|
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20148T6101997-07-0303 July 1997 Follow-up to Special Rept SR-96-003-01:on 970411,damage to Cables for Sensors 1A & 1B Discovered.Sensor Cable for 7B Also Found Damaged.Cables for Channels 1A,1B & 7B Found Saturated W/Oil.Sensors Replaced for Channels 1A,1B & 7B ML20148N7281997-06-26026 June 1997 Special Rept SR-97-002-00:on 970513,personnel Identified Design Discrepancy for 'B' CCW Train Radiation Monitor. Design Flaw Existed Since Plant Built.Design Change DC-3537 Approved to Reroute Cooling Water Line from Connection ML20135E9641996-12-10010 December 1996 Special Rept SR-96-003-00:on 961027,valve & Loose Parts Monitoring Sys Declared Inoperable.Caused by Failure of Sensor on Channel 1.Sensor Will Be Replaced During Refueling Outage 8 ML20113E4501996-07-0303 July 1996 Special Rept SR-96-001-00:on 960603,output Breaker for EDG B Failed to Close.Caused by Intermittent Malfunction of Contacts on Synchronizing Switch.Performed Troubleshooting & Replaced EDG B Synchronizing Switch ML20094P5911995-11-27027 November 1995 Special Rept SR-95-004-00:on 951030,EDG Tripped on Turbocharger Low Lube Oil Pressure.Generated Condition Rept 95-1102 ML20094G2031995-11-0808 November 1995 Special Rept SR-95-003-00:on 951010,EDG Experienced Crankcase Overpressurization.Caused by Poor Lubricating Conditions During Startup & Rapid Loading Led to Tin Transfer from Piston to Cylinder Liner ML20093L8421995-10-23023 October 1995 Special Rept SR-95-002-00 on 951011,ABB C-E Identified Leaking Plug Due to build-up of Boric Acided Crystals Around OD of Plug.Leaking Plug Removed by Tig Relaxation & Replaced/Another Rolled Mechanical Plug ML20086E0181995-07-0707 July 1995 Special Rept SR-94-001-01:on 940228 & 0302,EDG a Experienced Nonvalid Failures Due to Worn Mechanical Governor Parts. Mechanical Governor & Faulty Relay Replaced & Procedure OP-009-02, EDG Revised ML20070N6601994-05-0404 May 1994 Special Rept SR-94-003:on 940404,EDG a Experienced Nonvalid Failure While Performing Valid Test.Probably Caused by Emergency Mode Master Run Relay 4EX1 de-energized During Run.Troubleshooting in Progress ML20065A3761994-03-29029 March 1994 Special Rept SR-94-001,on 940228,EDG a Tripped on Overspeed. Caused by Faulty Contacts in Relay of Electronic Grovernor Droop.Faulty Relay & Mechanical Governor Replaced ML20059B9521993-10-26026 October 1993 Special Rept SR-93-001-01,final Rept:On 930811,declared Condenser Vacuum Pump Wide Range Gas Monitor PRM-IRE-002 Inoperable.Monitor Returned to Svc on 930901.Inoperability of Subj Monitor Did Not Pose Safety Concern ML20056H1011993-09-0101 September 1993 Special Rept SR-93-001-00:on 930811,condenser Vacuum Pump WRGM PRM-IRE-002 Declared Inoperable & Not Returned to Svc within Seven Days.Monitor Will Be Returned to Svc After Low Range Sample Flow Cv Repaired & Functionally Checked ML20126M5881993-01-0606 January 1993 Special Rept SR-92-003:on 921207,EDG a Failed to Reach Rated Speed & Voltage in Less than or Equal to 10 S.Caused by Failure to Properly Secure Turning Gear Brackets.Control Brackets for Turning Gear Interlock Valves Adjusted ML20127M4981992-11-24024 November 1992 Special Rept SR-92-002-00:on 921023,component Cooling Water (CCW) A/B Radiation Monitor Was Inoperable for More than 30 Days.Ts Change Request NPF-38-127,dtd 921021 Submitted,Which Changes Operability Requirement ML20116B2121992-10-23023 October 1992 Special Rept SR-92-001-00:on 921010,inservice Eddy Current Exam of SG Tubing Completed,Per 10CFR50.36(c)(2).Total Number of Tubes Have Been Plugged in SG Shown as Listed ML20086K8731991-12-11011 December 1991 Special Rept SR-91-007-00:on 911111,diesel Generator a Loaded to 4.3 MW & Tripped.Caused by Inadequate Positioning of Turbocharger Inlet Air Butterfly