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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML17353A6141996-02-28028 February 1996 Part 21 Rept 10CFR21-0073 Re Defect W/Voltage Adjust Potentiometer Mfg by Chicago Telephone Supply Used on NEI Peebles (Portec) Voltage Regulators at Plant.Util Updating Voltage Regulators W/Maury Instrument Corp Potentiometer ML17352B1391995-04-28028 April 1995 Part 21 Rept Re Mechanical Defect in Shaft Length of Some HEA63 Lockout Relays Mfg Between 1990-94.Defect Identified Could Possibly Result in Binding of Front Shaft.Suspect Relays Checked for Date Codes & Replacements Ordered ML17352A8951994-11-15015 November 1994 Part 21 Rept Re Unit 3A Sequencers at Turkey Point Plant. Unless Contacted by FP&L to Perform Programming Changes & Subsequent V&V to Sequencer Software,United Controls Plans No Other Evaluation of Defect for Listed Reason ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML17348B4411992-03-23023 March 1992 Interim Part 21 Rept Re Westinghouse Reactor Vessel Head Adaptor Tube Cracking.Wog Approved Project Authorization on 920205 for Reactor Vessel Closure Head Penetration Alloy 600 Primary Water Stress Corrosion Cracking ML17348B3051991-12-12012 December 1991 Supplement to 910812 Part 21 Rept Re Potential Generic Defects in Abb Type RHMH2 Model RK223068-EA & 069-EA Relays. Caused by Tape Fold Back Condition.New Method for Installing Insulation Tape Initiated ML17348B0431991-08-16016 August 1991 Part 21 Rept Re Potential Generic Component Defect Found During Insp of Asea/Abb Type RXMH2,Model RK223068-EA & RK223069-EA Relays.Caused by Misplacement of Insulating Tape Installed on Coil Termination ML17348B2921991-08-12012 August 1991 Part 21 Rept Re Potential Generic Component Defect in Asea/Abb Type RXMH2 Relays.Relays Utilized in Emergency Diesel Generator Bus Load Sequences.Info Gathering Underway. Customers Will Be Notified as Soon as Possible ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML17347A7511988-05-0202 May 1988 Part 21 Rept Re Component Cooling Water Sys Containment Isolation Function.Addl Evaluation of Issue in Progress as Part of Util Design Basis Effort.Ltr Sent as Formal Followup to Feb 1988 Discussion ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20204E9161986-06-30030 June 1986 Rev 0 to Part 21 Rept JPE-L-86-75 Re Potential for Overloading Emergency Diesel Generators (EDG) Prior to Dec 1985.EDG Levels Exceed Highest FSAR Value Levels.Test Data Demonstrates That EDG Could Not Accept High Levels ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires NRC-86-3142, Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List1986-06-19019 June 1986 Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List ML20211K1491986-06-10010 June 1986 Part 21 Rept Re Potential for Exceeding FSAR Limits for Emergency Diesel Generator Loading Prior to Nov 1985. Justification for Continued Operation Written & Evaluation Complete ML20135E2271985-08-23023 August 1985 Part 21 & Deficiency Rept Re Potential Problems W/Natl Valve & Mfg Co Pipe Clamps.Initially Reported on 850613.Ltrs Sent to Purchasers of Pipe Clamps Encl for Perusal ML17340B1431981-03-31031 March 1981 Part 21 Rept Re Review of All Deficiency Repts Submitted to NRC for 770810-800731.Forwards LERs Determined Reportable Under 10CFR21 L-75-474, Interim Deficiency Rept Re Leaking Field Welds on Lines. Investigation Still in Progress.Next Rept Expected by 7510311975-10-0303 October 1975 Interim Deficiency Rept Re Leaking Field Welds on Lines. Investigation Still in Progress.Next Rept Expected by 751031 ML20084M1981973-05-30030 May 1973 Deficiency Rept Re Three Bent Instrument Nozzles on Reactor Coolant Pipe Spool 42-inch RC-503-01.Caused by Rigging &/Or Transportation of Spool to Reactor Containment Area.Nozzles Replaced ML20084M2051973-05-16016 May 1973 Deficiency Rept Re HX Mods Made to Rhr,Spent Fuel Pit & Nonregenerative HX to Meet Design Flow Rates W/O Potential Vibration Problems ML20084M5891972-12-11011 December 1972 Deficiency Rept Re 720908 Unusual Event 72-1 Concerning Simultaneous Safety Injection Signal.Initially Reported on 720908.Caused by Design Deficiency in Vital 120-volt Distribution Sys.Static Inverters & Station Batteries Added 1998-09-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML17355A4471999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With 991008 Ltr ML17355A4121999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With 990909 Ltr ML17355A3981999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Turkey Point,Units 3 & 4.With 990809 Ltr ML17355A3891999-07-20020 July 1999 LER 99-001-00:on 990623,manual Rt