Categ Number 'omponent Component Type Exam 601760 SN-VT RHU AUG VT-3 MECHANZCAL SNUBBER 92 SERIAL NUMBER 8629, TEMPERATURE 66 DEGREES F., SETTING 2 3/8"g OTHER: SADDLE CLAMP HAS TAPE AROUND PIPE BETWEEN SADDLE CLAMP PSA-10'CCEPTABLE.
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| AND PIPE. ACCEPTABLE.
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| ----
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| k 601769 SN-VT RHU-71 (NORTH) AUG VT-3 MECHANICAL SNUBBER 92 SERZAL NUMBER 1 1466'EMPERATURE 67 DEGREES F g SETTING 2 7/16 ~ PSA 1 g ACCEPTABLE.
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| 76
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| Ro E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~
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| RESIDUAL HEAT REMOVAL LINE 10G-AC-601 (CONT.) DRAWINGS t B-20A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601770 SN-VT RHU-71 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 11465, TEMPERATURE 67 DEGREES F., SETTING 2 9/16", PSA-lf ACCEPTABLE.
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| F33 ~ RHR PUMP A SUCTION LINE DRAWINGS t B-20A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601780 SN-VT RHU-72 AUG VT-3 MECHANZCAL SNUBBER 92 SERIAL NUMBER 8606'EMPERATURE 67 DEGREES Fo g SETTING 3 1/8 g PSA 10/
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| ACCEPTABLE, F34+ RESIDUAL HEAT REMOVAL LINE 10D-AC-601 DRAWZNGSt B-20 Summary Exam Item NDE Number Categ Number Component Component. Type Exam 601790 SN-VT RHU-75 AUG VT-3 MECHANICAL SNUBBER 92.- SERIAL NUMBER 8632, TEMPERATURE 67 DEGREES F.~ SETTING 3 1/2", PSA-10/
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| ACCEPTABLE.
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| 77
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| Ro E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT, F35 ~ RESIDUAL HEAT REMOVAL LINE 6K-AC-151 DRAWINGS! B 21 Summary Exam "
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| Item NDE Number Categ Number Component Component Type Exam 601800 SN-VT RHU-92 AUG VT-3 MECHANZCAL SNUBBER 92OTHER: BORIC ACID ON BASE PLATE. EXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 16376'EMPERATURE 76 DEGREES F g SETTING 2 1/4 J,PSA 1J EXAM AFTER REMOVAL OF BORIC ACID) GENERAL CORROSION ON BASE ACCEPTABLE'NSIGNIFZCANT:
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| PLATEg SLIGHT CORROSION ON STUDS 6 NUTS BUT ARE SECURED IN FLOOR 6 UNABLE TO TURN BY HAND. ACCEPTABLE.
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| 601801 SN-FT RHU-92 AUG FT MECHANICAL SNUBBER 92 PSA 1 g SERIAL NUMBER 1 6376 g REMOVED'ESTED 6 REZNSTALLED ACCEPTABLE.
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| F36 ~ L+P ~ SAFETY INJECTION LINE FROM RWST DRAWINGS ! B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601810 SN-VT RHU-109 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 1 1463 g TEMPERATURE 80 DEGREES Fo ~ SETTING 2 1/8 ~ PSA 1 ~
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| ACCEPTABLE.
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| 601820 SN-VT RHU-110 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 16373 / TEMPERATURE 80 DEGREES F g SETTING 2 1/8 g PSA 1 g ACCEPTABLE.
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| F37 ~ SAFETY INJECTION PUMP A SUCTION LINE DRAWINGS! B 16B Summary Exam Item NDE Number Categ Number Component Component Type Exam 601830 SN-VT RHU-119 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 15766, TEMPERATURE 74 DEGREES F.i SETTING 1 5/8", PSA-3, ACCEPTABLE.
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| 78
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| Ro E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990 1999 Interval, Third Outage 1992
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| "
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| ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT, t F38 ~ SAFETY INJECTION LINE 8H-SI-151 DRAWINGS! B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601840 SN-VT RHU-123 AUG VT-3 MECHANZCAL SNUBBER 92 SERIAL NUMBER 15765 g TEMPERATURE 75 DEGREES F i SETTING 2 1/2 g PSA 3 i ACCEPTABLE.
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| F39 ~ 8 o P ~ SAFETY INJECTION LINE TO LOOP A COLD LEG DRAWINGS'-17, Summary Exam Item Number; Categ Number Component'IU-3 Component Type Exam 601850 SN-VT AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 8416, TEMPERATURE 61 DEGREES F., SETTING 3 1/4"i PSA-10i ACCEPTABLE.
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| F40. H.P. SAFETY INJECTION LINE TO LOOP B COLD LEG DRAWINGSt A-16 Summary Exam Item NDE
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| 'umber Categ Number Component Component Type Exam 601860 SIU-47 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 15349 i TEMPERATURE 60 DEGREES F ~ i SETTING 3 i PSA 3 i ACCEPTABLE.
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| F41 ~ 10-1Ne RESIDUAL HT REMOVAL (IN) DRAWINGS'-14 E
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| Summary Exam Item NDE Number Categ Number Component Component Type Exam 601870 SN-VT ---- SIU-52 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 15348 i TEMPERATURE 64 DEGREES F i SETTING 2 1/2 i PSA 3 g ACCEPTABLE.
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| 79
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| )l 4
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| Ro Eo GINNA NUCLEAR POWER PLANT
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| ,1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT, t F42 'VCoWTRo-TO A 5 B DIESEL GEN+WTR+COOLERS DRAWINGS! C-13 Summary Exam Item NDE Number Categ Number Component Component Typi Exam 601890 SN-VT SWU-254 AUG VT-3 MECHANZCAL SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 12508i TEMPERATURE 56 DEGREES, F g SETTI NG 1 5/3 2 I PSA 1 /2 g
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| ~ ACCEPTABLE ~ I I ZNS GN F ICANT I D TAG REPLACED.
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| 601891 SN-FT SWU-254 AUG(EXPANDED) FT MECHANICAL SNUBBER 92 PSA 1 /2 g SERIAL NUMBER 1 2 508 j I REMOVED I TESTED AND RE NSTALLED ACCEPTABLE, F43 'ERVICE WATER LINE 8L-SW-125 DRAWINGSs,B-50A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601900 SN-VT SWU-308 AUG VT-3 MECHANICAL,SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 8031i TEMPERATURE 74 DEGREES F i SETTING 3 i PSA
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| ----
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| 10'CCEPTABLE'01901 SN-FT SWU-308 AUG(EXPANDED) FT MECHANICAL SNUBBER 92 PSA 10'ERIAL NUMBER 803 1 I REMOVED'ESTED AND REZNSTALLED ACCEPTABLE.
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| 601910 SN-VT ---- SWU-309 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 10073 i TEMPERATURE 56 DEGREES F ~ i SETTING 3 3/8" i PSA-10/
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| ACCEPTABLE+
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| 601911 SN-FT -- SWU-309 AUG FT MECHANICAL SNUBBER 92 PSA 10'ERIAL NUMBER 10073 REMOVED'ESTED AND REINSTALLED ACCEPTABLE.
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| 80
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| Re E ~ GINNA NUCLEAR POWER PLANT 1990 -Inservice Inspection Report 1999 Interval, Thi'rd Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
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| F44 ~ SVCoWTRo INTMDoBLDGo16 HDo TO PEN 312 320 DRAWINGSt C-16B Summary Exam Item NDE Number Categ Number Component Component Type Exam 601920 SN-VT SWU-370 AUG VT-3 MECHANICAL SNUBBER I 92 SERIAL NUMBER 1 1464 i TEMPERATURE 65 DEGREES F i SETTING 2 1/4 i,PSA 1 i ACCEPTABLE'45+
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| STANDBY AUX FW THRU PEN 123 TO B S/G FWHD DRAWZNGSt C-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601930 SN-VT AFU-205 (AFW-10) AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER 1 2900 g TEMPERATURE 69 DEGREES F ~ i SETT ING 3 1 /4 i GRI NNELL 1 1 /2 i ACCEPTABLE ~
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| 601931 SN-FT -- AFU-205 (AFW-10) AUG- FT HYDRAULIC SNUBBER 92 RE JECT GRINNELLi SERIAL NUMBER 1 2900 i SIZE 1 1/2 i FAILED COMPRESSION BLEED RATE. NO RECORDABLE READJUSTED TO MEET REQUIRED SETTING 6 REZNSTALLED.
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| 601940'N-VT - - AFU-208 (AFW-13) AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL, NUMBER 2 10 1 0 i TEMPERATURE 59 DEGREES F ~ i SETTING 2 1 /1 6 g GRZNNELL 1 1/2, ACCEPTABLE.
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| F46 'TANDBY AUX FW THRU PEN 119 TO A S/G FWHD DRAWINGS t C-20
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| .Summary Exam Item NDE Number Categ Number Component Component Type Exam 601970 SN-VT AFU-224 (AFW-28) AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER 12905 i TEMPERATURE 70 DEGREES F ~ i SETTING 2 7/8 i GRINNEL 1 1/2, ACCEPTABLE.
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| 81
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| R. E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~
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| STANDBY AUX FW THRU PEN 119 TO A S/G FWHD (CONT.) DRAWZNGSt C-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601980 SN-VT AFU-226 (AFW-27) AUG VT-3 HYDRAULIC SNUBBER 92 - SERIAL NUMBER 12901, TEMPERATURE 71 DEGREES F., SETTING 3 1/8". GRZNNEL 1 1/2, ACCEPTABLE.
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| 601990 SN-VT AFU-225 (AFW-29) AUG VT-3 HYDRAULIC SNUBBER 92 - REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 12906, TEMPERATURE 68 DEGREES F i SETTING 1 1/2 i GRINNEL 1 1/2i ACCEPTABLE'01991 SN-FT AFU-225 (AFW-29) AUG(EXPANDED) FT HYDRAULIC SNUBBER 92 - GRlNNELL SNUBBER, SERIAL NUMBER 12906 PASSED.
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| 602000 SN-VT -- AFU-227 (AFW-31) AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 25594 i TEMPERATURE 72 DEGREES F ~ I SETTING 4 1/8 g PSA 3 g ACCEPTABLE+
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| F47 ~ PRESS o RELIEF FM PRESS TO RELIEF MANIFOLD DRAWINGS! S-2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602010 SN-VT N601 AUG VT-3 HYDRAULIC SNUBBER 92 - REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 6565, TEMPERATURE 59 DEGREES F kg SETTING 3 9/16 g GRINNELL SIZE 2i ACCEPTABLE'2
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| Ro Bo GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. t PRESS, RELIEF FM PRESS.TO RELIEF MANIFOLD (CONT+) DRAWINGS! S-2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602011 SN-FT N601 AUG(EXPANDED) . FT HYDRAULZC SNUBBER 92 ZTT GRINNELL, SERIAL NUMBER 6565) REMOVED'ESTED AND REINSTALLED ACCEPTABLE.
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| 602020 SN-VT ---- N602 AUG HYDRAULIC SNUBBER 92 SERIAL NUMBER 6568 g TEMPERATURE 68 DEGREES F o ~ SETTING 2 7/ 16 g GRINNELL SIZE 2, ACCEPTABLE.
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| 602030 SN-VT ---- N604 AUG VT-3 HYDRAULIC SNUBBER 92 - SERIAL NUMBER 6566, TEMPERATURE 70 DEGREES F.g SETTING 1 9/16"i GRINNELL SIZE 2g ACCEPTABLE.
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| 602040 SN-VT N605 AUG VT-3 HYDRAULIC SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER 6561'EMPERATURE 62 DEGREES F.g SETTZNG 2 11/16"g GRINNELL SIZE 2g ACCEPTABLE'02041 SN-FT ---- N605 AUG FT HYDRAULIC SNUBBER 92 ITT GRINNELLg SERIAL NUMBER 656 1 g NCR92 247 g REMOVED g PERFORMED CORRECTIVE MAINTENANCE, TESTED AND REINSTALLED - ACCEPTABLE.
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| 602050 SN-VT ---- N607 AUG VT-3 HYDRAULIC SNUBBER f 92 SERIAL NUMBER 6562 g TEMPERATURE 71 DEGREES F g SETTING 3 5/8 GRINNEL SIZE 2, ACCEPTABLE.
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| 602060 SN-VT ---- N608 AUG HYDRAULIC SNUBBER 92 - SERIAL NUMBER 6563, TEMPERATURE 62 DEGREES F., SETTING 3 5/8", GRINNELL SIZE 2, ACCEPTABLE.
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| 83
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| 4 0
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| Ro Eo GINNA NUCLEAR POWER PLANT 1990 li
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| - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT PRESS @RELIEF FM PRESS TO RELIEF MANIFOLD (CONT o ) DRAWINGS j S 2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602061, SN-FT N608 AUG FT HYDRAULIC SNUBBER 92 - ITT GRZNNELL, SERIAL NUMBER 6563.
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| 602070 SN-VT ---- N615 AUG VT-3 HYDRAULIC SNUBBER 92 - SERIAL NUMBER 6564, TEMPERATURE 71 DEGREES F.i SETTING 2 3/8", GRINNELL SIZE 2i ACCEPTABLE.
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| 602080 SN-VT ---- N616 AUG VT-3 HYDRAULIC SNUBBER
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| ,92 SERIAL NUMBER 6567 i TEMPERATURE 70 DEGREES F ~ i SETTING 2 3/4 i GRZNNEL SIZE 2i ACCEPTABLE.
