Similar Documents at Surry |
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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 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 1993 ANNUAL STEAM GENERATOR INSERVICE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY
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. PDR ADOCK 05000280 Q PDR: - .,__,
SURRY UNIT 2, APRIL 1993 RFO S/G "B", EDDY CURRENT EXAMINATION
SUMMARY
In Steam Generator "B", 3342 tubes were inspected full length with bobbin probes. Supplemental examinations were also performed using Rotating Pancake probes where additional confirmatory or other data was desired. This included an examination of 301 tubes in the top of the tubesheet transition area. Of the tubes inspected, 91 tubes contained one or more indications. Two tubes were preventively plugged for anti-vibration bar wear. Including the plugged tubes, 30 tubes had indications between 20% and 29% through wall, 45 tubes had indications between 10% and 19% through wall, 20 tubes with 21 SAA signals, one tube with a PVN signal and one tube with a DRI signal. See the attached list for details.
e SURRY UNIT 2, APRIL 1993 STEAM GENERATOR "B" EDDY CURRENT EXAMINATION INDICATION LIST ROW COL LOCN IND REMARKS 15 9 6H 16 18 9 7C SAA 3 10 7C 22 16 11 5C 14 21 11 6H 13 4 12 4H 13 30 15 5H 14 28 16 4C 25 7 17 2C PVN 12 19 6C 21 13 19 6H 16 2 23 4C 17 30 26 2H 15 15 27 6H 11 17 27 lH 17 3 28 TSH SAA 13 28 6H 22 28 31 6H 28 43 31 2C 29 18 35 3H 27 2 36 lC 10 3 36 2H 19 Page 1 of s
SURRY UNIT 2, APRIL 1993 STEAM GENERATOR "B" EDDY CURRENT EXAMINATION INDICATION LIST ROW COL LOCN IND REMARKS 19 36 TSC 19 21 36 TSH 15 12 38 6C 19 45 38 7H 11 25 39 4H 15 44 39 lC 10 45 39 lC 17 29 40 6H 19 13 41 lH 11 12 42 TSH SAA 26 42 2H 16 10 43 TSC 10 13 43 lH 25 42 44 4H 15 34 45 6H 15 7 46 TSH SAA 14 46 6C 18 34 46 BPC 14 32 47 4C 15 40 47 3C 21 3 48 2C 16 23 48 2C 24 Page 2 of 5
SURRY UNIT 2 1 APRIL 1993 STEAM GENERATOR 11 B11 EDDY CURRENT EXAMINATION INDICATION LIST ROW COL LOCN IND REMARKS 45 48 6H SAA 9 50 4H 16 19 50 TSH SAA 44 50 6H 13 1 56 TSH 25 9 56 6C 20 9 56 TSH SAA 36 56 2C 14 41 56 lC 23 3 57 TSC SAA 17 57 5H 24 17 57 4C 16 25 57 6C 10 41 57 4C 26 34 58 4C 23 36 58 2C 22 41 58 6C 17 42 58 lH 11 4 59 4C 18 4 59 TSC SAA 30 59 2C 22 32 59 6C 27 38 59 4C 12 Page 3 of 5
SURRY UNIT 2, APRIL 1993 STEAM GENERATOR "B" EDDY CURRENT EXAMINATION INDICATION LIST ROW COL LOCN IND REMARKS 24 60 2C 27 40 60 AV3 20 plugged*
1 61 3H SAA 3 61 7H SAA 3 62 TSH SAA 3 62 3H SAA 38 62 7H SAA 20 63 7H SAA 33 63 AV2 20 plugged*
33 63 AV3 14 3 64 4C 18 12 64 TSH SAA 4 65 6C 29 12 65 4C 13 32 65 TEH DRI 32 65 7H 22 3 66 -TSH SAA 22 66 2C 27 2 67 lH 22 2 67 6H SAA 1 68 TSH SAA 20 69 lC 11 4 72 2C 29 37 74 4C 13 Page 4 of 5
SURRY UNIT 2, APRIL 1993 STEAM GENERATOR "B" EDDY CURRENT EXAMINATION INDICATION LIST ROW COL LOCN IND REMARKS 3 80 4C 27 19 80 7H SAA 2 83 3C 24 13 84 3C 14 18 87 5C 21 20 87 6C 10 15 89 lC SAA
- These tubes were preventively plugged.
Page 5 of 5
e ATTACHMENT 2 GLOSSARY OF TERMS SURRY POWER STATION ANNUAL STEAM GENERATOR INSERVICE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY
VIRGINIA ELECTRIC AND POWER COMPANY STEAM GENERATOR EDDY CURRENT TUBE INSPECTION GLOSSARY OF TERMS
- 1. ROW, COL COLUMN tube identifier numbers an X-Y coordinate system.
- 2. IND INDICATION Character codes and numerics that represent the analysis results of the data for that tube, e.g., SAA, 25%, etc.
- 3. INF Indication Not Found Indicates that a previously reported Indication, from current inspection data or historical data, is not found in the data being analyzed - also used to address the case where a tube/
signal is being retested for positive identification (PID) and the retest data does not show any signal present.
- 4. LOCN LOCATION The location in the tube of the INDICATION called.
- 5. DR! DISTORTED ROLL TRANSITION INDICATION - A possible tube wall loss condition that is unquantifiable with a numeric percent call due to the signal characteristics and is located at the roll transition - often retested with RPC (Rotating Pancake Coil Probe).
- 6. 55 A number in the indication column shows the%
through wall depth of the indication.
- 7. PVN PERMEABILITY VARIATION A variance in the tube permeability that produces a signal that can mask other signals of interest.
- 8. SAA SINGLE AXIAL ANOMALY Describes a single axially oriented anomaly signal from RPC (Rotating Pancake Probe) data. The anomaly is based on metallurgical evaluation of tube pull data and is caused by lift-off from a slight inside diameter depression in the tube.
9 TEH Tube End Hot leg.
- 10. TEC Tube End Cold leg.
- 11. TSH Top of Tube sheet Hot leg.
- 12. TSC Top of Tube sheet Cold leg.
- 13. BPH, BPC Baffle Plate Hot Leg and Cold Leg 1
e VIRGINIA ELECTRIC AND POWER COMPANY STEAM GENERATOR EDDY CURRENT TUBE INSPECTION GLOSSARY OF TERMS
- 14. #C, #H (#=number) of Support Plate Hot or Cold leg.
e.g., 3H, 6H, 7C.
- 15. AVl, AV2, AV3, AV4 Anti-Vibration Bars 1 through 4.
Note: Where no comment appears in the remarks column the tube is still in service.
2
e ATTACHMENT 3 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 TUBESHEET MAPS VIRGINIA ELECTRIC AND POWER COMPANY
X : 2 TUBES TO BE PLUGGED .
S/G B TUBES TO BE PLUGGED '
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- N 80 NON-QUANTIFIABLE INDICATION (INDICATION TESTED WITH RPC) 2 20 20 ,c - 29 ,c INDICATION Surry Unit 2 VIR-8 SERIES 51F 1 25 10 x - 19 ,c INDICATION 8 : 118 7 MANUFACTURES BUFF MAf\K 03-29-1993 08:09 HRS. SUPERTUBIN * : Same note as hot leg map.
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