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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20046D3721993-08-10010 August 1993 Special Rept SR-91-002-03:on 910318,EDG a Experienced Overpressurization.Caused by Gross Cylinder to Cylinder Load Imbalance.Event Classified as Failure Per Reg Guide 1.108.Pulled & Replaced Cylinders ML20028H8441991-01-25025 January 1991 Special Rept SR-90-004-00:on 901226,emergency Diesel Generator Tripped on Loss of Field While Operating at 100% Power.Caused by Faulty Motor Operated Potentiometer.Faulty Component Replaced ML20011F3501990-02-23023 February 1990 Special Rept SR-90-002-00:on 900128,emergency Diesel Generator a Declared Inoperable to Perform Automatic Synchronization Test.Caused by Thick Oil Forming in Low Turbocharge Lube Oil Pressure Sensing Device.Device Cleaned ML20005G7681990-01-12012 January 1990 Special Rept SR-90-001-00:on 891229,condenser Vacuum Pump Wide Range Gas Monitor Inoperable Due to Spurious Alarms. Functional Test Per Maint Instruction (MI)-003-386 Satisfactorily Performed ML19351A4061989-10-16016 October 1989 Special Rept SR-89-002-00:on 890930,video Scan of Steam Generator 1 Tubesheet Indicated Presence of Foreign Object Lodged in Tube.Object Identified as Calibr Tube Pressure Cap.Caused by Inadequate Corrective Action 1993-08-10
[Table view] Category:LER)
MONTHYEARML20046D3721993-08-10010 August 1993 Special Rept SR-91-002-03:on 910318,EDG a Experienced Overpressurization.Caused by Gross Cylinder to Cylinder Load Imbalance.Event Classified as Failure Per Reg Guide 1.108.Pulled & Replaced Cylinders ML20028H8441991-01-25025 January 1991 Special Rept SR-90-004-00:on 901226,emergency Diesel Generator Tripped on Loss of Field While Operating at 100% Power.Caused by Faulty Motor Operated Potentiometer.Faulty Component Replaced ML20011F3501990-02-23023 February 1990 Special Rept SR-90-002-00:on 900128,emergency Diesel Generator a Declared Inoperable to Perform Automatic Synchronization Test.Caused by Thick Oil Forming in Low Turbocharge Lube Oil Pressure Sensing Device.Device Cleaned ML20005G7681990-01-12012 January 1990 Special Rept SR-90-001-00:on 891229,condenser Vacuum Pump Wide Range Gas Monitor Inoperable Due to Spurious Alarms. Functional Test Per Maint Instruction (MI)-003-386 Satisfactorily Performed ML19351A4061989-10-16016 October 1989 Special Rept SR-89-002-00:on 890930,video Scan of Steam Generator 1 Tubesheet Indicated Presence of Foreign Object Lodged in Tube.Object Identified as Calibr Tube Pressure Cap.Caused by Inadequate Corrective Action 1993-08-10
[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
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i-U.S. Nuclear Regulatory Commission '
ATTENTION: Document Control Desk Washington, D.C. 20555
SUBJECT:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Reportina of Special Report r
Attached is Special Report Number SR-89-002-00 for Waterford Steam Electric Station Unit 3. This Special Report is submitted per ,
Regulatory Guide 1.133.
Very'truly yours,
.R. McGaha lant Manager 'Quelear JRM/KTWark Attachment .
cc: Messrs. R.D. Martin '
J.T. Wheelock - INPO Records, Center l' E.L. Blake ll W.M. Stevenson
- 'D.L. Wigginton 1 NRC Resident Inspectors l
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SPECIAL REPORT F
F SR-89-002-00 t ,
1 l IN-CORE INSTRUMENTATION PRESSURE CAP DISCOVERED IN #1 STEAM GENERATOR INTRODUCTION I At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on September 30, 1989, Waterford Steam Electric Station Unit 3 !
was in cold shutdown when a video scan of the Steam Generator (SG) #1 tubesheet indicated the presence of a foreign object lodged in the tube opening at row 2 l
line 172. The foreign object was removed and positively identified as a movable in-core instrumentation (ICI) calibration tube pressure cap.