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| F48 ~ POWER PRESS +RELIEF LINE DRAWINGS t S-1 Summary Exam Item NDE Number Categ 'umber Component Component Type Exam 602090 SN-VT PS-2 AUG VT-3 HYDRAULIC SNUBBER 92 EXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER PD87239-1244, TEMPERATURE 78 DEGREES F g SETTING 4 i PAUL MONROE'CCEPTABLE'02091 SN-FT ---- PS-2 AUG FT HYDRAULIC SNUBBER 92 SERIAL NUMBER PD87239-1244, PAUL MONROE.
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| 602100 SN-VT ---- 'S-4 AUG VT-3 HYDRAULIC SNUBBER 92 REEXAM AFTER FUNCTIONAL TEST. SERIAL NUMBER PD-86144-1152, TEMPERATURE 59 DEGREES F i SETTING 1 1/8 i PAUL MONROEi ACCEPTABLE'NSIGNIFICANT TAG TO BE INSTALLED BY MEIS.
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| I'E 602101 SN-FT ---- PS-4 AUG(EXPANDED) FT HYDRAULIC SNUBBER 92 PAUL MONROE i SERIAL NUMBER PD 86 144 1 1 52 i REMOVED i TESTED AND REINSTALLED - ACCEPTABLE.
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999. Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS . CONT. t F49 '-IN PRESSURIZER RELIEF LINE DRAWINGS i A-12 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602110 SN-VT PS-5 AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER PD 87239 1246 g TEMPERATURE 68 DEGREES F g SETTING 2 3/4
| |
| ,PAUL MONROE'CCEPTABLE.
| |
| 602120 SN-VT PS-6 AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER PD 81767 1239@ TEMPERATURE 68 DEGREES F g SETTING 3 5/8 g PAUL MONROE, ACCEPTABLE.
| |
| 602130 SN-VT PS-8 AUG VT-3 HYDRAULIC SNUBBER 92 SERIAL NUMBER PD 86144 1 159 g TEMPERATURE 68 DEGREES F g SETTING 2 15/16/
| |
| PAUL MONROE, ACCEPTABLE.
| |
| F50+ POWER PRESS+RELIEF LINE DRAWINGS'-1A Summary Exam Item NDE Number Categ Number Component Component Type Exam 602140 SN-VT PS-9 AUG VT-3 HYDRAULIC SNUBBER 92 REJECT: FILL RING SHOWS INCORRECT (LOW) FLUID LEVEL, NCR92-161 GENERATED FOR CORRECTIVE ACTION. REEXAM FOR FUNCTIONAL TEST+ SERIAL NUMBER PD 86144 1154'EMPERATURE 62 DEGREES F g SETTING 3 g RED 1/2g GREEN 1/16'AUL MONROE, ACCEPTABLE.
| |
| 602141 SN-FT ---- PS-9 AUG FT HYDRAULIC SNUBBER 92 PAUL MONROE'ERIAL NUMBER PD 86144-1154'EMOVED'ESTED REINSTALLED ACCEPTABLE.
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| 602150 SN-VT PS-10 AUG VT-3 HYDRAULIC SNUBBER SETTING 3 1 5/ 16
| |
| '
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| 92 SERIAL NUMBER PD 86 144 1 57 g TEMPERATURE 68 DEGREES F g PAUL MONROE, ACCEPTABLE.
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| 85
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| R>> E>> GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~
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| POWER PRESS>>RELIEF LINE (CONT.) DRAWINGS'-1A 4
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| Summary Exam Item NDE Number Categ Number Component Component Type Exam 602160 SN-VT PS-11 AUG HYDRAULIC SNUBBER 92 - TEMPERATURE 68 DEGREES F., SETTING 2 1/4", PAUL MONROE'CCEPTABLE.
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| SERIAL NUMBER COULD NOT BE SEEN, "INTERNAL CONTAMINATION" STICKER COVERING ZT>> STICKER HAS BEEN ZN PLACE SINCE THE 1991 EXAM.
| |
| F51 'VCS RCP B LEAKOFF RET. DRAWINGS'-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602200 SN-VT CVU-131 AUG VT-3 MECHANICAL SNUBBER 92 - SERIAL NUMBER 254'EMPERATURE 57 DEGREES F.g SETTING 2 5/8"g PSA-3g ACCEPTABLE.
| |
| 602300 SN-VT CVU-550 AUG VT-3 MECHANICAL SNUBBER 92 SERIAL NUMBER 18 190 g TEMPERATURE 54 DEGREES F>> g SETTING 2 1/4 g PSA 3 g ACCEPTABLE.
| |
| F52 'TANDBY AUX FW THRU PEN 123 TO B S/G FWHD DRAWINGS! C-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602400 SN-VT AFU-209 AUG VT-3 HYDRAULZC SNUBBER 92 SERIAL NUMBER 12907, TEMPERATURE 62 DEGREES F., SETTING 2 1/4", GRINNELL 1 1/2g ACCEPTABLE.
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| 86
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| Ro E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990'- 1999 Interval, Third Outage 1992 ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. t F53+ STANDBY AUX FW THRU PEN 119 TO A S/G FWHD DRAWINGS t C-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602500 SN-VT AFU-229 AUG VT-3 HYDRAULIC SNUBBER 92 SERZAL NUMBER 12903 g TEMPERATURE 63 DEGREES F ~ i SETTING 2 1/8 i GRINNELL SIZE 1 1/2, ACCEPTABLE.
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| G. STEAM GENERATOR EDDY CURRENT EXAMINATIONSt I
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| Glo STEAM GENERATOR A DRAWZNGSt N/A Summary Exam Item NDE Number Categ Number Component Type Exam 800000 B-Q B16.20 OPEN 20'%omponent GENERATOR TUBES ASME PREVIOUS IDENTIFIED DEGRADATION >
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| 92 PREVIOUS INDICATIONS > 20% i OTHER THAN WASTAGE i WERE EXAMINED TO THE EXTENT OF DEGRADATION AS A MINIMUM. SINCE NO GROWTH HAS BEEN SEEN IN WASTAGEi ONLY PREVZOUS INDICATIONS > 30% WERE EXAMINED TO INCLUDE AREA OF WASTAGE AT A MINIMUM. SEE 'THE 1992 EDDY CURRENT REPORT FOR DETAILS.
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| 800150 B-Q B16.20 OPEN GENERATOR TUBES ASME ET 20% ROTATING RANDOM SAMPLE FULL LENGTH 92 20% RANDOM SAMPLE OF ALL OPEN UNSLEEVED TUBES WERE EXAMINED FULL LENGTH (F/L). SEE THE 1992 EDDY CURRENT REPORT 'FOR DETAILS.
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| 800200 SG-ET RG-1.83 OPEN GENERATOR TUBES AUG ET 100% OF ALL UNSLEEVED TUBES 92 100'%F ALL OPEN UNSLEEVED TUBES WERE EXAMINED TO THE TOP OF TUBESHEET ON THE HOT LEG SIDE AS A MINIMUM. SEE THE 1992 EDDY CURRENT REPORT FOR DETAILS.
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| 87
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 -Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I STEAM GENERATOR EDDY CURRENT EXAMINATIONSt CONT ~
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| STEAM GENERATOR A (CONT>> ) DRAWINGSt N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 800350 SG-ET RG-1.83 SLEEVED GENERATOR AUG ET TUBESi 20t ROTATING RANDOM SAMPLEi EACH SLEEVE TYPE 92 20't RANDOM SAMPLE OF EACH TYPE OF SLEEVED GENERATOR TUBES WERE EXAMINED FROM SLEEVE END TO SLEEVE END AS A MINIMUM. SEE THE 1992 EDDY CURRENT REPORT FOR DETAILS.
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| G2 ~ STEAM GENERATOR B DRAWINGS! N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 801000 B-Q , B16.20 OPEN GENERATOR TUBES ASME ET PREVIOUS IDENTIFIED DEGRADATION > 20t 92 PREVIOUS INDICATIONS > 20't i THROUGH WALLi OTHER THAN WASTAGE'ERE EXAMINED TO THE EXTENT OF DEGRADATION AS A MINIMUM. SINCE NO GROWTH HAS BEEN SEEN IN WASTAGE, ONLY,PREVIOUS INDICATIONS > 30t WERE EXAMINED TO INCLUDE AREA OF WASTAGE AT A MINIMUM. SEE THE 1992 EDDY CURRENT REPORT FOR DETAILS.
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| 801150 B-Q B16.20 OPEN GENERATOR TUBES ASME ET 20't ROTATING RANDOM SAMPLE FULL LENGTH 92 20t RANDOM SAMPLE OF ALL OPEN UNSLEEVED TUBES WERE EXAMINED FULL LENGTH (F/L). SEE THE 1992 EDDY CURRENT REPORT FOR DETAILS.
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| 801200 SG-ET RG-1.83 OPEN GENERATOR TUBES AUG ET 100t OF ALL UNSLEEVED TUBES 92 - 100t OF ALL OPEN UNSLEEVED TUBES WERE EXAMINED TO THE TOP OF TUBESHEET ON THE HOT LEG SIDE AS A MINIMUM. SEE THE 1992 EDDY CURRENT REPORT FOR DETAILS.
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| 88
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| Ro E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Third Outage1992 ATTACHMENT I STEAM GENERATOR EDDY ClHOMNT EXAMINATIONSt CONT.
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| STEAM GENERATOR B (CONT+ ) DRAWINGS! N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 801350 SG-ET RG-1.83 SLEEVED GENERATOR AUG ET TUBES'0% ROTATING RANDOM SAMPLERS EACH SLEEVE TYPE 92 20% RANDOM SAMPLE OF EACH TYPE OF SLEEVED GENERATOR TUBES WERE EXAMINED FROM SLEEVE END TO SLEEVE END AS A MINIMUM. SEE THE 1992 EDDY CURRENT REPORT FOR DETAILS .
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| 89
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| FORM NIS.2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
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| : 1. Owner Rochester Gas 8z Electric Corp. Date 31 July 1992 Name 89 East Ave., Rochester, N.Y. 14649 'heet of Address
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| : 2. Plant R.E. Ginna Nuclear Power Plant Unit Name 1503 Lake Road, Ontario,N.Y. 14519 Address Repair Organization P.O. No., Job No., etc.
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| : 3. Work Performed by Type Code Symbol Stamp Name Authorization No. N A Expiration Date N A Address
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| : 4. Identification of System
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| : 5. (a) Applicable Construction Code (q) 19 Edition, Addenda, Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19
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| : 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Replaced, (Yes Name of Component Name of Manufacturer Manufacturer Senal No.
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| '' Board No.
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| Other Identification Year Built or Replacement or No)
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| : 7. Description of Work B. Tests Conducted:
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| ( )
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| Hydrostatic Other Q Q
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| Pressure 'si Pneumatic Q Nominal Operating Pressure Test Temp.
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| Q oF NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is BS in. x 11 in., (2) informa-tion 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 rded at the top of this form.
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| This Form (E00030) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y. 10017
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| (+) SEE aATTACEIMENT II"
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| FORM NIS-2 (Back)
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| : g. Remarks Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE
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| (+ac)
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| We certify that the statements made ln the report are correct and this conforms to the rules of the repair or replacement ASME Code, Section XI.
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| Type Code Symbol Stamp N/A Certificate of Authorization No.
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| N/A Expiration Date N/A I
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| Signed F. A. Kle acki 31 July Owner or Owner's Des gnee, Title ISI Engineer 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 sB g Co. of peri x Z) Cr. have inspected the components described in this Owner's Report during the period to and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
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| 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 I 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 Commissions +National Bo rd, State, Province, and Endorsements D.t. Ig 5'X
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| (+) SEE "ATTACHMENTIIn
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| (**) repair, replacement or modification identified within "Attachment IIn
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| Ro Eo OINNA NUCLEAR POWER PLANT Inspection Report 1990 - Inservice 1999 Interval, Third Outage 1992 ATTACHMENT II REPAIR REPLACEMENT and MODIFICATION PROGRAM The Repair, Replacement and Modification (RR&M) Program, as identified within the "Appendix B" Program of the Ginna Station Quality Assurance Manual, 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.
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| The following information 'is being presented as required by ASME Section XI.
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| Owner: Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 Plant Location: R. E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, New York 14519 Date of Re ort: 31 July 1992 When an item under the rules and requirements of the "Appendix B" 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".
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| A "Code Service Induced Rejectable Indication" occurs when a component under'he 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.
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II 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.
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| A "Corrective Action Activity" may'ccur 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.
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| The following groups performed applicable Repair, Replacement and/or Modification activities during the 1992. Outage.
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| : 1. Rochester Gas & Electric, Ginna Station
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| : 2. Ginna Station Projects Department Nuclear Power Services Philadelphia, Pa.
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| : 3. ITI Movats 200 Chastain Center Blvd.
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| Suite 250 Kennensaw, Ga. 30144-5512
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| : 4. ABB Combustion Engineering, Inc.,
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| 1000 Prospect Hill Road
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| ~
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| P.O. Box 500 Windsor, Connecticut 06095-.0500
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| : 5. B & W Nuclear Services Millridge Road Company'55 Lynchburg, Virginia 24502-4341 Each group performing Repair, Replacement or Modification work during the 1992 outage is listed above and their corresponding number will be identified in each Code activity below.