from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With 990720 Ltr ML17355A3841999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Turkey Point,Units 3 & 4.With 990713 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17355A3611999-06-30030 June 1999 Refueling Outage ISI Rept. ML17355A3511999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Turkey Point,Units 3 & 4.With 990609 Ltr ML17355A3331999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Turkey Point,Units 3 & 4.With 990511 Ltr ML20217B9871999-04-0808 April 1999 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408 ML17355A2881999-04-0505 April 1999 COLR for Turkey Point Unit 4 Cycle 18. ML17355A2911999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Turkey Point,Units 3 & 4.With 990414 Ltr ML17355A2551999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Turkey Point Nuclear Power Plant,Units 3 & 4.With 990315 Ltr ML17355A2261999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Turkey Point,Units 3 & 4.With 990211 Ltr ML17355A2201999-01-20020 January 1999 Refueling Outage ISI Rept. ML17355A1911998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Turkey Point,Units 3 & 4.With 990112 Ltr ML18008A0461998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Turkey Point,Units 3 & 4.With 981209 Ltr ML17354B1921998-11-18018 November 1998 LER 98-007-00:on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With 981118 Ltr ML17354B1891998-11-0909 November 1998 Simulatory Certification Update 2. ML17354B1901998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Turkey Point,Units 3 & 4.With 981112 Ltr ML17354B1591998-10-23023 October 1998 COLR for Turkey Point Unit 3 Cycle 17. ML17354B1361998-10-16016 October 1998 LER 98-004-00:on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With 981016 Ltr ML17354B1311998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Turkey Point Unit 3 & 4.With 981012 Ltr ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML17354B0981998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Turkey Points,Units 3 & 4.With 980915 Ltr ML17354B0771998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Turkey Point,Units 3 & 4.W/980810 Ltr ML17354B0341998-07-15015 July 1998 LER 98-003-00:on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves ML17354B0241998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Turkey Point,Units 3 & 4.W/980709 Ltr ML17354B0171998-06-29029 June 1998 Rev 1 to PTN-FPER-97-013, Evaluation of Turbine Lube Oil Fire. ML17354A9841998-06-18018 June 1998 LER 97-007-01:on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps ML17354A9741998-06-0909 June 1998 LER 98-002-00:on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML17354A9711998-05-31031 May 1998 Monthly Operating Repts for Turkey Point,Units 3 & 4. W/980611 Ltr ML17354A9231998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Turkey Point,Units 3 & 4.W/980511 Ltr ML17354A8821998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Turkey Point,Units 3 & 4.W/980409 Ltr ML17354A8511998-03-24024 March 1998 LER 97-009-01:on 971114,discovered That CR Console Switch for 3B Sgfp Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR ML17354B0001998-03-18018 March 1998 Florida Power & Light Topical Quality Asurance Rept, Dtd June 1998 ML17354A8441998-03-18018 March 1998 LER 98-001-00:on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be revised.W/980318 Ltr ML17354A8311998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Turkey Point,Units 3 & 4.W/980311 Ltr ML17354A7871998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Turkey Point,Units 3 & 4.W/980209 Ltr ML17354A7581997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Turkey Point,Unit 3 & 4.W/980112 Ltr ML17354A7361997-12-12012 December 1997 LER 97-009-01:on 971114,identified That CR Console Switch for 3B SG Feedwater Pump Was Not in Start Position.Caused by Inadequate Procedural Guidance.Procedures 3/4-OP-074,SGFP Were revised.W/971212 Ltr ML17354A7381997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Turkey Point,Units 3 & 4.W/971215 Ltr ML17354A7211997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Turkey Point,Units 3 & 4.W/971114 Ltr ML17354A7491997-10-13013 October 1997 SG Insp Rept. ML17354A8851997-10-13013 October 1997 FPL Units 3 & 4 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 960408-971013. ML17354A6801997-10-0808 October 1997 LER 97-008-00:on 970909,containment Sump Debris Screens Outside Design Basis Due to Stress Damage Was Discovered. Caused by Inadequate Procedural Guidance & Personnel Error. Discrepancies Found on Screens corrected.W/971008 Ltr ML17354A6791997-10-0606 October 1997 COLR Unit 4 Cycle 17, for Turkey Point ML17354A6811997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Turkey Point,Units 3 & 4.W/971009 Ltr 1999-09-30
