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Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18151A2861998-01-26026 January 1998 SPS Unit 2 ISI Summary Rept for 1997 Refueling Outage ML18151A3111997-07-21021 July 1997 Inservice Inspections Abstract of Exams. ML18151A4381996-08-0808 August 1996 Form NIS-1 Owner Rept for ISI, Required by Provisions of ASME Code ML18152A1901995-12-31031 December 1995 Vepc SPS Units 1 & 2 1995 Annual SG ISI Rept. ML18151A2811995-12-27027 December 1995 Form NIS-1 Owner Rept for Inservice Insps, as Required by Provisions of ASME Code Rules ML18151A2281995-06-0707 June 1995 NIS-1 ISI Summary Rept for June 1995. ML18151A2241994-05-24024 May 1994 ISI Summary Rept for 1994 Refueling Outage ML18153A8731994-02-23023 February 1994 Annual Steam Generator ISI Rept. ML18151A2781993-11-10010 November 1993 IST Program Plan for Pumps & Valves Third Insp Interval 940510-20051, Rev 0 ML18151A2221993-05-0606 May 1993 Refueling Outage 2nd Interval,3rd Period Isi. ML18153D2381993-02-0909 February 1993 Annual SG Inservice Insp Rept. ML18151A2051992-07-15015 July 1992 ISI Rept for Surry Power Station Unit 1 for 1992 Refueling Outage,2nd Interval,3rd Period. ML20094H0271991-12-31031 December 1991 1991 Annual Steam Generator Inservice Insp Rept ML18151A1591991-09-0505 September 1991 Inservice Insp Rept of Surry Nuclear Power Station Unit 2, Second Interval,Second/Third Period. ML18151A1561991-03-12012 March 1991 Inservice Insp Summary Rept for 1990 Refueling Outage. W/910312 Ltr ML18153C5481991-02-25025 February 1991 Annual Steam Generator Inservice Insp Rept. ML18153C1391990-03-0808 March 1990 Suppl to Inservice Insp Rept,Consisting of NIS-2 Forms for Stud & Nut Replacement ML20011D3861989-11-27027 November 1989 Inservice Insp Rept of Surry Nuclear Power Station Unit 2, 2nd Interval,2nd Period. ML18153B6251989-03-0101 March 1989 1988 Annual Steam Generator Inservice Insp Rept. ML18151A2531988-10-10010 October 1988 Inservice Insp Summary Rept of Surry Power Station. ML18130A4441987-04-0101 April 1987 Rev 1 to Surry Power Station Unit 2 Inservice Insp Program, Interval 2,830501-930501. ML20205J9641987-03-30030 March 1987 Suppl to Owners Rept for Inservice Insps & Exams, Conducted on 850625-861202.Exam Resulted in Total of One Nozzle Weld Being Reported on Basis of Procedure Recording Criteria ML18130A4401987-03-27027 March 1987 Rev 3 to Surry Power Station Unit 1 Inservice Insp Program, Interval 2,821222-921222. ML18150A5201986-12-31031 December 1986 1986 Annual Steam Generator Inservice Insp Rept,Eddy Current Exam. ML20205F5081986-11-14014 November 1986 Inservice Insp Rept of Surry Nuclear Power Station,Unit 1 ML18139B5571981-08-31031 August 1981 Inservice Insp Rept on 800920-810705.Exam Procedures Were Approved Prior to Exams & Certification Documents Re Personnel,Equipment & Matls Were Reviewed & Determined to Be Satisfactory ML18139B5551981-07-31031 July 1981 Inservice Insp Rept on 810301-0705.Exams Conducted to Review Exam Zone within Geometric,Metallurgical & Physical Limitations.No Indications Found to Be Recordable ML20087B7671975-11-25025 November 1975 Inservice Insp Program,Refueling Outage 2. Insp Verified Integrity of Sys & Components ML20086Q1781975-06-15015 June 1975 Preliminary Results of Inservice Insp Program,Refueling Outage 1. No Significant Deficiencies Identified 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un. ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket 1999-09-30
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- ATTACHMENT 1 SURRY POWER STATION UNIT 1 19 9 0 ANNUAL STEAM GENERA TOR INSERVICE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY ( 9103040073 910225 ; PDR ADOCK 05000280 Q PDR
- ATTACHMENT 1 SURRY POWER STATION UNIT 1 REFUELING OUTAGE OCTOBER 1990 EDDY CURRENT EXAMINATION
SUMMARY
During the 1990 refueling outage for Surry Power Station Unit 1, the tubes in the "A," "B," and "C" steam generators were examined.