Valve Limit Switch Mounting Bracket.Limit Switch Repositioned ML20086G0201991-11-27027 November 1991 Special Rept SR-91-002-02:on 910318,emergency Diesel Generator a Experienced Crankcase Overpressurization.Caused by Stuck Piston Rings.Piston & Piston Liner Replaced & Improper Temp Differential Will Be Corrected ML20083D4431991-09-23023 September 1991 Special Rept SR-91-002-01:on 910318,emergency Diesel Generator a Experienced Crankcase Overpressurization.Caused by Stuck Piston Rings & Improper Temp Differential.Cylinder Liner,Piston Assemblies & Rod Bearings Replaced ML20082U6231991-09-16016 September 1991 Special Rept SR-91-003-01:on 910406,inservice Eddy Current Exam of Facility SG Tubing Completed by Westinghouse.Rept Submitted Per Tech Specs 4.4.4.5 & 6.9.2.Rotating Pancake Coil Exam Results Verified No Detectable Degradation ML20082T2121991-09-13013 September 1991 Special Rept:On 910820,EDG Secured During Surveillance Test Due to Power Dropping Resistor Failure.Power Dropping Resistor Assembly Replaced.Health & Safety of Public & Plant Personnel Not Affected by This Event ML20082C4021991-07-15015 July 1991 Special Rept 91-005-00:on 910619,EDG a Tripped on Turbocharger Lube Oil Low Pressure During Performance of Operating Procedure 903-068.Procedure Changed to Require Lubrication of Turbocharger ML20073Q8001991-05-29029 May 1991 Special Rept SR-91-04-00:on 910429,EDG a Failed Invalidly Due to Spurious Turbocharger Lube Oil Pressure Trip.Edg Restarted.Oil Pressure Remained within Normal Operating Limits & OP-903-068 Completed ML20073B3231991-04-19019 April 1991 Special Rept SR-91-003-00,re 910406 Completion of Inservice Eddy Current Exam of Steam Generator tubing.Follow-up Rept Will Be Submitted by 920406,per Tech Spec 4.4.4.5.b.Total Number of Tubes Plugged in Each Steam Generator Listed ML20084U8591991-04-17017 April 1991 Special Rept SR-91-002-00:on 910318,emergency Diesel Generator a Experienced Crankcase Overpressurization. Possibly Caused by Improper Temp Differential Between Jacket Cooling Water & Lube Oil Temp.Liner Replaced ML20072Q8931991-03-18018 March 1991 Special Rept SR-91-001-00:on 910207,channel 2 of SPDS Failed & Could Not Be Restored within 7 Days.On 910214, Channel 2 of Qualified SPDS Sensor 8 Out of Svc for More than 7 Days.Channel 2 Probe Will Be Replaced ML20065R6021990-12-12012 December 1990 Special Rept SR-90-003-00:on 901112,invalid Failure of Emergency Diesel Generator a Occurred.Caused by Mechanical Failure of 30 Psig Reducer in Control Air Sys & Crack on Spring Cap of Reducer.All Reducers Inspected ML20246C9091989-05-0303 May 1989 Special Rept SR-89-001-01:on 890206 & 0403,emergency Diesel Generator a Declared Inoperable.Caused by Fuse Not Being Secured in Fuse Holder & Oxidation of Speed Control Circuit Relay Contacts.Contacts Cleaned & Fuses & Holders Checked ML20245A3951989-04-10010 April 1989 Special Rept SR-88-004-01:on 880420,inservice Eddy Current Exam of Steam Generator Tubing Completed by Westinghouse.Two Tubes Exceeded Plugging Limit in Steam Generator A.All Discrepancies Resolved ML20236B0941989-03-0808 March 1989 Special Rept:On 890206,emergency Diesel Generator Secured Due to Failure of Speed Control Circuit While Generator in Manual Operation.Caused by Oxidation of Relay Contacts in Governor Control Circuitry.Contacts Replaced ML20206H4901988-11-18018 November 1988 Special Rept SR-88-009-00:on 880909,emergency Diesel Generator Tripped Due to Incorrect Valve Lineup.Caused by Personnel Error.Valves Opened ML20151U8841988-08-16016 August 1988 Special Rept SR-88-008-00:on 880726,plant Stack Effluent Accident wide-range Gas Monitor Declared Inoperable.Caused by Pump Failing Step 8.4.2.18 Which Checks high-range Sample Flow within Specified Tolerance.Transmitter Replaced ML20151C1121988-07-15015 