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| Re E ~ OINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II CODE REPAIRS:
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| 1~ ASME Class: 3 ~Sstem: Service Water GORR No: 92-T-017 v
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| Construction Code: B31.1, 1986 Edition Work Performed B : 3 Name of Com onent: Valve 4651 Work Descri tion Remarks: During the valve replacement activity, a weld prep was being performed and a pit discovered using the PT method. The pit area was cleaned and rewelded.
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| Reexamination of the pit area using the PT method was performed and acceptable as documented within WO number 9122001. The weld prep was then finalized for welding of the replacement. See "Replacement and Modification" section for details of the replacement activity.
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| 2 ~ ASME Class: 2 ~Sstem: Service Water GORR No: 91-M-001 Line: > 2" Construction Code: B31.1, ASME Section III, 1986 Edition Work Performed B : 1 Name of Com onent: Containment Fan Motor Cooler D, ACA09.
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| Work Descri tion Remarks: During multiple union disconnections, this action resulted in mechanical cracking of the existing bronze piping. This activity was controlled under WO number 9101554 and NCR91-503. A repair by silver brazing was performed on the copper cooler discharge header tube &
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| cooper discharge pipe coupling adaptor. 'A Construction Code VT-1 was performed and accepted as documented within the work order. The code required hydrostatic test was deferred with the implementation of Code Case N-416. The required augmented VT-2 Inservice Leakage test and the accompanying PT examinations were performed and acceptable.
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| C' Re E ~ GINNA NUCLEAR POWER PLANT Inspection Report 1990 - Inservi.ce 1999 Interval, Third Outage 1992 CODE REPAIRS'CONT ~ )
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| : 3. ASME Class: 2 ~S stem: Feedsater GORO No: 92-M-001 v
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| Construction Code: ASME Section III, 1986 Edition Work Performed B : 1 Name of Com onent: FWU-54 & FWU-55 Supports Work Descri tion Remarks: FWU-54, a Mechanical Snubber was to be removed for Functional Testing. At that time, discovered that FWU-55 prohibit the removal of FWU-54. A Code it was Repair was performed by drilling (metal removal) into FWU-55 in order to provide access for pin removal and subsequent support removal. FWU-54 was also drilled and tapped to allow for rebolting of supports. This action was needed for accessibility and maintainability of these components. This activity was controlled under WO number 9220447 and NCR92-012.
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| Upon reinstallation, VT-3 baseline examinations were performed on both supports and acceptable as documented within NDE summary examination record numbers 92096600 & 92096525.
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| ASME Class: 2 ~S stem: Safety Injection GORR No: 92-M-003 Construction Code:
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| Work Performed B :
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| ASME 1
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| Section III, 1986 i Edition Name of Com onent: SIU-85, Integral Attachment on'igid Support.
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| Work Descri tion Remarks: During ISI examination of SIU-85 integral attachment, cold lap indication was identified being beyond acceptable limits. A Code Repair cycle was initiated by welding. This repair activity was controlled by NCR92-130 and WO number 9220640. A PT baseline examination was performed and accepted as documented within NDE summary exam record 92163021.
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| 0 Ra Ea OINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II CODE REPAIRS ( CONT ~ )
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| : 5. ASME Class: 3 ~sstem: ComPonent Cooling Wtr. GORR No: 92-M-004 Construction Code: ASME Section Work Performed B : 1 III, 1986 Edition Name of Com onent: CCU-90, Xntegral Attachment on Rigid Restraint Support.
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| Work Descri tion Remarks: During XSX examination of CCO-90 integral attachment, undersize welds and slag indications were identified. A Code Repair cycle was initiated by welding. This repair activity was controlled by NCR92-131 and WO number 9220639. A PT baseline examination was performed and acceptable as documented within NDE summary exam record 92500240.
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| : 6. ASME Class: 2 ~Sstem: S/G Slowdown GORR No: 92-M-005 Construction Code: ASME Section Work Performed B : 1 III, 1986 Edition Name of Com onent: Base Metal Repair on pipe during V 3520 replacement.
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| Work Descri tion Remarks: During the replacement activity of Valve 3520 as identified within GORR 92-T-025, base metal damage was caused by a grinding operation. A Code Repair Cycle was performed by welding. This repair activity was controlled by WO number 9122124. A PT examination was performed on the repaired area and acceptable. Upon completion of the replacement activity, a VT-2 Leakage examination was performed as well as surface examinations to comply with the requirements of Code Case N-416.
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| 7 ~ ASME Class: 2 ~S stem: Feedwater GORR No:
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| 1" 92-M-006'ine:
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| Construction Code: ASME Section IIX, 1986 Edition Work Performed B : 1 Name of Com onent: Weld leak by Valve 4099E, NPS Work Descri tion Remarks: During a maintenance activity, a l.
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| welder originated a pin hole weld defect causing a leak. A Code Repair'as performed by removing the weld and rewelding.
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| This repair activity was controlled by WO number 9200747.
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| Construction Code VT and PT examinations were performed and accepted. Section XI baseline examinations were not required.
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| I R. E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II CODE REPAIRS: (CONT )
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| : 8. ASME Class: 1 ~Sstem: Reactor Coolant System GORR No: 92-E-036 Line: N/A v
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| . Construction Code:
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| Work Performed B :
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| ASME 5
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| Section III, 1986 Edition Name of Com onent: Steam Generator "A" (EMSO1A) Tubesg Explosive Sleeves Work Descri tion Remarks: During Eddy Current Examination of Steam Generator "A", a total of 194 tubes containing defects were identified and determined to be candidates for B&W bi-metallic explosive sleeves. The location of these defective tubes are identified within the "1992 Steam Generator Eddy Current Inspection Report". This activity was controlled under WO number 9220407, M-43.55 and B&W document 51-.1212535-01.
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| Upon completion of the installation activity, baseline Eddy Current Examinations were performed and accepted on these sleeves. Eddy Current examinations is also utilized to verify proper weld location and provide comparison to assure weld soundness.
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| : 9. ASME Class: 1 ~S stem: Reactor Coolant System GORR No: 92-E-037 Line: N/A v Construction Code: ASME Section III, 1986 Edition Work Performed B : 4 Name of Com onent: Steam Generator "A&B" (EMSO1A,EMSO1B)
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| Tubes, Welded Sleeves Work Descri tion Remarks: During Eddy Current Examination of Steam Generator "A & B", a total of 231 tubes containing defects were identified and determined to be candidates for CE welded sleeves. A total of 36 welded CE sleeves were installed in the "A" Steam Generator. A total of 195 welded CE sleeves were installed in the "B" Steam Generator. The location of these defective tubes are identified within the "1992 Steam Generator Eddy Current Inspection Report". This activity was controlled under WO number 9220407, M-43.55 and CE report CEN-320-P. Upon completion of the installation activity, UT examinations were performed on the Upper Sleeve Weld while VT examinations were performed on the Lower Sleeve Weld. Baseline Eddy Current Examinations were performed and accepted on these welded CE sleeves.
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| e 4
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| Re Ee GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Repert 1999 Interval, Third Outage 1992 ATTACHMENT II CODE REPAIRS (CONT. )
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| : 10. ASME Class: 1 ~S stem: Reactor Coolant System'GORE No: 92-E-038 Line: N/A v Construction Code: ASME Section III, 1986 Edition Work Performed B : 4 Name of Com onent: Steam Generator uA&Bu (EMS01A,EMS01B)
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| Tubes, Welded Plugs Work Descri tion Remarks: During Eddy Current Examination of Steam Generator "A 6 B", a total of 20 tubes containing defects were identified and determined to be candidates for CE welded plugs. A total of 4 welded CE plugs were installed in the "A" Steam Generator. A total of 16 welded CE plugs were installed in the "B" Steam Generator. The location of these defective tubes are identified within the "1992 Steam Generator Eddy Current Inspection Report". This activity was controlled under WO number 9220407, M-43.55 and CE report CEN-320-P. Upon completion of the installation activity, VT examinations were performed and acceptable.
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| E Re E. GZNNA NUCLEAR POWER PLANT 1990 - Znservice Znspecti.on Report 1999 Znterval, Third Outage 1992 ATTACHMENT ZZ REPLACEMENTS AND MODIPICATIONS 1~ ASME Class: 3 ~S stem: Service Water GORR No: 92-T-001 Construction Code: B31.1, 1955 Edition Work Performed B : 1 Name of Com onent: "D" Service Water Pump "PSW01D", Discharge Flange Bolt replacement.
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| Work Descri tion Remarks: A 7/8" bolt was replaced on the discharge flange of the "D" Service Water Pump. The bolt was replaced due to normal wear/corrosion of this item. The replacement activity was controlled by WO number 9040169. The bolt was obtained from Nova Machine of Middleburg Heights, Ohio under PO NQ 12396AJD. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within NDE summary record number 911295.
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| 2 ~ ASME Class: 3 ~S stem: Service Water GORR No: 92-T-002 Construction Code: 531.1, 1955 Edition Work Performed B : 1 Name of Com onent: Hanger Pin, Bracket Bolts and Disk assembly for Valve 4604 on the "D" Service Water Pump Discharge.
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| Work Descri tion Remarks: Replacement of Hanger Pin, Bracket Bolts (3/4") and Disk assembly for Valve 4604 on the "D" Service Water Pump Discharge, line. This replacement activity was necessary because the bolts holding the disk hinge had vibrated loose causing excessive wear on the other internal parts. To prevent future reoccurrence, lockwires were installed to properly retain bolts. This replacement activity was controlled by WO number 9040169, and TSEE's 91-149 & 90-242. Parts obtained for this activity were the same 'as original (Crane Chapman 151-A) except for the following: Disc assembly under PO NEG 37023-84-1. Hinge bracket bolt under PO NQ 12066 AJD. Both items were obtained from Crane, Indian Orchard, Maine. A PT construction 'code examination was performed on the disc. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within NDE summary record number 911295.
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| Re E ~ OINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS (CONT.)
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| 3 ~ Class: 3 ~S stem: CVCS, Boric Acid GORR No: 92-T-003 Construction Code: B31.1, 1955 Edition Work Performed B : 1 Name of Com onent: Suction flange bolting on the "A" Boric Acid Transfer Pump.
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| Work Descri tion Remarks: Four (4) bolts with associated nuts were replaced on the suction flange of the "A" Boric Acid Transfer Pump. This replacement activity was necessary because of normal wear and end, of service life. This replacement activity was controlled by WO number 9140174 and TSEE 91-088.
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| The studs were obtained from Energy Steel of Auburn Hills, MI.
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| under PO NQ10487. The nuts were obtained from Nova Machine of Middleburg Heights, OH. under PO NQ12396AJD. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO number 9140174.
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| 4 ~ ASME Class: 3 ~S stem: Waste Gas GORR No: 92-T-004 Line: N/A Construction Code: B31.1, 1955 Edition Work Performed B : 1 Name of Com onent: Waste Gas Compressor "A", PWD04A (Pump)
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| Work Descri tion Remarks: The "A" Waste Gas Compressor was replaced with a rebuilt, "like-for-like" spare component. This replacement activity consisted .of disconnecting the old and reconnecting the spare. This action was necessary because the compressor was not obtaining the desired discharge pressure and was replaced as part of a normal troubleshooting activity.
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| This replacement activity was controlled by WO number 9122199.
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| The component was obtained from Nash Engineering under drawing 14-1124 and Westinghouse Order 54-E-70518-B. The new model number is AL-621C. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO 9122199.
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| e 0
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| Ra E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS (CONT ~ )
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| : 5. ASME Class: stem: Service Water GORR No: 92-T-005
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| '"': "/
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| Construction 3 ~S Code: Gilbert BOM MD-1, Specification RO-2204.
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| ASME Section addenda.
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| III, 1983 Edition, Summer '85 Work Performed B : 1 Name of Com onent: "B" Service Water Pump, PSW01B, Gland Studs.
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| Work Descri tion Remarks: During a PM activity, the original studs were too short for full nut engagement. This deficiency was noted by QC surveillance and resulted in stud replacement.
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| This replacement activity was controlled by WO numbers 9024081 and 9141062, and TSEE 91-546. The studs were obtained from Energy Steel of Auburn Hills, MI. under PO NQ10487-BJD. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO 9141062.
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| : 6. ASME Class: 3 ~Sstem: Diesel Air Start GORR No: 92-T-006 Construction Code: B31.1, 1955 Edition, MSS-SP69 Work Performed B : 1 Name of Com onent: PS-8, Rod Support Work Descri tion Remarks: During a Non-ISI walkdown, the rod associated with the PS-8 Support was found to be bent due to some physical impact. The Hanger was evaluated to be acceptable per EWR 3596 and calculation g 42031-C-003, rev. 0 (att. A, Sheet A13). A replacement activity was initiated to restore the deficient, acceptable, component support. This replacement activity was controlled by WO numbers 9122672.
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| Components replaced consisted of the following: Nut, supplied by Rochester Screw & Bolt under PO NEG 83456. Washer, supplied by REC Corporation under PO NEG 99107. Rod, supplied by Inland Steel under PO FDN 12159. Upon installation, a VT-3 examination was performed and accepted as documented within the Mainten'ance Examination Record M92142.