The material that follows presents the results of those examinations.
These results include the number and extent of the tubes examined, location and characterization of each indication of an imperfection, and the identification of the tubes that were plugged. Attachment 2 to this letter provides a glossary of terms (abbreviations) used.
- SURRY POWER STATION UNIT 1
- REFUELING OUTAGE OCTOBER 19 9 0 EDDY CURRENT EXAMINATION
SUMMARY
STEAM GENERATOR "A" Attachment 1 Page 2 of 8 In "A" Steam Generator, 203 tubes were examined with bobbin probes. Of these, 152 were examined full length (tube end to tube end), four were examined from the seventh support plate on the inlet side to the tube end on the inlet side, one was examined from the third support plate on the inlet side to the tube end on the inlet side, 27 were examined from the second support plate on the inlet side to the tube end on the inlet side and 19 were examined from the first support plate on the inlet side to the tube end on the inlet side. This is approximately six percent of the available tubes. In addition, all open tubes were examined at the inlet tubesheet
(+/-3") with a MRPC probe. Of the tubes examined, three had indications less than 19% through wall, one had a indication between 20% and 29% through wall, one had a indication between 30% and 39% through wall, one was characterized as a "possible indication," eight were characterized as "manufacturer's burnish marks," and 125 were characterized as "indication not reportable." No tubes were plugged. Refer to the table below for details. %TWD Location Row-Column Remarks INR lC R23C08 INR 6H R09Cl0 INR 2C R29C12 INR 3H R09Cl3 INR 4H R25C13 INR TSH R06Cl4 INR 5C Rl0Cl6 INR BPH Rl0C16 INR 3H R02Cl8 INR 4H R20C18 INR 3H R33Cl8 INR 5H Rl4C19 INR lH R22Cl9 INR lH Rl5C20 INR lH Rl9C21 INR 2H Rl9C21 INR 2H R21C22 INR 6H Rl5C23 INR 4H Rl9C24 INR lC R21C25 MBM 6H R15C27 INR TSH Rl5C28 INR lC R21C28 INR 6C R22C28
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%TWD Location INR lH INR SH INR TSH INR lC INR lH INR SH INR 6H INR 6C INR 4H INR lC INR TSH INR 2H INR 7H INR 7H INR lH INR 4H INR BPH INR 6C INR lH INR 2H 27 AV4 INR 7H INR 6C INR 4H INR 4H INR 6H INR 6C INR 7H INR 3C INR lH INR 3C 17 AVl INR 6C INR 6C INR 2C INR 6H INR 3H 17 AVl INR lC MBM TSC INR 4H INR SH INR 4C INR 4H INR BPC INR 6C INR 4C INR SC
- UNIT 1 "A" Row-Column R04C30 R16C30 R19C30 R13C31 R20C31 R42C31 R43C32 Rl3C33 R23C33 Rl2C34 R03C36 R09C36 R22C36 R22C37 R34C37 R34C37 R29C38 R34C38 R44C38 R12C40 R28C41 R28C42 R28C42 R34C42 R36C42 R36C42 R44C42 R28C43 R34C43 R24C44 R41C44 R46C44 R23C4S R2SC4S R28C4S R29C4S R36C4S R46C4S R21C46 R21C46 R26C46 R26C46 R07C47 R23C47 R32C47 R4SC47 R08C48 R40C48 Attachment 1 Page 3 of 8 Remarks