July 1988 Special Rept SR-88-007-00:on 880628,primary Meteorological Tower Instruments out-of-svc Greater than Seven Days.Caused by Instruments Being Out of Calibr.Temp Elements Replaced & Corrective Maint on Delta Temp Instruments Completed ML20151C0781988-07-15015 July 1988 Special Rept SR-88-006-00:on 880616,emergency Diesel Generator B Tripped Due to Personnel Error.Caused by Failure to Raise Load within 5 S.Operating Procedure OP-9-002 Reviewed & Considered to Adequately Address Operation ML20195H7171988-06-20020 June 1988 Special Rept SR-88-005-00:on 880511,unit Was in Refueling Mode When Operations Personnel Declared Seismic Monitor SM-IYR-6021 Inoperable.Plastic Lexan Mounting Board Appeared to Be Deformed Due to Heat.Monitor Will Be Relocated ML20153F3831988-05-0404 May 1988 Special Rept SR-88-003-01:on 850801-880404 Several Failures of Emergency Diesel Generators to Start Occurred.Caused by Actuation of Trips Which Bypassed in Emergency Mode.Trip Sensor Replaced ML20153F2541988-05-0404 May 1988 Special Rept SR-88-004-00:on 880420,inservice Eddy Current Exam of Steam Generator Tubing Completed.Rept Submitted in Accordance W/Tech Specs 4.4.4.5.a.Number of Tubes Plugged in Each Steam Generator Listed ML20148F1021988-03-21021 March 1988 Special Rept SR-85-002-01:on 851230,discovered Emergency Diesel Generator a Failed to Complete Surveillance Run as Defined in Procedure OP-903-068 & Tech Spec 4.8.1.1.2a.5. Cause Not Determined.Minor Adjustments Made to Governor ML20148F0971988-03-18018 March 1988 Special Rept SR-88-003-00:from 850801-880308,several Emergency Diesel Generators Failed to Start.Caused by Malfunctioning Trip Mechanisms.Diesels Will Not Be Taken Out of Svc Until Plant Scheduled to Be out-of-svc for Maint ML20149J3411988-02-18018 February 1988 Special Rept SR-88-001-00:on 880128,during Plant Startup Operations,Personnel Declared Fuel Handling Exhaust Wide Range Gas Monitor out-of-svc for Calibr.Caused by Extensive Teardown.Procedure Revised ML20236Q1121987-11-16016 November 1987 Special Rept SR-87-006-00:on 871028,primary Meteorological Tower Upper Wind Speed & Wind Direction Instrument out-of- Svc in Excess of 7 Days.Caused by Failed Signal Converter. Parts Replaced & Instrument Returned to Svc on 871104 ML20236Q2621987-11-13013 November 1987 Special Rept SR-87-005-00:on 871103,Tech Specs 3.3.3.1 & 6.9.2 Violated.Caused by Inoperability of Effluent Accident wide-range Gas Monitor for More than 7 Days Due to Damaged Connectors.New Monitor Should Be Installed by 871125 ML20235J8531987-09-24024 September 1987 Special Rept SR-87-004-00 Re Results of Inservice Eddy Current Exam of Steam Generator Tubing Completed on 861214. No Indication of Degradation Greater than or Equal to 20% Through Wall Detected in Steam Generator a ML20237G9341987-08-21021 August 1987 Special Rept SR-87-003-00:on 870731 & 0809,condenser Vacuum Vacuum Pump Discharge Wide Range Gas Monitor (WRGM) Inoperable.Caused by Water Blockage of Sample Lines.Wrgm Restarted & Being Tested for Operation ML20234B2111987-06-29029 June 1987 Special Rept SR-87-002-00:on 870606,high Range Gas Monitor Inoperable Greater than 7 Days.Caused by Faulty Display Module & Lack of Spares & Quality Documentation.Module Replaced & Monitor Returned to Svc After Functional Test ML20215H0841987-06-17017 June 1987 Special Rept SR-87-001-00:on 870527,during Full Reactor Power,Condenser Vacuum Pump Discharge Wide Range Gas Monitor Declared Inoperable.Caused by Failed Input/Output Circuit Board & Low Range Detector.Faulty Components Replaced ML20205G1731987-03-18018 March 1987 Ro:On 870222,steam Line Break on Scavenging Steam Vent Line from Moisture Separator Reheater Experienced.Caused by Classic Fatigue Failure in Heat Affected Zone of Weld Joining Alloy 800 Matl.Temporary