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| 10
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| Rs E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Repart 1990 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS , (CONTe)
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| : 7. ASME Class: 3 ~S stem: Service Water GORR No: 92-T-008 Construction Code: ASME Section XIX, 1986 Edition Work Performed B : 3 Name of Com onent:" V-4649 Work Descri tion Remarks: Valve 4649 had general corrosion on the seats after 20 years of service and was replaced. This replacement activity was controlled by WO number 9121999 and TSR 91-140. The valve replacement consisted of an approved equivalent supplied by Crane under PO NQ 12921 AJD.
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| Construction Code NDE performed included VT and PT examinations. An ISI VT-2 Leakage examination was performed on the required hydrostatic test for the replacement. The hydrostatic test was performed at ambient temperature at a test factor of 1.1 that produced a pressure range of 165-175 psi. The test was acceptable and documented within the work order.
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| : 8. ASME Class: 3 ~S stem: Service Water GORR No: 92-T-009 v
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| Construction Code:
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| Work Performed B :
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| ASME 3
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| Section III, 1986 Edition Name of Com onent: V-4650 Work Descri tion Remarks: Valve 4650 had general corrosion and was at the end of its'ervice life after 20 years and was replaced. This replacement 'activity was controlled by WO number 9122000 and TSR 91-140. The valve replacement consisted of an approved equivalent supplied by Crane under PO NQ 12921 AJD. Construction Code NDE performed included a VT examination. An ISI VT-2 Leakage examination was performed on the required hydrostatic test for the replacement. The hydrostatic test was performed at ambient temperature at a test factor of 1.1 that produced a pressure range of 165-175 psi. The test was acceptable and documented within the work order.
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| Re E. GINNA NUCLEAR POWER PLANT 1990 -Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: 'CONTe)
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| : 9. ASME Class: 3 ~Sstem: CVCS, Boric Acid GORR No: 92-T-010 Line: N/A Construction Code: B31. 1, 1955 Edition Work Performed B : 1 Name of Com onent: <<A<< Boric Acid Transfer Pump, PCH03A.
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| Work Descri tion Remarks: The <<A>> Boric Acid Transfer Pump required replacement due to front bearing wear. This is a like-for-like replacement and was controlled by WO number 9200209. The pump was obtained by Crane, model g GE20K23HIS.
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| Upon installation, a VT-2 Functional Leak test was performed and accepted as documented within WO number 9200209.
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| : 10. ASME Class: 2 ~Sstem: Main Steam GORR No: 92-T-011 Construction Code:
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| Work Performed B :
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| ASME 3 ~
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| Section III, 1977 Edition Name of Com onent: Disk, Anchor Darling for Valve 3505 Work Descri tion Remarks: The Anchor Darling Disk for Valve 3505 had experience steam cuts when the valve was disassembled for routine maintenance. NCR 91-093 was generated for corrective action that resulted with the disk being replaced.
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| This like-for-like replacement was controlled by NCR 91-093
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| . and WO number 9120984. The disk was obtained from Anchor Darling under PO NQ 12229 AJD. Upon installation, a VT-2 Inservice Leak test was perfor'med and accepted as documented within WO number 9120984.
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| ASME Class: 2 ~S stem: Containment Spray GORR No: 92-T-012 Constru tion Code:
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| Work Performed B :
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| ASME 3
| |
| Section III, 1986 Edition Name of Com onent: Bonnet Bolts, for Valve 862B Work Descri tion Remarks: During a routine maintenance activity it was discovered that the bonnet bolts associated with Valve 862B require replacement. This replacement activity was controlled by TSR 90-004 and WO number 9121995. The bolts were obtained under PO NQ 11982 AJD. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO number 9121995.
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| 12
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| Re E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: (CONT ~ )
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| 12 'SME Class: 2 ~S stem: Safety Injection GORR No: 92-T-014 Construction Code: 531.1 Work Performed B : 3 Name of Com onent: Stem for MOV 826D Work Descri tion Remarks: During a routine maintenance activity it was identified that the stem associated with Valve 826D needed replacement to avoid having custom packing on the existing turned down stem. The stem replacement activity was controlled by WO number 9121994. The stem was obtained from Crane under PO NQ 12304 AJD. Upon installation, a VT-2 Xnservice Leak test was performed and accepted as documented within WO number 9121994.
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| : 13. ASME Class: 3 ~S stem: Service Water GORR No: 92-T-015 4D-SWO-125-1 4H-SWO-125-1 Construction Code: B31.1, 1986 Edition Work Performed B : 3 Name of Com onent: Nuts & Bolts flange connection between the following:
| |
| V4649 & "A" CR Chiller HX V4650 & "B" CR Chiller HX V4651 Discharge Work Descri tion Remarks: During a routine maintenance activity between it was, identified that the flange nuts Valve 4649 & "A" CR Chiller HX, Valve 4650 &
| |
| & bolts "B" CR
| |
| 'Chiller HX and Valve 4651 Discharge needed replacement due to end of service life. This replacement activity of nuts & bolts was controlled by WO numbers 9122001, 9220560 & 9220561 and TSR 91-051. The nuts & bolts were obtained under PO numbers GPN 477465/ NQ 12396 AJD & NQ 11478 FJD/ NQ 11380 AJD/ NEG 36893-83-1; and NQ 12679 AJD, NQ 12673 AJD. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO numbers 9122001, 9220560 & 9220561.
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| 13
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| t Re E. GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS. (CONT ~ )
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| : 14. ASME Class: 2 ~S stem: Main Steam GORR No: 92-T-016 Line: N/A Construction Code:
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| Work Performed B : 3 Name of Com onent: SGA-8, Hydraulic Snubber Work Descri tion Remarks: During a maintenance activity to remove SGA-8 Hydraulic Snubber to facilitate testing, the snubber was replaced with a stock Hydraulic Snubber, formally SGA-5. This "like-for-like" replacement activity was controlled by WO number 9240404. Upon installation, a VT-3 examination was performed and accepted as documented within WO number 9240404.
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| : 15. ASME Class: 3 ~S stem: Service Water GORR No: 92-T-017 v
| |
| Construction Code: B31.1, 1986 Edition Work Performed B : 3 Name of Com onent: Valve 4651 Work Descri tion Remarks: Valve 4651 was replaced due to general corrosion and end of service life after 20 years. This is an approved equivalent replacement and was controlled by WO number 9122001 & ITI MOVATS Dr g 01. The Valve was obtained by Crane under PO NQ 12608 AJD. Construction Code NDE performed included a PT examination. An ISI VT-2 examination for Leakage was performed on the required hydrostatic test for the replacement. The hydrostatic test was performed at ambient temperature at a test factor of 1.1 that produced a pressure range of 165-175 psi. The test was accepted and documented within the Work Order 9122001 &
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| SM91-183.'4
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| Re Ee GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: (CONT.)
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| : 16. ASME Class: 3 ~Sstem: Service Water GORR No: 92-E-018 Construction C'ode: B31.1, 1986 Edition Work Performed B : 3 Name of Com onent:, Stem & Plug on Valve 4652 Work Descri tion Remarks: During a maintenance activity on Valve 4652, it was discovered that the stem had pits caused by corrosion. A determination was made to replace the stem and
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| .
| |
| plug. This replacement activity was controlled by WO number 9122002 and TSR 90-197. The valve components were obtained by Crane under PO NQ 12608 AJD. Upon installation, a VT-2 Inservice Leak t'est was performed and accepted as documented within WO number,9122002.
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| : 17. ASME Class: 3 ~S stem: Service Water GORR No: 92-T-019 v
| |
| Construction Code: ASME Addenda.
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| Section III, 1977'Edition, Summer '77 Work Performed B : 3 Name of Com onent: V9627B, Disk Assembly, Arm & Pin.
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| Work Descri tion Remarks: BorgWarner Tech Alert to the NRC dated 3/28/91 identified possible casting flaws within the hinge arm that were caused by their process control. Also, the disc replacement was due to NRC N/R g 0005. This replacement activity was controlled by WO number 9122003, TSR 90-197 and MOVATS Dr g11.The replacement components were obtained from BorgWarner; Disc Assembly & Pilot Pin under PO NQ 12420 AJD and the Arm under PO NQ 10058 BJD. A Construction Code PT examination was performed and accepted. Upon installation, both a PT examination and VT-2 Inservice Leak test was performed and accepted as documented within WO number 9122003.'5
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| Re E ~ QINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Third Outage 1992 ATTACHMENT II II REPLACEMENTS AND MOD F CAT ONS I ( CONT ~ )
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| : 18. ASME Class: 3 stem: Service Water GORR No: 92-T-020 Construction Code:
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| ~S Edition e ~
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| . B31.1, 1955 Work Performed B : 3 Name of Com onent: Bonnet Stud for Valve 4603.
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| Work Descri tion Remarks: During a Maintenanc e activity, general corrosion was identified on a Bo nnet Stud.
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| Determination was made to replace the stud. This replacement activity was controlled by WO number 9240122 and TSR 91-088.
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| The stud was obtained from Energy Steel & Supply under PO NQ 12070 AJD. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO num ber 9240122.
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| : 19. ASME Class: 1 ~Sstemi Reactor Coolant System GORR No: 92-T-021 3B-RC8-2501 Construction Code: Westinghouse E-Spec G-952852 Work Performed B : 3 Name of Com onent: Stem, Disc Assembly & Cage for Valves 430
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| & 431C.
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| Work Descri tion Remarks: During a Maintenance activity, gaulling marks were observed on valves 430 & 431C.
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| Determination was made to replace the Stem, Disc Assembly &
| |
| Cage on both valves as preventative maintenance. This replacement activity was controlled by WO numbers 9122273 &
| |
| 9122280. The replacement components were obtained from Copes Vulcan under PO's NQ 11960 BJD & NQ 11168 AJD. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO numbers 9122273 & 9122280.
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| 16
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| Re Ee GZNNA NUCLEAR POWER PLANT 1990 - Znservice Znspection Report 1999 Znterval, Third Outage 1992 ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS' (CONT ~ )
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| : 20. ASME Class: 1 ~S stem: Reactor Coolant System GORR No: 92-T-023 v
| |
| Construction Code:
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| Work Performed B :
| |
| ASME 3
| |
| Section III, 1986 Edition Name of Com onent: Discs, Valve 516 Work Descri tion Remarks: During a Maintenance activity on Valve 516, indications on the valv'e discs hard facing was observed. Determination was made to replace the discs. This replacement activity was controlled by WO number 9121891 and ITI MOVATS Dr f17. The replacement discs were obtained from Anchor Darling under PO NQ 10974 BRD. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO numbers 9121891.
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| : 21. ASME Class: 1 ~S stem: Reactor Coolant System GORR No: 92-T-024 Construction Code:
| |
| Work Per ormed B :
| |
| ASME 3
| |
| Section III, 1986 Edition Name of Com onent: Disc, Valve 515 Work Descri tion Remarks: During a Maintenance activity on Valve 515, indications on the upstream valve disc hard facing was observed. Determination was made to replace the disc. This replacement activity was controlled by WO number 9121892 and ITI MOVATS Dr f18. The replacement disc was obtained from Anchor Darling under PO NQ 10974 BRD. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO numbers 9121892.
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| 17
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| Re E>> GZNNA NUCLEAR POWER PLANT 1990 - Znservice Znspection Report 1999 Zntervalg Third Outage 1992 ATTACHMENT Z Z REPLACEMENTS 2QG) MODIFICATIONS: (CONT ~ )
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| : 22. ASME Class- 2 ~S stem: Main Steam GORR No: 92-T-025 Construction Code: 931.1, 1996 Edition Work Performed B : 1 Name of Com onent: Valve 3520 Work Descri tion Remarks: Valve 3520 experienced seat leakage that was due to normal wear and had reached the end of service life. Determination was made to replace the valve. This replacement activity was controlled by WO number 9122124. The replacement valve was obtained from Henry Vogt under PO NQ 9200S BUG. A Construction Code VT examination was performed and accepted. Code Case N-416 was invoked to postpone the ISI required Hydrostatic Test. The Code Case additional requirements of a surface examination (PT), and a VT-2 Inservice Leak test was performed and accepted as documented within WO numbers 9121892.
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| : 23. ASME Class: 3 ~S stem: Stdy. Aux. Feedwater GORR No: 92-T-027 v
| |
| Construction Code: ASME Addenda.
| |
| Section III, 1977 Edition, Summer '77 Work Performed B : 3 Name of Com onent: V9708A, Arm & Pin.
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| Work Descri tion Remarks: BorgWarner Tech Alert to the NRC dated 3/28/91 identified possible casting flaws within'the hinge arm that were caused by their process control. Also, the Pin replacement was determined as being needed as a part of normal maintenance. This replacement activity was controlled by WO number 9122258, TSR 90-197 and ITI MOVATS Dr f21. The replacement components were obtained from BorgWarner; Arm under PO NQ 10058 BJD and the Pin under PO NQ 12420 AJD. A Construction Code PT examination was performed and accepted.
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| Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO number 9122258.
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| 18
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| Re Ee GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS. (CONT.)