The ICI cap entered the Reactor Coolant S; stem (RCS) during refueling activities i e +
in April, 1988. The missing pressure cap was identified by Westinghouse ;
refueling personnel, but attempts to recover the cap were unsuccessful, i Discussion with the refueling supervisor revealed that at che time, Westinghouse' t personnel felt confident that-tbc cap had been flushed out of the reactor control element assembly upper guide structure (UGS) and into the deep end of the refueling canal. ICI removal and disposal operations were being conducted in the deep end of the refueling canal, making a visual verification impractical. ;
Because of the size of the cap (1.125 inches by 0.75 inches, 1.54 ounces) the Vibration and Loose Parts Monitoring System (VLPMS) diu not detect the ;
presence of the dust cap in the RCS.
l 1
The refueling team has examined their records and have determined that no other itecs were unaccounted for during the last refueling period. They have also l been instructed to notify the Waterford 3 Refueling Director of any future ,
occurrences relating to loose parts in the RCS. The presence of the pressure i cap had no measurable effect on SG heat transfer capability. Because the cap caused no damage to the SG tubesheet and did not affect core thermal performance, this event did not threaten the health and safety of the general public or
-plant personnel.
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At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on September 30, 1989, Waterford Steam Electric Station Unit 3 was in cold shutdown when a video scan of the Steam Generator (SG) #1 tubesheet indicated the presence of a foreign object lodged in the tube opening at row 2, line 172. The foreign object was removed and positively identified as a movable in-core instrumentation (ICI) calibration tube pressure cap. This report is submitted pursuant to Regulatory Guide 1.133.
The ICI pressure cap entered the Reactor Coolant System (RCS) during refueling activities in April, 1988. Refueling logs indicate that on April 20, 1988, technicians attempted to recover two ICI pressure caps from the reactor vessel flange. One cap was recovered, but the other cap slid onto the control element assembly (CEA) upper guide structure (UGS). On May 9, 1988, technicians again attempted to retrieve the cap but it fell down onto the ICI lower plenum plate.
Later that night the cap could not be located, leading personnel to the conclusion that the cap had been flushed out of the UGS and tato the refueling canal.
This conclusion was communicated to the Waterford 3 refueling director.
Refueling activities concluded without further pursuit of the pressure cap.
The plant has operated since May 1988 with no indication of a loose part in the j RCS.
The Waterford 3 Vibration and Loose Part Monitoring System (VLPMS) conforms to the sensitivity reqinirements imposed by Regulatory Guide 1.133, Revision 1 (detection of metallic loonc parcs weighing as little as 0.25 lb with a l
kinetic energy of 0.5 ft-lb, within 3 ft of a sensor). Because the pressure cap is cylindrically shaped, measuring 1.125 inches in length and 0.75 inches !
outer diameter with a mass of approximately 1.54 ounces, it is reasonable to l
, expect that the VLPMS would not have detected its presence in the RCS.
Additionally, the physical dimensions of the cap are such that complete entry ,
1 into a SG tube was prohibited as the inner diameter of a SG tube is a nominal !
0.69 inches. At the time of discovery, the cap was wedged (less than finger tight) at the inlet to the hot leg side of the SG tube mentioned above. :
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[ 'The pressure cap was recovered in its entirety. The internal spring loading L assembly was intact; therefore, there is no reason to believe that any cap internals.or wear products were carried to the reactor fuel area. An inspection of the tubesheet area did not indicate any material defects. The presence of the cap partially inhibited flow into the SG tube, but even complete blockage of the tube would not significantly diminish the heat transfer characteristics of the SG. Refueling records have been examined and a determination made that no other items entered the RCS.
The root cause of t.his event is inadequate corrective action. Refueling personnel did not place sufficient emphasis on recovery efforts, which resulted in a presumption (the cap was flushed into the refueling canal). becoming the final assessment of the problem. Recovery efforts were not adequately planned and implemented, resulting in cursory attempts to extract the pressure cap from the system. Contributing to this was a lack of specific tracking of components, such as ICI pressure caps or dust caps, located within the refueling cavity or UGS area.
This event has been discussed with refueling personnel currently on-site for refuel three. Refueling personnel will immediately notify the Waterford 3 refueling director of any situation which may have resulted in the introduction of a loose part in the RCS or any other interrelated system, and a formal recovery plan will be instituted. In addition to the foreign material. exclusion program ultilized to control entry of material into the refueling area, refueling procedures have been changed to specifically log and track ICI pressure capo and ICI dust caps.
l Because core thermal performance was not affected and the presence of the ;
i
! pressure cap caused no identifiable material damage to the SG tubesheet or 1
associated tube, this event did not threaten the health and safet.y of the general public or plant personnel, j
PLANT CONTACT R.S. Starkey, Operations Superintendent, 504/464-3134.
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