Restraints Added W3P87-0237, Suppl 1 to Special Rept SR-85-001:on 850916,seismic Monitor Mounted on Pressurizer Found Damaged & Inoperable.Relocation of Seismic Monitor Completed,But Tech Spec Not Yet Approved1987-01-19019 January 1987 Suppl 1 to Special Rept SR-85-001:on 850916,seismic Monitor Mounted on Pressurizer Found Damaged & Inoperable.Relocation of Seismic Monitor Completed,But Tech Spec Not Yet Approved ML20214V2821986-09-26026 September 1986 Special Rept SR-86-005-00:on 860909 & 17,secondary & Primary Towers Removed from Svc,Respectively,But Not Returned to Svc within 7 Days.Caused by Need to Replace Hoist Cables. Secondary Tower Returned to Svc on 860916 ML20206J6331986-06-20020 June 1986 Special Rept SR-86-004-00:on 860523,emergency Diesel Generator a Malfunctioned.Caused by Failure of Power Parallel Voltage Dropping Resistor in Electrical Governor Control Circuit.Power Resistors & Amplifier Replaced ML20211H3531986-06-13013 June 1986 Special Rept SR-86-003-00:on 860523,wide-range Gas Monitor PRM-JR-0110 Declared Inoperable.Caused by Performance of Functional Test Per Procedure MI-3-382.Check Valve Removed & Seat Reworked.Monitor Returned to Svc on 860604 1997-07-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 ML20195K3391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Waterford 3 Ses.With ML20195C3041999-05-28028 May 1999 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20206S7401999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Waterford 3.With ML20205T2621999-04-22022 April 1999 LER 99-S02-00:on 990216,contract Employee Inappropriately Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Security Personnel Performed Review of Work & Work Area That Individual Was Involved with ML20205N9671999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Waterford 3 Ses.With ML20205E8531999-03-30030 March 1999 Corrected Pages COLR 3/4 1-4 & COLR 3/4 2-6 to Rev 1, Cycle 10, Colr ML20205A6331999-03-25025 March 1999 SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3 ML20204H1401999-03-23023 March 1999 Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3 ML20204H1231999-03-22022 March 1999 Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping ML20204H2451999-03-22022 March 1999 Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3 ML20204F0791999-03-17017 March 1999 Rev 1 to Waterford 3 COLR for Cycle 10 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207F3491999-03-0505 March 1999 LER 99-S01-00:on 990203,contraband Was Discovered in Plant Protected Area.Bottle Was Determined to Have Been There Since Original Plant Construction.Bottle Was Removed & Security Personnel Performed Search of Area.With ML20204B5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Waterford 3.With ML20203H8591999-02-17017 February 1999 Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 ML20199H6261999-01-21021 January 1999 Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change ML20199C9101998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Waterford 3.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20206N4131998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Waterford 3.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20195E5161998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Waterford 3.