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| : 24. ASME Class: 1 ~S stem: Pressurizer Spray GORE No: 92-T-028 v
| |
| Construction Code: 531.1, 1955 Edition Work Performed B : 3 Name of Com onent'. Plug Stem Assembly & Cage, Bonnet Nuts
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| & Studs for Valve 431A.
| |
| Work Descri tion Remarks: During a maintenance activity discovered that the Plug & Gage had linear Galling and/or it was steam cuts. A determination was made to replace the Plug Stem Assembly & Cages, as well as the Bonnet Nuts & Studs for Valve 431A. This replacement activity was controlled by WO number 9122276,.TSR 90-197 & 91-515, and ITI MOVATS Dr g22.
| |
| The replacement components were obtained from Copes Vulcan; Plug Assembly under PO NQ 10401 BJD,'onnet Studs/Nuts under PO NQ 11199 BJD. A Construction Code PT examination was performed and accepted. Upon installation, a VT-1 examination on bolting and a VT-2 Inservice Leak test was performed. Both examinations were accepted as documented within WO number 9122276.
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| : 25. ASME Class: 3 ~S stem: Standby Aux. Feedwater GORR No: 92-T-029 Construction Code:
| |
| Work Performed B :
| |
| ASME 3
| |
| Section III, Summer '73/'77 Addenda Name of Com onent: Disc & Stem Assembly, and Hinge Arm on Valve 9708B.
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| Work Descri tion Remarks: BorgWarner Tech Alert to the NRC dated 3/28/91 identified possible casting flaws within the hinge arm that were caused by their process control. Also, the disc was replaced in accordance with BorgWarner N/R g 0005 to the NRC. This replacement activity was controlled by WO number, 9122259; TSR 90-197 and ITI MOVATS Dr f23. The replacement components were obtained from .BorgWarner; Arm under PO, NQ 12420 AJD and the Disc under PO NQ 10058 BJD. A Construction Code PT examination was performed and accepted. Upon installation, a VT-2 Inservice Leak test was performed and accepted as documented within WO number 9122259.
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| 19
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| Re Ee GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODZPICATIONS ~ (CONT.)
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| : 26. ASME Class: 1 ~S stem: Reactor Coolant Syst: em GORR No: 92-T-030 Line: N/A v Construction Code: ASME Addenda.
| |
| Section III, 1983 Edition, Summer '84 Work Performed B - 1 Name of Com onent: S/G primary Manway Studs; Five on "A" S/G Cold Leg g's 13, 14, 15, 16 & 8, One on "B" S/G Cold Leg g 5.
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| Work Descri tion Remarks: During a Maintenance activity, some studs were identified containing crack like indications.
| |
| Determination was made to replace the studs containing these indications as preventative maintenance since the indications were classified as being non-critical to the functioning of the studs. This replacement activity was controlled by WO number 9220407. The replacement components were obtained from EG&G under PO NQ 12395 AJD. Construction Code examinations performed included Charpy V-notch impact t6st, UT and hardness examinations. These tests/examinations were performed and accepted. Upon installation, a VT-2 System Leak Test was performed and accepted as documented within WO number 9122259 and PT-7.
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| : 27. ASME Class: N/A ~Sstem: Main Steam GORR No: 92-E-001 Construction Code:
| |
| Work Performed B :
| |
| ASME 2
| |
| Section III, 1986 Edition Name of Com onent: MSU-'60, Mechanical Snubber Work Descri tion Remarks: Additional welds were installed to accommodate a new support attachment to the existing support.
| |
| This modification was controlled under EWR 5277, SM 5277.1, and WO number 9220352. Addition structure material was added to MSU-60 and welded. A Construction VT examination was performed and accepted as required by EWR '277. Upon modification completion, a VT-3 Snubber Program examination was performed and accepted as documented within SM 5277.1.
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| 20
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| Re Ee GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIPICATIONS: (CONT ~ )
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| : 28. ASME Class: 2 ~S stem: Steam Gen. Slowdown GORR No: 92-E-002 Line: 3" Construction Code: ASME Section III, 1986 Edition Work Performed B : 2 Name of Com onent: S/G "A" & "B" Piping.
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| Work Descri tion Remarks: EWR 4324C was generated to replace existing 2" piping with 3" piping on S/G "A" Blowdown line from the S/G through the reducer downstream of valve 5738.
| |
| Also, the existing 2" piping was replaced with 3" piping on S/G "B" Blowdown line from Penetration 322 through the reducer downstream of valve 5737. This modification was controlled under EWR 4324C, and SM 4324.17 & 4324.18. Construction Code examinations performed included VT, MT, PT, . UT & RT.
| |
| Applicable and acceptable examination results can be found within SM 4324.17 & 4324.18. ISI baseline examinations are not required but Code Case N416 was imposed to defer the required hydrostatic test. This deferral is acceptable as long as the augmented required tests are performed. These additional tests included 100% surface examinations on partial penetration welds & 1004 volumetric examinations on all full penetration welds. Also, an Inservice VT-2 Leak test was performed. All applicable tests were acceptable.
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| : 29. ASME Class: 3 ~S stem: Service Water GORR No: 92-E-006 Line: N/A Construction Code: ASME Section III, 1986 Edition Work Performed B : 1 Name of Com onent: "B" D.G. (ESW08B) Jacket Water Heat Exchanger Channel & bolting replacement.
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| Work Descri tion Remarks: NCR91-441 was generated that identified damaged and missing base material around a bolt hole of the flange connection. Determination was made to repiace the channel and bolting associated with the "B" Diesel Generator Jacket Water Heat Exchanger. This replacement was controlled under NCR91-441 and EWR 5168C. The channel was obtained from ITT Standard under Pruchase Requisition N-41883.
| |
| Upon mechanical installation of the replacement components, a VT-2 Inservice Leak test was performed and accepted as identified and documented within SM. 5168.21. (See GORR 92-E-007 & -008) 21
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| Re Ee GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspects.on Report 1999 Intervaled Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS "
| |
| (CONT ~ )
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| : 30. ASME Class: 3 ~S stem: Service Water GORR No: 92-E-007 Line: N/A v Construction Code:
| |
| Work Performed B :
| |
| ASME 2
| |
| Section III, 1986 Edition Name of Com onent: "A&B>> D.G. (ESW08 A&B) Jacket Water Heat Exchangers Channel Covers & bolting replacement.
| |
| Work Descri tion Remarks: NCR91-441 was generated that identif ied damaged and missing base material around a bolt hole of the flange connection. Determination was made to replace the channel covers and bolting associated with the "A&B" Diesel Generator Jacket Water Heat Exchangers. This replacement was controlled under EWR 5168C (Ref. GORR 92-E-006) and SM's 5168.20 & 5168.21.. The channel .covers were obtained from ITT Standard under Pruchase Requisition N-41883.
| |
| Upon mechanical installation of the replacement components, a VT-2 Inservice Leak test was performed and accepted as identified and documented within the applicable SM 5168.20/.21 package. (See GORR 92-E-006 & -008)
| |
| : 31. ASME Class: 3 ~S stem: Service Water GORR No: 92-E-008 Line: N/A Construction Code:
| |
| Work Performed B :
| |
| ASME 2
| |
| Section III, 1986 Edition Name of Com onent: "A&B" D.G. (ESW08 A&B) Jacket Water Heat Exchangers 2" piping & isolation valve replacement.
| |
| Work Descri tion Remarks: Determination was made modify the existing piping (addition of piping & isolation valves) to allow flushing of the "A&B" Diesel Generator Jacket Water Heat Exchangers. This modification was controlled under EWR 5168C and SM's 5168.20 & 5168.21. The valves were obtained from Velan under PO NQ-11903-BRD. Construction Code examinations were performed and accepted as identified and documented within the applicable SM 5168.20/21 package. An ASME Section XI hydrostatic test (1.1 test factor) and accompaning VT-2 Leak test were performed and accepted. Upon install'ation of the replacement components (See GORR 92-E-006 & -007), a VT-2 Inservice Leak test was performed and accepted as identified and documented within the applicable SM 5168.20/.21 package.
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| 22
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| Re E ~ OINNA NUCLEAR POHER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: (CONT )
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| 32 'SME Class: 3 stem: Service Water GORR No: 92 E pp9 Construction Code:
| |
| Work Performed B :
| |
| ASME 2
| |
| Section III, 1986 Edition Name of Com onent: SWU-257, Support Work Descri tion Remarks: Corrective Action was initiated on support, SWU-257 when NCR91-519 was generated. Determination was made to upgrade an existing weld within the support. This activity was controlled by NCR91-519 and SM2512.145.
| |
| Applicable Construction Code Examinations were performed and accepted as documented within SM2512.145.'A Section XI VT-3 baseline examination is not required.
| |
| 33 'SME Class: 2 ~S stem: Feedsater GORR No: 92-E-010 Construction Code: ASME Section III, 1986 Edition Work Performed B : 2 Name of Com onent: FWU-15, Mechanical Snubber Work Descri tion Remarks: Corrective Action was initiated on Mechanical Snubber FWU-15 when NCR91-599 was generated.
| |
| Determination was made to upgrade a component support weld and to replace the 1 1/8" bolts & nuts. This activity was controlled by NCR91-599 and SM2512.146. Applicable Construction Code Examinations were performed and accepted. A VT-3 baseline examination was performed and accepted.
| |
| : 34. ASME Class: 3 ~S stem: Service Water GORR No: 92-E-011 Line: 10" Construction Code: ASME Section III, 1986 Edition Wo k Performed B : 2 Na e of Com onent: SWU-108, Support Work Descri tion Remarks: Corrective Action was initiated on support SWU-108 when NCR91-475 was generated. Determination was made to replace components within this support.
| |
| Replacements included 3/4" nuts, rod washer plate and a 3/4" welded eyerod. This activity. was controlled by NCR91-475 and SM2512.145. A Section XI VT-3 baseline examination is not required.
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| 23
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| Re E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Intervaled Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIPICATZONS (CONT ~ )
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| : 35. ASME Class: 3 ~S stem: Service Water GORR Nc: 92-E-012 Line: 6>>
| |
| Construction Code: ASME Section III, 1986 Edition Work Performed B : 2 Name of Com onent: SWU-107, Support Work Descri tion Remarks: Corrective Action was initiated on support SWU-107 when NCR91-475 was generated. Determination was made to replace components within this support.
| |
| Replacements included; 5/8>> hex nuts, plate washer, steel rod, turnbuckle and a welded eyerod. This activity was controlled by NCR91-475 and SM2512.145. A Section XI VT-3 baseline examination is not required.
| |
| : 36. ASME Class: 3 ~S stem: Service Water GORR Nc: 92-E-013 Line: 4" Construction Code: ASME Section III, 1986 Edition Work Performed B : 2 Name of Com onent: SWU-223, Support Work Descri tion Remarks: Corrective Action was initiated on support SWU-223 when NCR91-475 was generated. Determination was made to upgrade an existing weld within the support. This activity was controlled by NCR91-475 and SM2512.145.
| |
| Applicable Construction Code Examinations were performed and accepted as documented within SM2512.145. A Section XI VT-3 baseline examination is not required.
| |
| : 37. ASME Class: 3 ~S stem: Service Water GORR Nc: 92-E-014 Line: 4>>
| |
| Construction Code: ASME Section III, 1986 Edition Work Performed B : 2 Name of Com onent: SWU-219, Support Work Descri tion Remarks: Corrective Action was initiated on support .SWU-219 when NCR91-475 was generated. Determination was made to upgrade an existing weld and incorporate additional plates within the support. This activity was controlled by NCR91-475 and SM2512.145. Applicable Construction Code Examinations were performed and accepted as documented within SM2512.145. A Section XI VT-3 baseline examination is not required.
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| 24
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| Ra Ea GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS (CONT ~ )
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| : 38. ASME Class: 3- ~S stem: Service Mater GORR No: 92-E-015 Line: 10" Construction Code: ASME Section III, 1986 Edition Work Performed B : 2 Name of Com onent: SWU-109, Support Work Descri tion Remarks: Corrective Action was initiated to add support SWU-109 when NCR91-475 was generated. This activity was controlled by NCR91-475 and SM2512.145.
| |
| Applicable Construction Code Examinations were performed and accepted as documented within SM2512.145. A Section XI VT-3 baseline examination is not required.
| |
| : 39. ASME Class: SS ~S stem: Reactor Coolant Sys. GORR No: 92-E-017 v
| |
| Construction Code:
| |
| Work Performed B :
| |
| ASME 2
| |
| Section III, 1986 Edition Name of Com onent: PS-9, Hydraulic Snubber Work Descri tion Remarks: PS-9 Hydraulic Snubber is a Seismic Support that needed to be lowered to avoid interference between the support pipe and closure of Valve 431A. This activity was controlled by NCR91-521, WO number 9220497, EWR 1660B and SM-1660.51. A VT Construction Code exam was performed and accepted as documented within SM-1660.51. This non-class component falls within the Snubber Program. A Snubber Program VT-3 examination was performed and acceptable as documented within the NDE Summary report number 602140.
