|
---|
Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML17229A9961999-01-14014 January 1999 SG Tube Inservice Insp Special Rept. ML17229A6861998-04-0303 April 1998 Form OAR-1 Owners Activity Rept, for Slp Unit 1,second Interval,Third Period ML17229A6131998-01-12012 January 1998 Rev 1 to ISI-PSL-1, St Lucie Nuclear Plant,Unit 1 ISI Sketches. ML17229A4411997-06-19019 June 1997 SG Tube ISI Special Rept. ML17229A0851996-10-18018 October 1996 NIS-1 Owner Data Rept for Isi. ML17228B4611996-03-25025 March 1996 Form NIS-1 Owners Data Rept for Inservice Insps, for 960325 ML17228B0261995-02-0303 February 1995 Rev 0 to Second ISI Interval Second Insp Period Third Outage 1994 Summary Rept Submittal. ML17228A8361994-08-0303 August 1994 Rev 1 to JNS-PSL-204, Second Ten-Yr ISI Interval IST Program for Pumps & Valves,St Lucie Nuclear Power Plant Unit 2. ML20071H9701994-07-0808 July 1994 Second ISI Interval First Insp Period First Outage 1994 Summary Rept Submittal for St Lucie Unit 2 ML17228A3021993-09-0606 September 1993 Rev 0 to Second ISI Interval Second Insp Period Second Outage 1993 Summary Rept Submittal. ML20137K4911993-07-21021 July 1993 Npp,Unit 2,Second 10-yr Inservice Insp Interval IST Program ML17228A2401993-07-21021 July 1993 Second Ten Yr Inservice Insp Interval Inservice Testing Program. ML17227A6091992-09-22022 September 1992 Spring 1992 Refueling Outage ISI Rept. ML17227A3621992-03-23023 March 1992 Owners Data Rept for Inservice Insp (Forms NIS-1 & NIS-2), St Lucie Unit 1. ML17227A3191991-12-31031 December 1991 Steam Generator Inservice Insp Rept St Lucie Unit 1 for 1991 ML17223B1421991-03-0707 March 1991 Inservice Insp Summary Rept for St Lucie Unit 2,1990 Refueling Outage. ML17223A9231990-08-28028 August 1990 Owners Rept for Inservice Insps as Required by Provisions of ASME Code Rules. ML17223B1201990-07-16016 July 1990 Steam Generator Inservice Insp Rept. ML17223A2311989-07-17017 July 1989 Inservice Insp Rept for 890201-0428.Exam Included Class I & II Components & Piping Sys ML17222A6251988-12-14014 December 1988 Errata to 881130 Inservice Insp Rept,Consisting of Forms NIS-1 & NIS-2, Owners Rept for Repairs or Replacements. ML17222A6001988-11-30030 November 1988 Inservice Insp Rept for Second 10 Yr Interval ML17222A5621988-10-31031 October 1988 Eddy Current Exam of Steam Generator Tubing During Oct 1987. ML17221A6391988-02-12012 February 1988 1987 Inservice Insp Summary Rept, Describing Insp & Testing of ASME Code,Section Xi,Class 1 & 2 Components & Piping Sys & Corrective Measures Recommended & Taken ML17219A6911987-07-10010 July 1987 1987 Inservice Insp Summary Rept. ML17216A5101986-04-25025 April 1986 Inservice Insp Rept for 851020-1224.Listed Components Inspected & NDE Techniques & Results Discussed.Statement Re Status of Work for Current Interval Encl ML17219A2171985-12-31031 December 1985 1986 Inservice Insp Summary Rept. ML17215A7631985-02-19019 February 1985 Rev 0 to Vol 1 of 1984 Inservice Insp Final Rept. ML20094P4701984-08-0909 August 1984 Inservice Insp Rept on 830302-840516,describing Exams Performed on Pressure Containment Appurtenance for in-core Instrumentation Flange Assembly 1999-01-14
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17241A4891999-10-0707 October 1999 LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr ML17241A4951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for St Lucie,Units 1 & 2.With 991014 Ltr ML17241A4741999-08-31031 August 1999 Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr. ML17241A4591999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr ML17241A4301999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr ML17241A4111999-07-16016 July 1999 LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr ML17241A4031999-07-0606 July 1999 LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr ML17241A4041999-07-0606 July 1999 LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr ML17241A4091999-06-30030 June 1999 Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr ML17241A3941999-06-30030 June 1999 LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17241A3551999-06-0404 June 1999 LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr ML17241A3631999-05-31031 May 1999 Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr ML17241A3321999-05-17017 May 1999 LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11 ML17241A3271999-05-0606 May 1999 LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr ML17241A3331999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr ML17229B0801999-04-0707 April 1999 LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr ML17229B0841999-04-0707 April 1999 Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines. ML17229B0791999-04-0707 April 1999 LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr ML17229B0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr ML17229B0541999-03-10010 March 1999 LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr ML17229B0461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for St Lucie,Units 1 & 2.With 990310 Ltr ML17229B0051999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for St Lucie,Units 1 & 2.With 990211 Ltr ML17229A9901999-01-20020 January 1999 LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr ML17229A9961999-01-14014 January 1999 SG Tube Inservice Insp Special Rept. ML17229A9821999-01-0404 January 1999 LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr ML17229A9831998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr ML17229A9611998-12-22022 December 1998 LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr ML17229A9561998-12-15015 December 1998 LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr ML17241A3581998-12-0909 December 1998 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period of 970526-981209. ML17229A9421998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for St Lucie,Units 1 & 2.With 981215 Ltr ML17229A9301998-11-25025 November 1998 LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage ML17229A9021998-11-0404 November 1998 LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr ML17241A4931998-11-0101 November 1998 Statement of Account for Period of 981101-990930 for Suntrust Bank,As Trustee for Florida Municipal Power Agency Nuclear Decommissioning Trust (St Lucie Project). ML17229A9051998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for St Lucie,Units 1 & 2.With 981110 Ltr ML17229A8871998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length ML17229A8781998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length ML17229A8771998-10-14014 October 1998 LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr ML17229A8761998-10-14014 October 1998 LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr ML17229A8721998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for St Lucie Units 1 & 2.With 981009 Ltr ML17229A8511998-09-0202 September 1998 LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr ML17229A8611998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for St Lucie,Units 1 & 2.With 980911 Ltr ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML17229A8481998-08-0707 August 1998 Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr. ML17229A9461998-08-0707 August 1998 Rev 0 to PCM 98016, St Lucie Unit 2,Cycle 11 Colr. ML17229A8301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for St Lucie,Units 1 & 2.W/980814 Ltr ML17229A8201998-07-29029 July 1998 LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr ML17229A7981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for St Lucie,Units 1 & 2.W/980713 Ltr ML17229A7701998-05-31031 May 1998 Monthly Operating Repts for May 1998 for St Lucie,Units 1 & 2.W/980612 Ltr ML17229A7411998-05-28028 May 1998 LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr 1999-09-30
[Table view] |
Text
Florida Power & Light Company St. Lucie Unit f2 Nuclear, Plant Special Report For DDY CURRENT EXAMINATION OF STEAM GENERATOR TUBING DURING OCTOBER, 1987 Nuclear Energy Services Materials, Codes and Inspections Department Juno Beach, Florida 33408 SSi10104i3 8S1024 PDR ADOCK 05000389 9 PDC
I I
1 5(,,
Introduction The Nuclear Energy Services, Materials, Codes & Inspection Department, conducted an inservice eddy current examination of the Florida Power & Light St. Lucie Unit g2 Steam Generator Tubing in October, 1987. The extent of this examination included 1004 of non-plugged hot leg and cold leg tubes in accordance with plant technical specifications using multi-frequency eddy current equipment and differential bobbin coil test probes. The eddy current data was subjected to two independent analyses using certified data analysts from Combustion Engineering, NDE Technology and Zetec, Inc.
Discrepancies in the independent analyses were resolved by Level III individuals from the respective agencies.
St. Lucie Unit g2 contains two Combustion Engineering series 67 recirculating steam generators identified as PSL-2A and PSL-2B. Each steam generator contains approximately 8,411 u-bend tubes made of inconel 600. A baseline eddy current examination was performed in July, 1982 and the first inservice eddy current examination was performed in October, 1984. An unscheduled inservice eddy current examination was last performed in March, 1985, due to primary to secondary tube leakage which was identified and attributed to flow; induced vibrational wear at the diagonal and vertical support straps, referred to as batwings (Figures 1 and 2). To obtain wear progression data, 29 tubes which were plugged in March, 1985 were de-plugged in April, 1986 and examined using a standard bobbin coil and a segmented bobbin coil probe. The segmented bobbin coil probe provides wear data at both sides of the tube in contact with the batwing. The results of this wear progression analyses is presented in Combustion Engineering report CEN-328 dated May, 1986. Application of
'he wear progression model and conservative management practice during the October, 1987 outage resulted in "preventive maintenance plugging" of six (6) additional tubes in PSL-2A and two (2) additional tubes in PSL-2B. Table 1 provides a summary by steam generator of tubes examined, indications of tube wall penetration and tubes plugged.
Table 2 provides a listing of tubes plugged as a result of the October, 1987 examination and application of wear progression models. Refer to Figure 1 as a key to location codes. A total of 8 tubes were plugged in the PSL-2A generator and 10 tubes were plugged in the PSL-2B generator. Seven (7) tubes in PSL-2A were plugged as a result of wear at batwing or vertical support straps. One (1) tube was plugged as a result of wear from a foreign object; identified by visual examination to be a length of weld wire at the periphery of the tube bundle. Ten (10) tubes were plugged in PSL-2B as a result of wear at batwing or vertical support straps.