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- Attachment 1 Page 4 of 8 SURRY POWER STATION UNIT 1 STEAM GENERATOR "A" %TWD Location Row-Column Remarks INR TSH R42C48 INR 2C Rl6CSO INR SC R41CSO INR 4C R21CS1 INR 6H
- R31CS1 INR TSC RllCSS MBM 4H R36CS6 MBM 6H R36CS6 MBM 4C R39CS6 INR SH R43CS6 PI TSH R19CS7 INR TSH R3SCS7 INR 4C R3SCS7 INR 6C R41CS7 INR 7C R4SCS7 MBM SH R20CS8 INR BPC R24CS8 INR 3H R41CS8 INR 3H R44CS8 INR 4H R44CS8 INR 6H R44C58 INR 4C R15C59 INR AV4 R34C59 INR 7C R44CS9 INR 2H R27C60 INR 3C R27C60 INR AV4 R34C60 INR 2H R12C61 INR 2H R13C61 INR 6H R17C61 INR 7C R38C61 INR 6H R04C63 INR 7H Rl9C63 INR AV4 R21C64 INR SH R41C64 INR 4C R25C65 INR 3C R25C6S INR AV4 R39C6S MBM AV2 R40C6S INR 4H R42C65 INR 3H R40C66 INR 4H Rl6C67 INR TSH R27C67 INR 6C R21C68 INR 2H R08C69 INR AV4 Rl3C69 INR 7C R28C69 INR SH R31C69
- Attachment 1 Page 5 of 8 SURRY POWER STATION UNIT 1 STEAM GENERATOR "A" %TWO Location Row-Column Remarks INR 6H R31C70 INR 7C R31C70 INR 4C R20C71 INR 4C R35C71 30 6C R31C73 INR 5C R34C76 INR lC R07C77 INR 3H RllC79 MBM 6C Rl5C79 INR TSH R31C79 INR AV4 R31C79 INR lH R05C80 INR TSH R21C80 INR 6C R24C80 INR 4C R32C81 INR lC R24C83 INR BPC R30C83 INR lH R01C84 INR lC R28C84 INR 2H R02C28 INR 5H Rl6C86 INR 6H Rl6C86 INR 6C R24C86 INR AV2 R20C87 INR 7C R21C87 INR SC R21C87 INR 2C Rl9C88 MBM 3H R22C88 INR TSH R08C89 INR BPH R20C89 10 TSC R07C90 INR SH R14C90 INR 7C Rl4C90 INR BPH R03C91 INR BPC Rl2C92
- SURRY POWER STATION UNIT 1
- REFUELING OUTAGE OCTOBER 19 9 0 EDDY CURRENT EXAMINATION
SUMMARY
STEAM GENERATOR "B" Attachment 1 Page 6 of 8 In "B" Steam Generator, 911 tubes were examined with bobbin probes. Of these, 19 were examined from the second support plate on the inlet side to the tube end on the inlet side, 11 tubes were examined from the first support plate on the inlet side to the tube end on the inlet side and 881 tubes examined full length (tube end to tube end). This is approximately 27 percent of the available tubes. In addition, all open tubes were examined at the inlet tubesheet
(+/-3") with a MRPC probe. Of the tubes examined, one had a indication between 30% and 39% through wall, four had indications between 20% and 29% through wall, two had indications less than 19% through wall, one was charcterized as a "possible indication," three were characterized as "manufacturer's burnish mark," and three were characterized as "indication not reportable." No tubes were plugged as a result of the inservice inspection.
However, two tubes that were previously plugged were replugged (Rl1C14 and R33C43) in response to NRC Bulletin 89-01 concerns.