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| 25
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| R>> E>> GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS (CONT>>)
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| : 40. ASME Class: HE ~S stem: Mainsteam GORR No: 92-E-018 v
| |
| , Construction Code: ASME Section IZZ, 1986 Edition Work Per ormed B : 2 Name of Com onent: MS-36, Support Work Descri tion Remarks: A replacement activity was initiated on support MS-36. Determination was made within EWR 5114 to remove existing items and .replace them with size 16 v.s.
| |
| hanger, 1 1/4" beam attachments, locknuts, welded eyerod pipe clamp. This activity was controlled and replacements obtained as specified within EWR 5114 and SM 5114.1. A VT-3 baseline examination was performed and accepted as documented within the NDE Summary report number 201100. PCAQ 92-018 was generated to resolve component support drawing conflicts.
| |
| : 41. ASME Class: HE ~Sstem: Mainsteam GORR No: 92-E-019 Construction Code:
| |
| Work Performed B :
| |
| ASME 2
| |
| Section III, 1986 Edition Name of Com onent: MS-39, Support Work Descri tion Remarks: A replacement activity was initiated on support MS-39. Determination was made within EWR 5114 to remove existing items and replace them with size 17 v.s.
| |
| hanger, locknut & eyerod. This activity was controlled and replacements obtained as specified within EWR 5114 and SM 5114.1. A VT-3 baseline examination was performed and accepted as documented within the NDE Summary report number 201180.
| |
| PCAQ 92-018 was generated to resolve component support drawing conflicts.
| |
| 26
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| Re E ~ OZNNA NUCLEAR POWER PLANT Inspection Report 1990 - Znservice 1999 Interval, Third Outage 1992 ATTACHMENT II REPI9ACEMENTS AND MODIFICATIONS: 'CONT ~ )
| |
| : 42. ASME Class: HE ~S stem: Mainsteam GORR No: 92-E-020 Construction Code:
| |
| Work Performed B :
| |
| ASME 2
| |
| Section III, 1986 Edition Name of Com onent: MS-42, Support Work Descri tion Remarks: A replacement activity was initiated on support MS-42. Determination was'ade within EWR 5114 to remove existing items and replace them with size 15 v.s.
| |
| hanger, locknut & welded eyenut. This activity was controlled and replacements obtained as specified within EWR 5114 and SM 5114.1. A VT-3 baseline examination was performed and accepted as documented within the NDE Summary report number 201300.
| |
| PCAQ 92-018 was generated to resolve component support drawing conflicts.
| |
| : 43. ASME Class: HE ~Sstem: Mainsteam GORR No: 92-E-021 Construction Code:
| |
| Work Performed B :
| |
| ASME 2
| |
| Section III, 1986 Edition Name of Com onent: MS-44, Support Work Descri tion Remarks: A replacement activity was initiated on support MS-44. Determination was made within EWR 5114 to remove existing items and,replace them with size,16 v.s.
| |
| hanger, locknut, eyerod & pipe clamp. This activity was controlled and replacements obtained as specified within EWR 5114 and SM 5114.1. A VT-3 baseline examination was performed and accepted as documented within the NDE Summary report number 201380. PCAQ 92-018 was generated to resolve component support drawing conflicts.
| |
| 27
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| Re Ee GINNA NUCLEAR POWER PLANT 1990 -Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS. (CONT ~ )
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| : 44. ASME Class: HE ~S stem: Mainsteam GORR No: 92-E-022 Construction Code! ASME Section XXZ, 1986 Edition Work Performed B : .2 Name of Com onent: MS-47, Support Work Descri tion Remarks: A replacement activity was initiated on support MS-47. Determination was made within EWR 5114 to remove identified'existing items, drill 1 3/4" hole in item g9 and install a new welded beam attachment, welded eyerod, turnbuckle, locknut and machine rod. Welding was performed to attach some of the components.'his activity was controlled and replacements obtained as specified within EWR 5114 and SM 5114.1. Applicable Construction Code Examinations were performed and accepted as documented within the SM. A VT-3 baseline examination was performed and accepted as documented within the NDE Summary report number 201050. PCAQ 92-018 was
| |
| , generated to resolve component support drawing conflicts.
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| : 45. ASME Class: HE ~S stem: Mainsteam , GORR No: 92-E-023 Construction Code:
| |
| Work Performed B :
| |
| ASME 2
| |
| Section III, 1986 Edition Name of Com onent: MS-59, Support Work Descri tion Remarks: A replacement activity was initiated on support MS-59. Determination was made within EWR 5114 to remove identified existing items and install new bolt, turnbuckle and locknuts. This activity was controlled welded'yerods, and replacements obtained as specified within EWR 5114 and SM 5114,.1. A VT-3 baseline examination was performed and accepted as documented within the NDE Summary report number 201060.
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| PCAQ 92-018 was generated to resolve component support drawing conflicts.
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| 28
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| Re Ee GINNA NUCLEAR POWER PLANT 199O - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIPICATIONS'CONT ~ )
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| ~S stem: Feedwater GORR No: 92-E-024 v
| |
| Construction Code: ASME Section ZZI, 1986 Edition Work Performed B : 2 Name of Com onent: FW-43, Support Work Descri tion Remarks: A replacement activity was initiated on support MS-43. Determination was made within EWR 5114 to remove identified existing items and install a 1 1/2" B & P, and bolt & nut. This activity was controlled and replacements obtained as specified within EWR 5114 and SM 5114.1. A VT-3 baseline examination was performed and accepted as. documented within the NDE Summary report number 202220. PCAQ 92-018 was generated to resolve component support drawing conflicts.
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| : 47. ASME Class: 2 ~S stem: CVCS GORR No: 92-E-026 Line: 2H-CH-601 Construction Code: ASME Section III, NF Work Performed B : 1 Name of Com onent: CVU-351, Mechanical Snubber Work Descri tion Remarks: CVU-351, a Mechanical Snubber, was damaged during removal prior to functional testing.
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| "
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| Determination was made to replace the damaged snubber with a "like-for-like" PSA-1/2 snubber. This activity was controlled by NCR92-145, and WO number 9240434. Upon installation, a VT-3 Snubber Program examination was performed and accepted as documented within the work order.
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| 29
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| Rs E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPIACEMENTS AND MODIFICATIONS: (CONTe)
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| : 48. ASME Class: 3 ~S stem: CVCS GORR No: 92-E-027 Line: 2A-CH4-151 Construction Code:
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| Work Performed B :
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| ASME 1
| |
| Section III, NF Name of Com onent: CVU-372, Mechanical Snubber Work Descri tion Remarks: CVU-372, a Mechanical Snubber, was not inoperable by vendor standards but the as found breakaway drag force exceeded piping allowable. Determination was made to replace the snubber with a "like-for-like" PSA-1/2 snubber.
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| The piping was evaluated for adverse impact due to excessive drag no =adverse impact was found. This activity was controlled by NCR92-225, and WO number 9241154. Upon installation, a Snubber Program VT-3 examination was performed and accepted.
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| : 49. ASME Class: 2 ~S stem: Main Steam GORR No: 92-E-028 Construction Code:
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| Work Performed B :
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| ASME Section III, NF 1
| |
| Name of Com onent: MSU-26, Mechanical Snubber Work Descri tion Remarks: MSU-26, the bottom Mechanical Snubber, failed Functional Testing and was due to water buildup in the component. Vendor recommendation of drilling a drain hole at the underside of the snubber protective boot was taken. Determination was made to replace the snubber with a "like-for-like" PSA-35 snubber. This activity was controlled by NCR92-270, and WO number 9220842. Upon installation, a VT-3 Snubber Program examination was performed and accepted.
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| 30
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| 0 Re Ee GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999'-Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS (CONT ~ )
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| : 50. ASME Class: NC-SS Snubber ~S stem: Main Steam GORR No: 92-E-029
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| , Construction Code: ASME Section IZZ, NF Work Performed B : 1 Name of Com onent: MSU-57, Mechanical Snubber Work Descri tion Remarks: MSU-57, a Mechanical Snubber, failed Functional Testing and was apparently due to vibration over an extended period of time. Determination was made to replace the snubber with a "l'ike-for-like" PSA-3 snubber. Engineering is considering alternatives to the mechanical snubber at this location. This activity was controlled by NCR92-257, and WO number 9241168. Upon installation, a Snubber Program VT-3 examination was performed and accepted.
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| : 51. ASME Class: NC-SS Snubber ~Sstem: Main Steam GORR No: 92-E-030 Construction Code:
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| Work Performed B :
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| ASME 1
| |
| Section III, NF Name of Com onent: MSU-60, Mechanical Snubber Work Descri tion Remarks: MSU-60, a Mechanical Snubber, failed Functional Testing and was apparently due to vibration over an extended period of time. Determination was made to replace the snubber with a "like-for-like" PSA-3 snubber. Engineering is considering alternatives to the mechanical snubber at this location. This activity was controlled by NCR92-266, and WO number 9241169. Upon installation, a Snubber Program VT-3 examination was performed and accepted.
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| 31
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| Re E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: *
| |
| (CONT ~ )
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| : 52. ASME Class: 3 ~S stem: Main Steam GORR No: 92-E-031 v
| |
| Construction Code: ASME Section III, NF Work Performed B : 1 Name of Com onent: MSU-74, Mechanical Snubber Work Descri tion Remarks: MSU-74, a Mechanical Snubber, failed Functional Testing and was apparently due to vibration over an extended period of time. Determination was made to replace the snubber with a "like-for-like" PSA-10 snubber. Engineering is considering alternatives to the mechanical snubber at this location. This activity was controlled by NCR92-211, and WO number 9240436. Upon installation, a Snubber Program VT-3 examination was performed and accepted.
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| : 53. ASME Class: 3 ~S stem: Main Steam GORR No: 92-E-032 Y
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| Construction Code: ASME Section ZZZ, NF Work Performed B : 1 Name of Com onent: MSU-84, Mechanical Snubber Work Descri tion Remarks: MSU-84, the East Mechanical Snubber, failed Functional Testing and was apparently due to vibration over an .extended period of time. Determination was made to replace the snubber with a "like-for-like" PSA-3 snubber.
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| Engineering is considering alternatives to the mechanical snubber at this location. This activity was controlled by NCR92-259, and WO number 9241175. Upon installation, a VT-3 examination was performed and accepted.
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| 54 ~ ASME Class: 3 ~S stem: Main Steam GORR No: 92-E-033 Construction Code: ASME Section ZZZ, NF Work Performed B : 1 Name of Com onent: MSU-84, Mechanical Snubber Work Descri tion Remarks: MSU-84, the West'Mechanical Snubber, failed Functional Testing and was apparently due to vibration over an extended period of time. Determination,was made to replace .the snubber with a "like-for-like" PSA-3 snubber.
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| Engineering is 'considering alternatives to the mechanical snubber at this location. This activity was controlled by NCR92-258, and WO number 9241176. Upon installation, a VT-3 examination was performed and accepted.
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| 32
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| Re Ee GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: (CONT ~ )
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| Class: No: 92-E-034
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| : 55. ASME
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| /'" Code:
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| Construction 2 ~S ASME
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| ' Section stem:. Service Water '
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| III, 1986 GORR Edition
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| '
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| y Work Performed B : 2 Name of Com onent: Containment Recirculating Fan Motor Cooler Coils, EIN's(,ACA07, ACA08, ACA09 & ACA10.
| |
| Work Descri tion Remarks: A replacement activity was initiated due to leaking within the old coils as a result of 20+ years of service. The motor cooling coils were obtained from Marlo Coil= under PO NQ 12279-AJD. This replacement activity was controlled by EWR 5393 and SM's 5393.1,, 5393.2 and 5393.3.
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| Construction Code Examinations were performed and accepted as documented within the applicable SM's. ISI baseline examinations are not required. Code Case N416 was imposed to defer the required hydrostat'ic test. This deferral is acceptable as long as the augmented required tests are performed. These additional tests included 1004 surface examinations on partial penetration welds. These examinations were performed by Projects and accepted as documented within the applicable SM. An Inservice VT-2 Leak test was performed and accepted.
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| 33
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| Re E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II r
| |
| REPLACEMENTS AND MODIFICATIONS: (CONT ~ )
| |
| : 56. ASME Class: 2 stem: Service Water GORR No: 92-E-035
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| /'" ~S Construction Code: 531.1 & ASME Section ZIZ, 1986 Edition Work Performed B : 1 Name of Com onent: Service Water Discharge Piping from Containment Recirculation Fan Motor Cooler Coil "A" Work Descri tion Remarks: A leak was discovered with the flexible hose assembly at the discharge side of the Containment Recirculation Fan Motor Cooler Coil "Ane The leak was caused by galvanic corrosion at the bimetallic weld area.
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| NCR92-240 was generated for disposition.,Determination was made to replace associated piping and flexible hose. The replacement activity was controlled by NCR92-240, WO number 9220823 and EWR 5393. The flexible hose was obtained from Flexonices under PO NPSC 13830. Construction Code examinations performed included visual and surface examinations. These examinations were acceptable and documented within WO number 9220823. Code Case N416 was imposed to defer the required ASME Section XI hydrostatic test. This deferral is acceptable as long as the augmented required tests are performed. These additional tests include surface examinations on the partial penetration welds and a VT-2 Inservice Leak test. These tests were performed and acceptable.
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| 34
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| R. E. IIINA IIUC LEAR POMER PLAtlT
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| ":
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| G Inservi ce Inspection Report 1990 - 1999 Interval, Third Outage 1992 ATTACllHEIIT I I REPLACEMENTS AND MODIFICATIONS: (CONT. )
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| : 57. ASME Class: 2 ~Sstem: Comp. Cooling Water GIIRR No: 92-T-031 I *
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| * Construction Code: ANSI B16.34-1981 & ASME Section XI,1986 Ed.
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| Work Performed B : 1 Name of Com onent: CCW Inlet Check Vlv to Excess Letdown Hx Work Descri tion Remarks: Check valve 743 is the containment, isolation valve for the subject line. It has had repeated problems passing the seat leakage requirements under Appendix J. Consequently, NCR 90-450 changed the disc seat, from a hard seat to a soft seat.