Table 3 provides a listing of all indications of tube wall penetration by location for each steam generator.
l E
A I'
r.
t,
A number of tubes had indications located at the batwing areas which represent the initiation of tube wall damage from vibration as discussed above. However, the wear at these areas has not advanced to the point which will produce a measurable result in terms of wall penetration. Therefore, these indications are identified in the eddy current database and the affected tubes will be monitored during subsequent examinations or otherwise dispositioned.
PSL-2A PSL-28 V2 V4 vl~ ~v5 DH- (Top) - (Top)
(Bottom) - (8ot tom) 09H 09C 38.25" OOH- 08C 38.25" 07H 070 37.5" 06H 05H f I 35.0e 32.0" 06C 050 04H li 04C 37.5w 03H f
030
- 35. 0" 02H 020 OIH I! II I 32.0" OIC TSH 28.0" TSC.
TEH 21. 5 TEC INLET OUTLET le Ct'atea ~ Kiev. 1 to 7 Drilled Supporte
'T.
~ Elev. 8 & 9 LUCIK II STEAK GENERATOR ARRANGEMENT Figure 1
I gglP HEI l DH-(top)
DH (bottom) gyps
~
~>+
~APE BEND RFG!ON TVBE, 5UPPORT5 PLANT ST. LUClK UNlT 2 Figure 2
TABLE 1 St. Lucie Unit 2 Summa of Inservice Edd Current Examination Results for October 1987 PSL-2A PSL-2B TOTAL TUBES EXAMINED Indications of Wall Penetration IND Less than 204 337 186 20 to 394 27 16 40 to 1004 2 9 Total 366 211 Tubes Plugged based on Wear Progression Analysis and Management Conservatism Tubes Plugged Which Exceeded Plugging Limits Total Tubes Plugged 10 Total Tubes Plugged To Date 208 155
TABLE 2 St. Lucie Unit 2 Steam Generator Tubes Plu ed Durin the October 1987 Outa e Steam Generator A Line Row Indication Location 56 94 40 V4 59 133 40 DH 82 52 33 DC 92 42 37 DH 92 44 36 DH 94 40 34 DH 98 38 35 DC 130 116 33 TSH + 11.3 Steam Generator B Line Rov Indication Location 25 89 43 V2 38 96 51 V2 62 V4 69 133 45 V1 75 41 53 V3 80 48 33 DH 87 49 47 V3 88 46 47 V3 100 36 28 DC 100 92 42 V2 111 93 53 V2
St. Lucie Unit 2 Examination ram October 1987 Steam Generator PSL-2A List of all Tubes with Flaws 1
Line Row Indication Location 27 93 33 V4 + 1.0 33 105 31 V2 + 0.2 48 126 27 DH + 0.9 52 84 36 V3 + 0.2 56 94 25 V4 + 0.1 40 V4 + 0.9 57 95 32 V2 0.8 58 132 28 DH + 0.0 59 133 40 DH + 0.0 61 83 20 V3 + 0.9 64 94 29 V2 + 1.0 64 134 21 DH + 0.0 73 47 25 V3 + 0.9 81 47 20 V3 +- 0.8 82 52 33 DC + 0.0 87 69 24 5C + 8.9 91 109 34 TSC + 4.0 92 42 37 DH + 0.0 92 44 36 DH + 0.0 94 40 34 DH + 0.0 96 40 26 V3 0.7 96 50 30 V3 0.8 98 38 35 DC + 0.0 98 138 22 DH + 0.0 108 96 27 V2 + 0.7 117 113 22 5H + 29.7 127 53 22 V3 + 0.8 129 87 28 V3 + 0.7 130 116 33 TSH + 11.3
TABLE 3 St. Lucie Unit 2 Examination Pr ram October 1987 Steam Generator PSL-2B List of all Tubes with Flaws Line Row Indication Location 24 96 30 8H 1.0 25 89 43 V2 0.9 34 96 26 V2 + 0.5 38 96 51 V2 0' 62 V4 0.9 68 32 22 DH + 0.0 69 133 45 V1 + 0 '
75 41 53 V3 0.9 76 112 36 7C + 0 '
78 50 21 DC + 0.0 79 47 21 DH + 0.0 79 49 25 DC + 0.0 80 48 33 DH + 0.0 83 89 35 V3 0.7 87 49 47 V3 0' 88 46 47 V3 + 0 ~ 0 88 56 39 V3 + 0.8 97 97 26 TSH + 20.8 99 35 28 DC + 0.0 100 36 28 DC + 0.0 100 92 42 V2 0.9 111 93 53 V2 + 0.6 122 94 21 V2 1.1 123 97 23 V3 + 0.7 134 104 20 V1 + 0.5