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K0801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Waterford 3 Ses. with ML20151W8331998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Waterford,Unit 3. with ML20237B6831998-08-17017 August 1998 LER 98-S01-00:on 980723,discovered That Waterford 3 Physical Security Plan,Safeguards Document Was Not Under Positive Control of Authorized Person at All Times.Caused by Human Error/Inappropriate Action.Counseled Employee Involved ML20237C5661998-08-17017 August 1998 Safety Evaluation Accepting Licensee Request for Exemption from Section Iii.O of Appendix R to 10CFR50 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 ML20237B5261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Waterford 3 ML20236S9031998-07-22022 July 1998 SER Accepting Rev 19 to Quality Assurance Program for Waterford Steam Electric Station,Unit 3 ML20198H3911998-07-14014 July 1998 Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool ML20236N4181998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Waterford,Unit 3 ML20248E7781998-06-0101 June 1998 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20249A4711998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Waterford 3 Ses ML20196A4051998-05-31031 May 1998 Rept of Facility Changes,Tests & Experiments,Per 10CFR50.59 for 970601-980531. with ML20198H4681998-05-20020 May 1998 Non-proprietary Rev 1 to HI-981942, Independent Review of Waterford Unit 3 Spent Fuel Pool Cfd Model ML20247A3891998-05-0101 May 1998 SG Eddy Current Examination (8th Refueling Outage) ML20247F6761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Waterford,Unit 3.W/ ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20216B1751998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Waterford 3 Ses ML20217M1411998-03-0303 March 1998 Rev 2 of Waterford 3 Cycle 9 Colr 1999-09-30
[Table view] |
Text
, _ _ _ _ _ _ _ . . _ _ . . . _ _ _ _.
- ._...-._____m
_ __ _ _. ._ . _ . . .____.m...___. .
=
7,,,,
(Q{^[ Entergy Operations,inc.
Operations .
W3HL-91 0237 A4.05 QA September 16, 1991 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555
SUBJECT:
Waterford 3 SES Docket No. 50-382 LicensJ No. NPF-38 Reporting of Special Report Gentlemen:
Attached is Special Report Number SR-91-003 01 for Waterford Steam Electric Station Unit 3. This Special Report is submitted per Technical Specifications 4.4.4.5 and 6.9.2.
Very truly your ,
/ ,
Cm '
k O/,f ..'I D.F. Packer General Manager Plant Operations DfP/WEF/rk Attachment cc: Messrs. R.D. Martin G.L. Florreich J.T. Wheelock INPO Records Center E.L. Blake N.S. Reynolds NRC Resident inspectors Office l
100C04
-9109200269 910916 PDR ADOCK 050003B2 / l S PDR
l SPECIAL REPORT SR-91-003-01 STEAM GENEPATOR EDDY CpHRENT EXAMINATION (ATH KEFUEl.ING)
INTRODUCTION Inservice eddy current examination of Waterford 2 Steam Generator (SG) tubing was completed by Westinghouse Electric poration NSD on April 6, 1991. This report is submitted in accordance with Technical Specification 4.4.4.5, which requires the con.plete results of this inspection be submit ted in a special report pursuant to Technical Specification 6.9.2, within 12 n'on;hs f ollowing the inspection.
The eddy current testing included full length bobbin coil examinations of 318 tubes (3.4%) In SG #1, and 303 tubes (3.2%) in SG #2. Additionally, 259 tubes (2.7%) in SG #2's hot leg were examined at the top of the tubesheet with a Rotating pancake Coll (EPC) to inapect for circumferential cracking induced by stress corrosion cracking. RpC examination resulta verified No Detectable Degradation (NDD).
As recommende1 by Combustion Engineering's Report CEN-328, " Remedy Ior Steam Generator Tube And Diagonal Strap Wear," Waterford 3 elected to plug the remaining tubes in the batwirg uear concern area. A total of 312 tubes (156 tubes per SG) were plugged with bestinghouse Inconel-690 mechanical plugs as ,
part of batwing preventive plugging. Prior to any plugging, Westinghouse identified nnd marked tubes to be plugged by utilizing the Eddy Current Test (ECT) probe to ensure correct hot / cold leg tubcsheet locations. Steam generator tubesheet marking was performei in accordance with Plant approved Westinghouse procedure MRS 2.2.2 GEN-12, Rev. 2, "Ste n Generator Tubesheet Marking."