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| The replacement activity was controlled by NCR 90-450 and WO number 9122570.The new disc was obtained from the original mfg, Rockwell Edwards, under P.O. NQ-12879-AJD. An ASME section XI VT-2 Inservice Leakage Test and a local leak rate test were performed and found acceptable.
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| 35
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| Ro E. OINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT III EROSION/CORROSION tMINWALL) PROGRAM
| |
| | |
| ==SUMMARY==
| |
| | |
| This section provides details and information corresponding to components with associated examination results on 161 items that were inspected during the 1992 Ginna Outage.
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| The following lists and tables shall- identify Drawings and Systems of examined components, System 'component result summaries by drawing, and individual component result details by drawing.
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| SYSTEMS OP EXAMINED COMPONENTS~
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| DWG ~
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| NO. SYSTEM M-3 HEATER 4A/B DRAIN TO HEATER DRAIN TANK.
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| M-7B CONDENSATE PUMP & HEATER DRAIN TANK DISCHARGE TO FEEDWATER SUCTION.
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| M-12B MSR 2AI2B 2ND PASS DRAIN TO 5B H P H &: CONDENSER M-15A MSR 1A 4TH PASS TO 5A HEATER.
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| M-16 MSR 1A & 1B 4TH PASS TO CONDENSER.
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| M-18 MSR 2A & 2B 4TH PASS TO CONDENSER.
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| M-21 STEAM EXTRACTION TO PRESEPARATOR B & 4B L.P.H.
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| M-22 STEAM EXTRACTION TO PRESEPARATOR A & 4A L.P.H.
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| M-3l MSR 1A & 1B TO HEATER DRAIN TANK.
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| M-32 MSR 2A & 2B TO HEATER DRQIN TANK.
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| M-33 MSR 1AJ 1Bg 2A & 2B TO HEATER DRAIN TANKS M-41A 5A H.P.H.DRAIN TO 4A L.P.H.
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| M-45 PRESEPARATOR A/B TO HEATER DRAIN TANK C CONDENSER.
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| M-46A PRESEPARATOR A/B TO HEATER DRAIN TANK & CONDENSER.
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| M-46B PRESEPARATOR A/B TO HEATER DRAIN TANK.
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| M-75 STEAM EXTRACTION TO 5A & 5B H.P.H.
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| M-82 FEEDWATER DISCHARGE; INTERMEDIATE BUILDING.
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| M-83 FEEDWATER DISCHARGE; INTERMEDIATE & FACADE.
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| M-88D S/G BLOWDOWN TO FLASH TANK (TURBINE BLDG. ).
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| M-88E S/G BLOWDOWN (INTERMEDIATE BLDG. ).
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| M-89A S/G 1A BLOWDOWN (CONTAINMENT BLDG. ).
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| M-89B S/G 1B BLOWDOWN (CONTAINMENT BLDG. ).
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| M-89C S/G 1A BLOWDOWN (CONTAINMENT BLDG. ) TO PEN. 322.
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| M-92 MAIN FEEDWATER PUMP BYPASS.
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| M-93 FEEDWATER HEADER BYPASS.
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| M-94 S/G BLOWDOWN TO CONDENSER.
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| M-96 REHEATER EXCESS STEAM TO CROSS UNDER.
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| M-97 STEAM EXTRACTION FROM BLOWDOWN TANK TO 3A L.P. HEATER.
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| M-98 S/G BLOWDOWN TANK TO CONDENSER.
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| E ~ GINNA NUCLEAR POWER PLANT 199O - Znservice Inspection Report 1999 Interval, Third Outage 1992 ATT CHMENT IIZ COMPONENT RESULTS BY SYSTEM
| |
| | |
| ==SUMMARY==
| |
| 'WG NOi SYSTEM M-3 HEATER 4A/B DRAIN TO HEATER DRAIN TANK+
| |
| Components Examined: Results: 4 of Nominal 2 Pipes 2 >884 M-7B CONDENSATE PUMP & HEATER DRAIN TANK DISCHARGE TO FEEDWATER SUCTION Components Examined: Results: 4 of Nominal 1 Reducer 1 70-65%
| |
| M-12B MSR 2Ag 2B 2ND PASS DRAIN TO 5B H P Ho & CONDENSERo Components Examined: Results: 4 of Nominal 1 Elbow 1 88-824 1 Pipe 1 <654 M-15A MSR 1A 4TH PASS TO 5A HEATER.
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| Components Examined: Results: > of Nominal 1 Pipe 2 >884 3 Reducers 2 88-824 M-16 MSR 1A & 1B 4TH PASS TO CONDENSER.
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| Components Examined: Results: 4 of Nominal 2 Elbows 5 >88%'
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| Pipes 2 88-824 1 Reducer' Tees M-18 MSR 2A & 2B 4TH PASS TO CONDENSER Components Examined: Results: 4 of Nominal 1 Elbow 2 >884 1 Pipe
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| i J'a
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| E ~ GINNA NUCLEAR POWER PLANT 199O - Inservice Inspection Report 1999 Interval, Thi.rd Outage 1992 ATTACHMENT II I COMPONENT RESULTS BY SYSTEM
| |
| | |
| ==SUMMARY==
| |
| Cont.
| |
| DNG NOi SYSTEM M-21 STEAM EXTRACTION TO PRESEPARATOR B & 4B L P,H.
| |
| Components Examined: Results: 4 of Nominal 6 Elbows 4 >88%
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| 5 Pipes 3 82-764 1 Tee 1 76-704 4
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| <654'-22 STEAM EXTRACTION TO PRESEPARATOR A & 4A Le Pe Ho Components Examined: Results: 4 of Nominal 1 Elbow 2 >88%
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| 3 Pipes 3 82-764' Tee M-3 1 MSR 1A & 1B TO HEATER DRAIN TANK Components Examined: Results: 4 of Nominal 2 Elbows 7 >884
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| '
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| 1 Pipe 1 <654 Reducers 2 Tees M-32 MSR 2A & 2B TO HEATER DRAIN TANK.
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| Components Examined: Results: 4 of Nominal 1 Elbow 6 >884 2 Pipes 1 <65%
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| 3 Reducers 1 Tee M 33 MSR 1Aq 1Bi 2A & 2B TO HEATER DRAIN TANK+
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| Components Examined: Results: 4 of Nominal 1 Header 1 >88%
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| R>> E ~ GINNA NUCLEAR POWER PLANT 199O - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT I II COMPONENT RESULTS BY SYSTEM
| |
| | |
| ==SUMMARY==
| |
| Cont.
| |
| DWG>>
| |
| NO SYSTEM M-41A 5A H>>P H>> DRAIN TO 4A LE P H ~
| |
| Components Examined: Results: % of Nominal 1 Pipe 3 >88%
| |
| 2 Tees M-45 PRESEPARATOR A/B TO HEATER DRAIN TANK & CONDENSER>>
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| Components Examined: Results: % of Nominal 2 Elbows 1 >88%
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| 1 82-76%
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| M-46A PRESEPARATOR A/B TO HEATER DRAIN TANK & CONDENSER>>
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| Components Examined: Results: % of" Nominal 1 Pipe 2 >88%
| |
| 1 Reducer M-46B PRESEPARATOR A/B TO HEATER DRAIN TANK.
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| Components Examined: Results: % of Nominal 3 Elbows 9 >88%
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| 6 Pipes 3 88-82%
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| 2 Reducers 1 Tee M-75 STEAM, EXTRACTION TO SA & 5B H.P,,H, Components Examined: Results: % of Nominal 2 Pipes 5 >88% >>
| |
| 2 Reducers 1 Tee M-82 FEEDWATER DISCHARGEg INTERMEDIATE BLDG>>
| |
| Components Examined: Results: % of Nominal 1 Pipe 1 >88%
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| 4
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT III COMPONENT RESULTS BY SYSTEM
| |
| | |
| ==SUMMARY==
| |
| Cont.
| |
| DWG NO ~ SYSTEM M-83 FEEDWATER DISCHARGE~ INTERMEDIATE & FACADES Components Examined: Results: 4 of Nominal 1 Pipe 1 >884 M-88D S/G BLOWDOWN TO FLASH TANK (TURBINE BLDG ) ~
| |
| Components Examined: Results: 4 of Nominal 3 Pipes 1 >884 1 Reducer 1 88-824 1 82-764 1 <654 M-88E S/G BLOWDOWN '(INTERMEDIATE BLDG' ~
| |
| Components Examined: Results: 4 of Nominal 14 Elbows 31 Baseline 16 Pipes 1 Reducer M-89A S/G lA BLOWDOWN (CONTAINMENT BLDG' ~
| |
| Components Examined: Results: 4 of Nominal 3 Elbows 6 >88%
| |
| 3 Pipes M-89B S/G 1B BLOWDOWN (CONTAINMENT BLDG' ~
| |
| Components Examined: Results: 4 of Nominal 1 Pipe 2 >884 1 Tee M-89C S/G 1A BLOWDOWN (CONTAINMENT BLDG' TO PEN+ 322 '
| |
| Components Examined: Results: 4 of Nominal 6 Elbows 14 >88%
| |
| 7 Pipes 1 Tee
| |
| | |
| R>> E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspects.an RepaM 1999 Interva1, Thiz'6 Outage 1992 ATTACHMENT III COMPONENT RESULTS BY SYSTEM
| |
| | |
| ==SUMMARY==
| |
| Cont.
| |
| DWG.
| |
| NO>> SYSTEM M-92 MAIN FEEDWATER PUMP Examined: BYPASS'omponents Results: 0 of Nominal 1 Elbow 3 >884 1 Pipe 1 Reducer M-93 FEEDWATER HEADER Examined:
| |
| BYPASS'omponents Results: 4 of Nominal 1 Elbow 3 >884 2 Pipes 1 82-76%
| |
| 1 Reducer M-94 S/G BLOWDOWN TO CONDENSER.
| |
| Components Examined: Results: 4 of Nominal 3 Pipes 1 >884 1 Reducer 3 88-82%'-96 REHEATER EXCESS STEAM TO CROSS UNDER>>
| |
| Components Examined: Results: 4 of Nominal 2 Elbows 7 >884 4 Pipes 1 Tee M-,97 STEAM EXTRACTION FROM BLOWDOWN TANK TO 3A L.PE HEATER.
| |
| Components Examined: Results: 4 of Nominal 1 Elbow 2 >884 1 Pipe M-98 S/G BLOWDOWN TANK TO CONDENSER.
| |
| Components Examined: Results: 4 of Nominal 2 Elbows 5 >884 2 Pipes 1 82-764 2 Reducers 1 70-654 1 Tee
| |
| | |
| R. E. GINNA NUCLEAR POWER PLANT 199O - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT III The following list will provide component result details, by drawing number, for all items examined during the 1992 Outage.
| |
| Com onent Result Details:
| |
| Drawin No. M-3 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall '2 Allowable Readin Nominal T 202101 10A P 0.844 0.225 0.862 >88 UT 202181 18A P 0.844 0.435 0.882 >88 UT
| |
| '(Note: "P" = Pipe)
| |
| Drawin No. M-7B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 208380 38 R '.365 0.406 0.180 0.246 70-65 UT (Note: "R" = Reducer)
| |
| Drawin No. M-12B
| |
| ~
| |
| Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 222890 87 E 0.432 0.200 '.229 <65 UT 222900 88 P 0.432 0.200 0.335 88-82 UT (Note: "E" = Elbow, "P" = Pipe)
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| | |
| t' R E ~ QINNA NUCLEAR POWER PLANT 199O - Inservi.ce Inspecti.on Report 1999 Interval, Thi.rd Outage 1992 ATTACHMENT I II Com onent Result Details Cont.
| |
| Drawin No. M-1SA Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 226355 35A R 0.300 0.179 .190/.125 0.218 88-82 UT 226365 36A R 0.179 0.218 .160/.180 0.196 >88 RT 226366 36B R 0.218 0.337 .155/.220 0.243 88-82 UT 226370 37 0.337 0.205 0 '18 >88 , UT (Note: "R" = Reducer, "P" = Pipe)
| |
| Drawin No. M-16 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 228290 29 T 0.594 0.337 .280/.180 0.302 88-82 UT 228310 31 E 0.300 0.210 0.280 >88 UT 228312 31A P 0.300 0.245 0.274 >88 UT 228455 45A R 0.300 0.179 .230/.150 0.202 >88 UT 228480 48 E 0.337 0.245 0.310 >88 228490 49 P 0.337 0,.240 0.323 >88 UT 228560 56 T 0.337 0.594 .255/.430 0.313 88-82 UT (Note: "R" = Reducer, "P" = Pipe, "T" = Tee, "E" = Elbow)
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| | |
| E ~ GINNA NUCLEAR POWER PLANT 199O - Inservice Inspection Report 1999 Intervalg Third Outage 1992 ATTACHMENT III Com onent Result Details Cont.