Refer to the table below for inspection details. %TWD Location Row-Column Remarks 13 TSC R27C15 24 AV4 R34C17 15 AV3 R35C17 29 6C R17C23 MBM 7H R43C37 28 6C R36C38 MBM 2H R36C38 INR TSH R07C39 MBM 3C R04C40 MBM 6C R19C41 MBM 7C R19C41 22 6C R11C43 INR TSH R42C44 31 TSC R45C48 INR 6C R46C52 PI TSH R26C75 .___I
- SURRY POWER STATION UNIT 1
- REFUELING OUTAGE OCTOBER 19 9 0 EDDY CURRENT EXAMINATION
SUMMARY
STEAM GENERATOR "C" Attachment 1 Page 7 of 8 In "C" Stearn Generator, 1302 tubes were examined with bobbin probes. Of these, two were examined from the second support plate on the inlet side to the tube end on the inlet side, 51 tubes were examined from the first support plate on the inlet side to the tube end on the inlet side, three tubes examined from the baffle plate on the inlet side to the tube end on the inlet side and 1246 tubes were examined full length. (tube end to tube end). This is approximately 39 percent of the available tubes. In addition, all open tubes were examined at the inlet tubesheet
(+/-3") with a MRPC probe. Of the tubes examined, three had indications between 30% and 39% through wall, three had indications between 20% and 29% through wall, five had indications less than 19% through wall, three were characterized as "possible indication," four were characterized as "manufacturer's burnish mark," and eighteen were characterized as "indication not reportable." Two tubes (R10C53 and R25C57) were pulled for evaluation of axial and circumferential anomalies at the top of the tube sheet and were subsequently plugged. The results of the evaluation indicated no operationally induced degradation of the tube wall. Also, two tubes that were previously plugged were replugged (R02C07 and R40C70) in response to NRC Bulletin 89-01 concerns.
Re£er to the table below for inspection details. %TWO Location Row-Column Remarks 20 2C R25Cll INR TSH R08C14 MBM 3H R06C16 INR TSH R34C16 14 2C R26C22 INR SH R31C27 INR SC R34C33 INR AV4 R25C36 14 6H R16C37 INR TSH R20C40 33 6H R39C40 MBM lC R43C40 INR TSH R37C41 INR TSH R20C42 37 TSH Rl7C44 17 6H R38C44 INR 6C RlOC52 16 2H R24C53 INR TSH Rl0C57
- Attachment 1 Page 8 of 8 SURRY POWER STATION UNIT 1 STEAM GENERATOR "C" %TWD Location Row-Column Remarks 31 4H R23C59 INR TSH R31C60 MBM 4H R39C61 INR TSH R03C64 INR TSH R40C67 PI TSH R07C68 PI TSH R30C69 INR 2C R08C73 INR TSH R10C77 PI TSH R07C79 18 AV4 R15C81 INR TSH R28C82 INR TSH R30C83 INR TSH R08C89 MBM 2C Rl3C91 24 2C Rl3C92 29 TSH R04C94 I I ** I *
- ATTACHMENT 2 GLOSSARY OF TERMS SURRY POWER STATION ANNUAL STEAM GENERATOR INSERVICE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY
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- ATTACHMENT 2 VIRGINIA ELECTRIC AND POWER COMPANY ANNUAL STEAM EDDY CURRENT GENERATOR REPORT TUBE INSPECTION GLOSSARY OF TERMS 1) INR -INDICATION NOT REPORTABLE
-This condition is characterized by data indicating small tube wall loss that is below the reportable criteria threshold for the specific inspection method used. This indication type can be comparatively used to address indications identified in previous inspections that are still detectable but fall below current criteria.
- 2) MBM -MANUFACTURING BURNISH MARK -This condition is characterized by a tube wall loss due to a manufacturing process step. This type of indication is generally a relatively long shallow loss area which remains constant and does not present any operating problems for the tube. These indications are noted for reference only. 3) PI -POSSIBLE INDICATION (retest) -This condition is generally associated with 8xl analysis or sometimes with bobbin analysis.
This type of indication describes a potential wall loss condition signal that typically requires a retest for verification.
Verification testing is sometimes retested with a special probe, e.g., MRPC, etc. 4) 5) 6) 7) 8) 9) 10) TEH TEC TSH TSC Tube End Hot leg. Tube End Cold leg. Top of Tubesheet Hot leg. Top of Tubesheet Cold leg. #C, #H e.g., 3H, (# = number) 6H, 7C. of Support Plate Hot or Cold leg, AVl, AV2, AV3, AV4 Anti-Vibration Bars 1 thru 4. BPH BAFFLE PLATE HOT Note: Where no comment appears in the remarks column the tube is still in service.