Additionally, Waterford 3 deelded to have '4cstinghouse remove 6 Inconel-600 mechanical plugs (3 per hot leg) which were subject to Primary Water Stress Corrosion Cracking (PWSCC). During tube plugging activities, Westinghouse reinstalled 6 Inconel-690 mechanical plugs of Heat No. NX-6779HK.
1
.. .. l All SG tube examinations were conducted in accordance with USNRC Hegulatory Guide 1.83 and ASME Section XI using Westinghouse procedure MRS 2.4.2 GEN-28
" Digital Multifrequency Eddy Current inspection of Preservice And Innervice Heat Exchanger Tubing." ,
i HESULTS OF E'.(AMINATION S1EAM CENERATOR #1 The eddy current testing of 318 tubes in SC #1 resulted in the following analysis of 32 indications! ,
o 6 Tubes Greater Than or Equal To 20% Thru Wall But Less Than 40% Thru
-Wall F
o 7 Tubes Lens Than 20% Thru Wall o 19 Tuben With Manufacturing Buff Marks (MBMs)
In addition, a video scan of SG #1's tubesheet was perfortned to verify plugged tube locations. All tube plugs in SG #1 were secure and in the correct tube locations. f The following tube listing identifies the indicaticun as a result of examining.
-318 tubes (3.4%) in SG #11 - - -
1.
ROW LINE % THRU WALL LOCATION COMMENTS ,
28 18 MhM BW1 15' 25 20% 6H 37 33 MBM TSil 70 38 MBM TSC 1
l
. - . - . _ . . . . _ _ _ . . . . _ _ . _ _ _ _ _ _ _ _ _ ____.._m _ _ _ . _ , . _ . . . . _ , . . . _ , , . _ . . _ , _ _ _ , , . . . . , . . _ . , , _ . , _ . , _ , .
S, TEAM CENERATOR #1 (Cont 'd) r R0W LINE % TilRtf WALL LOCATION COMMENTS l
'57 137 MBM TSC 19- 67 29% BW5 PLUCCED (PREVENTIVE. i PLUGGING) 56 TO MBM 6 11 j
2 96 .76 MBM IC i
95 77 - MBM 5C/70 54 78 MBM 4C .
74 76 MBM 2C/SC 146 80 19% BW1 -I 82 86 19% BW9 83 87 ~ MBM 41I ;
80 88 MBM 80 i
f l- 104 88 MBM 6C/711 l
l 53 91 MBM 7c 147 91 - 12% BW9 l
84 92 11% 7C ;
FWe yW ' e' y 4M 4t"e-e -Y ve + 5+=NP+ * *e-m--rF y "Nw#TYT4'r
- ~ - . _ .. - - ....~ _ ..
l l
STEAM GENERATOP #1, (Cont'd)
ROW LINE % TI:RU WAL1, LOCATION COMMENTS j 145 95 11% BW9 146 96 12% BW9 146 100 121 Et'9 75 105 26% 4 11 PLUGGED (PHEVENTIVE PLUGGING) 46 106 MBH 6C 82 108 MhH 2 11 j 77 113 MBM- 6C/811 136 120 MBM BW1 30 '126 MBM TSC 70 134 -32%/34% BW4/BW5 Pl.UGGED (PREVENTIVE
- PLUGGING) 46 148 36% BWS Pl.UGGED PREVENTIVE PLUGGINC)
- 2 2 -- 158 .MBM _ SC 32 158- 20% SH -
i e
a g t%r-- -- -
y ve n , ,---,e --, -, rw mi,,-- , e m c e m .,g-m-me.ve,--, men'_ , . Eym sw. ...w.,-- .,,.wn.m -, . - - - a -E
l L
STEAM GENERATOP #1 (Cont'd) i l
The following list of SG #1 tubes were plugged Refuel 4 as a result of Combust'on Engineering's recommendation for resolving the batwing wear area concernt ROW- LINE RDW !.INE l
' 30 70 35 71 l I
32 70 37 71 !