| |
| Drawin No. M-18 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 232580 58 E 0 ~ 594 0.420 0 '37 >88 232590 59 P 0 '94 0 '20 0.537 >88 UT (Note'EII Elbow~ Ilpll pipe)
| |
| Drawin No. M-21 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 301130 12 E 0.844 0. 200 0.859 >88 'T 301230 21 E 0 '44 0. 200 1.295 >88 UT 301260 24 E 0.375 0.200 0.230 <65 UT 301270 25 ~ P 0 '75 0.200 0.346 >88 UT 301280 26 E 0 '75 0.200 0.301 82-76 UT 301290 27 0 '75 0.200 0.170 <65 UT 301300 28 0.375 0.200 0.231 <65 UT 301310 29 0. 375 0.200 0.238 <65 UT 301350 33 0.500 0.200 0.386 82-76 UT 301360 34 P 0.375 0.200 0.287 82-76 UT 301370 35 E 0.375 0.240 0.268 76-70 UT 301380 36 P 0.375 0.200 0.368 >88 UT (Note Ilpll pipe I IITll Tee l II EII Elbow)
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| R E. GINNA NUCLEAR POWER PLANT 199o - Inservice Inspection Report 1999 Interval@ Third Outage 1992 ATTACHMENT I II Com onent Result Details Cont.
| |
| Drawin No. M-22 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T
| |
| ~
| |
| 302010 28 P 0.375 0.200 0.302 82-76 UT 302020 29 0.375 0.200 0.339 >88 UT 302030 30 E 0.375 0.205 0.291 82-76 UT 302070 33 0. 465 0.200 ,0.447 >88 UT 302080 34 0.375 0.200 0.290 . 82-76 UT (Note: <<P<< = Pipe, <<T<< = Tee, <<E<< = Elbow)
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| Drawin No. M-31 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 260020 2 T 0.432 0.305 0.460 >88 UT 260040 4 E 0.432 0.315 0.423 >88 UT 260050 5 , P 0.432 0.310 0.397 >88 UT 260157 15B R 0.432 0.300 .330/.235 0.317 >88 UT 260158 15C R 0.300 0.594 .230/.435 0.342 <65 UT 260180 18 E 0.594 0.425 '0.569 >88 260190 19 T 0.594 1.031 .425/.730 0.586 '88 260325 32A R 0.300 0.594 .230/.435 0.535 >88 UT (Note: <<R<< = Reducer, <<p<< pipe ~
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| <<T<<Tee ~
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| <<E<< Elbow) 10
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| Ro E. GZNNA NUCLEAR POWER PLANT 1990 - Znservice Znspection Report 1999 Znterval, Third Outage 1992 ATTACHMENT Z Z Z Com onent Result Details Cont.
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| Drawin No. M-32 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number lD T e Wall 1 Wall 2 Allowable Readin Nominal T 261040 4 0.432 0.310 0.463 >88 UT 261050 5 E 0.432 0.315 0.429 >88 261060 6 0.432 0.310 0.394 >88 261185 18B R 0.432 0.300 .330/.235 0.304 >88 261195 19A R '0.300 0.594 .226/.431 0.351 <65 261250 25 0.432 0.310 0.388 >88 UT 261445 44A R 0.300 0.594 .226/.431 0.331 >88 UT (Note: "R" = Reducer, "P" = Pipe, "T" = Tee, "E" = Elbow)
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| Drawin No. M-33 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number XD T e Wall 1 Wall 2 Allowable Readin Nominal T 262440 44 H 0.844 0.590 0.923 >88 UT (Note: "H" = Header)
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| Ro Eo GINNA NUCLEAR POWER PLANT 199O - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT II I Com onent Result Details Cont.
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| Drawin No. M-41A Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 290360 36 T 0.594 0.200 0.647 >88 UT 290370 37 P 0.594 0.200 0.592 >88 UT 290391 40 T 0.844 0.594 0.280 0.600 >88 UT (Note: 'rPn = Pipe, rrTrr Tee Drawin No. M-45 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 298020 2 E 0.375 0. 175 0.365 >88 UT 298660 66 E 0.432 0.200 0. 337 82-76 UT (Note: "E" = Elbow)
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| Drawin No. M-46A
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| ,Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 329085 38A R 0.300 0.432 .240/.325 0.310 >88 UT 329090 39 P 0.432 0.200 0.423 >88 UT (Note: "P" = Pipe, "R" = Reducer) 12
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| IC Ro E. GINNA NUCLEAR POWER PLANT 199O - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT III Com onent Result Details Cont.
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| Drawin No. M-46B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 328115 11A R 0.432 0.337 .380/.295 0.321 >88 UT 328125 12A R 0.337 0.432 .250/.320 0.350 >88 328160 16 T 0.432 0.200 0.435 >88 UT 328240 24 P 0.432 0.200 0.425 '88 328250 25 E 0.432 0.200 0.415 >88 UT 328260 26 0.432 0 ~ 200 0.423 >88 ,, UT 328270 27 0.432 0. 200 0.373 88-82 UT 328280 28 0.432 0. 200 0.404 >88 UT 328290 29 0.432 0.200 0.375 88-82 UT 328300 30 0.432 0.200 0.396 >88 UT 328301 30A P 0.844 0.200 0.714 88-82 UT 328841 '4 P 0.844 0.200 0.745 >88 UT (Note: "R" = Reducer, "P" = Pipe, "T" = Tee, "E" = Elbow)
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| Drawin No. M-75 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 303010 1 P 0. 375 0.200 0.333 >88 UT 303015 1A R 0.365 0.375 0.192 0.366 >88 13
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| R E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT III Com onent Result Details Cont.
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| Drawin No. M-75 Cont.
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| Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 303160 16 0.375 0.200 0.346 >88 UT 303165 16A R 0 '65 0.375 0.200 0.357 >88 303300 30 T 0.375 0.200 0.473 >88 (Note: "R" = Reducer, "P" = Pipe, "T" = Tee)
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| Drawin No. M-82 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 392040 4 P 0.938 0.715 0.978 >88 UT (Note: "P" = Pipe)
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| Drawin No. M-83 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Numbe ID T e Wall 1 Wall 2 Allowable Readin Nominal T 392530 3 P 0.938 0.600 0.950 >88 UT (Note: "P" = Pipe)
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| Ri E ~ GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990 1999 Interval, Third Outage 1992 ATTACHMENT III Com onent Result Details Cont.
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| Drawin No. M-88D Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 385381 38A R 0.300 0.337 0.150 0.336 >88 UT 385390 39 P 0.337 0.150 0.287 88-82 UT 385392 39B P 0.337 0. 170 0.178 <65 UT 385757 75B P 0.337 0. 170 0.274 82-76 UT (Note: "R" = Reducer/ "P" = Pipe)
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| Drawin No. M-88E Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 386010 01 E 0. 300 BASELINE 0.257 88-82 UT 386030 03 0. 300 BASELINE 0.287 >88 UT 386040 04 0.300 BASELINE 0.274 >88 UT 386050 05 0.300 BASELINE 0.284 >88 386070 07 0.300 BASELINE 0.291 >88 386080 08 E 0.300 BASELINE 0.301 >88 UT 386090 09 0.300 BASELINE 0.288 >88 UT 386100 10 E 0.300 BASELINE 0.300 >88 UT 386110 11 0.300 BASELINE 0.292 >88 UT 386120 12 E 0.300 BASELINE 0.292 >88 UT 15
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| R, E, OZNNA NUCLEAR POWER PLANT Inspection Report l99O - Inservlce 1999 Interval, Third Outage 1992 ATTACHMENT III Com onent Result Details Cont.
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| Drain No. M-88E Cont.
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| Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 386130 13 0.300 BASELINE 0.294 >88 386140 14 0.300 BASELINE 0.285 >88 UT 386150 15 0.300 BASELINE '.273 >88 386160 16 0.300 BASELINE 0.288 >88 UT 386170 17 0.300 BASELINE 0.282 >88 UT 386180 18 0.300 BASELINE 0.288 >88 386270 27 0.218 BASELINE 0.208 >88 UT 386280 28 0.218 BASELINE 0.186 88-82 UT 386290 29 0.218 0.300 BASELINE 0.229 >88 UT 386300 30 0. 300 BASELINE 0.276 >88 UT 386320 32 0. 300 BASELINE 0.283 >88 UT 386330 33 0.300 BASELINE 0.301 >88 UT 386370 37 0.300 BASELINE 0.286 >88 UT 386380 38 0.300 BASELINE 0.299 >88 'T 386390 39 0.300 BASELINE 0.275 >88 UT 386400 40 0.300 BASELINE 0.295 >88 386410 41 0.300 BASELINE 0.266'88 UT 386420 42 0.300 BASELINE 0.308 >88 16
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| R. E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Repart 1999 Interval, Third Outage 1992 ATTACHMENT III Com onent Result Details Cont.
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| Drawin No. M-888 Cont.
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| Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 386430 43 0.300 BASELINE 0.286 >88 UT 386440 44 E 0.300 BASELINE 0.280 >88 UT 386450 45 P 0. 300 BASELINE 0.295 >88 UT (Note: "R" = Reducer, "P" = Pipe, "E" = Elbow)
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| Drawin No. '-89A Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 387010 1 0. 218 0. 125 0.210 >88 UT 387020 2 0. 218 0. 150 0.286 >88 UT 387030 3 0. 218 0. 125 0.210 >88 UT 387040 4 0. 218 0. 150 0.311 >88 UT 387050 5 0. 218 0. 125 0 '05 >88 387060 6 E 0.218 0.150 0.324 >88 (Note: "P" = Pipe, "E" = Elbow) 17
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| Ro Ee GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT III Com onent Result Details Cont.
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| Drawin No. M-89B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 388090 9 T 0. 218 0. 218 0. 230 >88 UT 388110 11 P 0. 218 0.210 0.220 >88 (Note: uP'i Pipe I "T" Tee)
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| Drawin . No. M-89C Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 388260 26 0. 218 0. 165 0.315 >88 388330 33 P 0. 218 0.165 0.209 >88 UT 388360 36 E 0. 218 0.125 0.340 '88 UT 388370 37 P 0.218 0.125 0.340 >88 UT 388380 38 E 0.218 0. 125 0.200 >88 388390 39 0.218 0. 135 0.210 >88 388400 40 E 0.218 0. 200 0.288 >88 388410 41 0.218 0. 125 0.196 >88 388420 42 0.218 0. 175 0.220 >88 UT 388430 43. 0.218 0 ~ 125 0.209 >88 UT 388440 44 E 0.218 0. 125 0.205 >88 388450 45 0.218 0. 130 0.225 >88 UT 18
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| R. B ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT III Com onent Result Details Cont.
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| Drawin No. M-89C Cont.
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| Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 388460 46 E 0.218 0.125 0.210 >88 UT 388470 47 P 0.218 0.125 0.215 >88 UT (Note: "P" = Pipe, "T" = Tee, "E" = Elbow)
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| Drawin No. M-92 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Numb r ID T e Wall 1 Wall 2 Allowable Readin Nominal T 281060 6 E 0.594 0.337 0.470 0.552 >88 UT 281110 11 P 0.237 0.100 0.332 >88 UT 281130 13 R 0.337 0.322 0.285 0.361 >88 UT (Note: "R" = Reducer, "P" = Pipe, "E" = Elbow)
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| Drawin No. M<<93 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 4
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| 394000 1 0. 375 0.270 0.343 >88 UT 394010 2 0.375 0. 270 0.324 88-82 UT 394040 5 0.375 0.337 0.240 0.366 >88 UT 394080 9 0.337 0. 200 0.301 >88 UT (Note: "R" = Reducer, "P" = Pipe, "E" = Elbow) 19
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| R. E ~ GZNNA NUCLEAR POWER PLANT 1990 - Znservice Inspection Report 1999 Interval, Third Outage 1992 ATTACHMENT III Com onent Result Details Cont.
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| Drawin No. M-94 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T
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| ~ 395202 20A R 0.300 0.337 0.125 0.320 >88 UT 395212 21B 0.337 0. 125 0.295 88-82 UT 395214 21D 0.337 0. 200 0.291 88-82 UT 395216 21F 0.337 0.200 0.284 '88-82 UT (Note: "R" = Reducer, ll P It Pipe, "E" = Elbow)
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| Drawin No. M-96 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 396010 1 0.200 0. 125 0.222 >88 RT 396020 2 E 0.200 0. 125 0.198 >88 RT 396090 9 0.200 0. 125 0.263 >88 396100 10 0.200 0. 125 0.219 >88 RT 396510 51 0.200 0 ~ 125 0.199 >88 RT 396520 52 0.200 0. 125 0.190 >88 RT 396700 70 P 0.200 0. 125 0-200 >88 RT (Note: "R" = Reducer, "P" = Pipe, "E" = Elbow) 20
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| Ro E ~ GINNA NUCLEAR POWER PLANT 1990 - Inservice Inspects.cn Report 1999 Interval, Thi.rd Outage 1992 ATTACHMENT III Com onent Result Details Cont.
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| Drawin No. M-97 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 397020 2 E 0.280 0.200 0.278 >88 UT 397030 3 P 0.280 0.200 0.261 >88 UT (Note: <<P<< = Pipe, <<E<< = Elbow)
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| Drawin No. M-98 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 398010 1 P 0.500 0.295 0.424 88-82 UT 398100 10 R 0.500 0.337 0.200 0.300 >88 UT 398110 11 T 0.337 0.200 0.325 >88 UT 398120 12 E 0.337 0.200 0.235 70-65 UT 298250 25 0.337 0.432 .155/.200 0.312 >88 UT 398260 26 0.432 0. 200 0.393 >88 UT 398280 28 E 0.432 0. 200 0.419 >88 UT (Note: <<R<< = Reducer, <<P<< = Pipe, <<T<< = Tee, <<E>> = Elbow) 21}}
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