34 70 39- 71 36 70 41 71 !
38 10 43. 71
}'
40 70 32 72 42 70 34 72 !
I 31 71' 36 ~72 i 33 .71 38 72 !
k i
40 72 48 76 l l
E42 72. 41 77 I f
t 44 72. - 43 77. 1
-f 33 73 45 77 -j f
37 73 47 77 t
i b
rn l
STEAM GENERATOR #1 (Cont'd)
ROW 1.1 NE HOW 1,1 N E 39 73 44 78 41 73 46 78 43 73 48 78 45 73 43 79 34- 74 45 79 36 74 47 79 38 74 46 80 40- 74 48 80 42- 74 50 80 44 74 47- 81 ;
t 46 74 49 81 I
-37 75- 51 81 t
39 75 48 82 41- 75 50 82 +
43 75- 52 82 45 75 47 83 i
6 e
.--_-.i2 1_ i-.___.__.__, _ _ _ _ - . . _
STEAM CENERATOR #1 (Cotit ' d)
ROW LINE BOW 1.1 N E 47 75 51 83 38 76 48 84 40 76 50 84 42 76 52 84 46 76 49 85 51 85 47 95 53 35 49 95 48 86 51 95 50 86 46 96 52 86 48 96 49 87 50 96 48 8" 45 97 50 88 47 97 52 88 42 98 49 89 44 98 51 89 46 98
STEAM GENERATO'.< #1 (Cont'd)
R 0k' LINE F 0b' LINE 48 90 48 98 50 90 43 99 52 90 45 99 49 91 47 99 51 91 40 100
$3 91 42 100 48 92 44 100 50 92 46 100 52 92 48 100 47 93 39 101 49 93 41 101 51 93 43 101 48 94 45 101 50 94 47 101 52 94 34 102 36 102 40 104
_ . - . . _ - _ ______..____._m _.-__m__ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ ___ _
4
, STEAM GENERATOR til (Cont'd)
EDW LINE ,R, O'd LINE 38 102 42 104 40 102 44 104 42 102 31 105 44 102 33 105 46 102 35 105
, 33 103 37 105 35 103 39 105 37 103 41 105 39 103 43 105 41 103 30 106 43 103 32 106 i
45 103 34 106 32 104 36 106 34 104 38 106 36 104 40 106 38 104 42 106
!I j .. j
- I t
STEAM CENERATOR #1- i i ;
) ,
- In addition, the following SG #1 hot leg tube mechanical plugo (inconel-600) ;
! . were retraved and replaced with Inconel-690 mechanical plugst I HOW l.INE '
s s :
) 12 *. 45 Ii e
j_ 42 78 ,
l
! i i, !
i f
49 83 4 i j I 4 i 4
G 6 i
).
)
[ '.
4 I !
t i
i o
1 I
t
{
2 l.
f i
l t
5
.t c
.i l -
STEAM GENERATOR #2, i l
l The Eddy Curre.it Testing of 303 tubes in SG #2 resulted in the following l l analysis of 15 indientions:
o 5 Tubes Greater Than 20% Thru Wall But Lens Than 40% Thru Wall !
t o 2 Tubes Less Than 20% Thru Wall o 8 Tubes W1th Manuf acturing Buf f Mm ks (M11Ms)
In addition, a video scan of SG #2's tubesheet was performed to verify plugged tube Ic ations. All tube plugs in SG #2 were secure and in the correct tube locationn.
t The following tube listing identifies the indiention as a result of examining 303 tubes (3.2%) in SG #2:
30W LINE I TilRU WALL 1.0 CATION COMMENTS f- .21 16% IC
.' 0 5 31 12% 5 11 l
22 44 MBM 1 11 30 46 MEM lit 137.- 57 26% llW1 PLUGGED (PREVENTIVE PLUGGING) 17 67 37% P,W1 PLUGGED (PREVENTIVE PLUGGING)
~
146 86 26% BW9 PLUGGED (PREVENTIVE PLUGGING) l l
l
STrfM GENERATOR #2 (Cont'd)
ROW LINE i TilRU UA1.L LOCAT'.CN COMMENTS 66 88 35% BW4 PLUGGEJ (PREVENTIVE PLUGGING) 91 89 MBM 14'7 145 91 30% BW8 PLUGGED (PREVENTIVE Pl.UGGING) 128 102 MBM 7C 75 111 MBM 2C 39 113 MBM IH 2 114 MBM 3C 138 114 MBM TSil The followinr. list of SG #2 tubes were plugged Refuel 4 at a result of Combustion Engineering's recommendation for resolving the batwing wear area concern:
ROW LINE ROW LINE 30 70 42 72 ,
22 70 44 72 34 70 35 73 36 70 37 73
I
)
STEAM CENERATOR f2, (Cont'd) _ i RW LINE- ROW 1.l N E 1
i 38 70 39 73 40- 70 41 73 42 70 43 73 31 71 45 73
-33 71- 34 74
'35
- 71 36 74 .
37 71 38 74 P
39 ~71 40 74 41 71 42 74 43 -71 44 74 32 72 46 74 ,
34 72 37 75 36 .72 39 75
- Y 38: 7_2 41 75.
40 72 4) -75~
43 75 47- 83 j n.'
3
,mm. , - , , --,-nnn-c -
-.,,-,--e,-,.,,-r- -a-. . . - - ., + - , - . , - . . ..----n--- - . .. - , - . + . - --c , w--, - . .
_ _ . . ._ _ .. _. _ _ _ ._ __ _ , ___ _ _ _ = _ . - .
- 1
- i STEAM CENERATOR #2 (Cont'd) >
I
. ]
ROW LINE R0W LINE ll 47 75 49 83 I
38 76 51 83 i
i- 42 76- 48 84 1
44 76 50 84 3
/6 76 52 84- 1
- . - 48 76 49 85 I i
41 77 51 85 i i
l 43 77 53 85 .t 45' 77 48 86 .
41 77 50 86 42 78 52 86
~44, -78 49 87 46 78 51- 87 48 78 48 88 43 79. 50 88 i.
45 79- 52 88 eewh=-- +E ,,-.-h.--.-.m.~.7 m...,_twm-- -,mr..yem _ ,,-g-. .,,. ..%.,%,,m,%.,,m_.m e ,_.,ww_ ____c,,,,mm,m,.,,,,,,,,,,,, , , . ,
..... .. - .- -.~. - . . - . - .... - - - -.. - .
4 .
STEAM CENEHg DR #2 (Cont'd)
-i ROW LINE ROW LINE l
47 79 31 89 j i
l 46 83 48 90 l
l 48 80 $0 90 I
$0 80- 52 90 49 81 49 91 51 -- 81 51 91 <
48 82 $3 91
$0 82 48 92 e 52 81 50 92 s2 92 48 100 r
47 93 37 101 !
t
'49 93 39 101 51 93 41 101 48 94 .43 101 1
50 94 45' 101.
4 52 94 47 101
. . .. - ... . . . . . . . - . .-..:_.-.-. - . - . . , , , - . - ~ ,- - ,. - --. - ,,,-..-,-- - - , _
STEAM CENERATOR #2 (Cont'd)
ROW EDW LINIl L1]E 49 95 34 102 51 95 38 102 46 96 40 102 48 96 42 102 50 96 44 102 43 97 46 102 45 97 35 103 47 97 37 103 42 98 39 103 44 98 41 103 46 98 43 103 48 98 45 103 c 41 99 32 104 43 99 34 104 47 99 36 104 38 100 38 104
STI AM Cl:NERNIDit #2 (Cont'd) 14 OW i.1 N E ItOW L1NF 42 100 40 104 44 100 42 104 46 100 44 104 31 105 30 106 33 105 33 106 35 105 34 10f.
37 105 36 106 39 105 38 106 41 105 40 106 43 105 42 106 The following list of SG #' hot Icg tube mechanical plugs (Inconel-600) were removed and replaced with Inconel--690:
It0W LINE
'3 73 47 95 19 109 Plant Contact J.E. Iloward. Prcourement/ Programs Engineering Manager (504)739-6327
. _ _ _ _ _ - _ _