[Table view] |
Text
FFL-JNL (38 P,g4 r
5UBSTANTIAL SAFETY HAZARD EVALUATION TURKEY POINT UNITS 3 & 4 (PTPN)
EMERGENCY DIESEL GENERATOR LOAD EVALUATION l
POWER PLANT ENGINEERING DEPARTMENT FLORIDA POWER & LIGHT COMPANY 3UNO BEACH, FLORIDA i i
JPE-L-#JJ '
Rev1alen 0 ,
IP-Mechanical / Nuclear L:A
' Che&ed _
rv I&C Wo.m. Mob-);ha Tednical Licanalng Electrical I:7 T Civil 2
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/$ T1I, ,14 O Issue Dates 3tme,1984 l l
Approved: I P. G. Pluggepf/
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8608010355 860128 PDR ADOCK 05000250 PDR
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E~ n m-m Os v.Q 3PE-1.-86-73 Rev.0 Page 2 of 4 i -
l Introduction 1
The evaluation hereinaf ter is responsive. to the Nuclear Energy Departments' l
request (REA No. TPN-56-011) to evaluate Emergency Diesel Generator (EDG) loadings with regard to their potential reportability under 10 CFR 21. Prior to
' December 1933, a potential existed for placing loads on the EDGs that exceeded the1TPN Technical Specification auto-connect !!mit of 2730 kWI the Emergency Operating Procedure (EOP) limit of 2930 kW and the 1/2 Hour Exceptional Rating of 3030 kW. This evaleatlon assesses whether or not these !!mits could have been exceeded, and whether a substantial safety hazard (as defined by 10 l
i CFR 21) existed prior to December 1983.
Evaluation 1
A load evaluation, conoucted in Decommer 1985, Indicated that the loads on the EDG for the case with one EDG in operation were as follows:
1 I
Aute-Connect 2747 kW 1-30 minutes 2873 kW 30 minutes - I hour 2794 kW ,
The December 1983 evaluation was based on the then current estimate of total
> ump kW on the EDC. Early in 1986,inplant testing of the ICW and CCW pumps
.ndicated that these pumps would oprate at higner flows than their design values. Additional inplant testing anc, analysis confirmed that this results in a nigher kW per pump than was ut!!! zed in the December 1985 evaluation. The total pump kW assumed in December 1985 and the value currently expected compare as follows:
Expected Delta M
0 - 30 minutes 2211 kW 2236 kW 43 1931 kW '964 kW +33 30 minutes . I hour This comparison confirms the fact that the pump loads used in the December 1983 analysis were underestimated. Had the current expected pump kW values been aval!able and included in the Cecember 1985 evaluation, the Technical -
Specification auto-connect limit of 2730 kW would have been exceeded.
The current two-EDG running toad evaluation Indicates that the maximum auto connect load based on exp6cted pump kW 1: 2399 kW. This evaluation assumes the implementation of speelfic plant changes that delete the auto-connect feature of the Normal Containment Coolers (NCC) and certain boric acid.related loads. Prior to.Decem>er 1983, these loads would have auto-connected to the EDG. Thus, they must be added to the current 2199 kW 4
-, -,n--,-,--n -.,nw-w ~ - _ - . - - - . - - - . . - - - , , . _ . - - , - - - - - - - - - - - - , . , , - - - , - - - -
W81 FFL-JNL 626 P.66
' JPE-L-86-73 Rev. O Page 3 of 4
= ** to determine the maximum auto connected two EDG running load prior to December 1983. The following loads mast be added: -
NCCs 128 kW i s ;ank Heaters 30 kW B A Transfer Pumps St kW 212 kW i
As a resuit, the auto-connect load prior w December 1983 coulo nave been 2811 Therefore, the 2730 kW auto-connected load kW for the two EDG case. ,
liinitation could also have been exceeded for the two (2) EDG case. !
Prior to December 1983, the Instrument Air Compressors and certain turbine re:ated loads could have auto-connected subsequent to Safety injection Signal l (515) reset without the operators' knowledge. These loads could have ralsed the j EDG load as follows:
IACs 186 kW ;
i Turbine-Related Loads 178 k%
j
)
j in November 1983, a Plant Change Modification was Installed to prevent the motor-driven fire pump from auto connecting to the EDG. Starting of the fire pump could have p aced an additional 21C 4W load on the EDG.
l PC/Ms 84 84 and 84-8) for Control Rod Drive Mechanism cooling fan power f source mod!fications were implemented such that they could automatically connect to the EDCs upon loss of offs.te power (REA No. TPN 86-11). This !
j potential existed on PTPN 4 from May 24, 1984 to June 22,1983, and on PTPN 3 l from February 17, 1983 to June 22, 1913. (PTPN 3 was in a refueling outage from March 30, 1983 to July 17,1983). The CRDMs on the hot shutdown unit l could potentially add 33 kW to the EDC.
The various loads cited above could hate auto-connected to the EDG In either the 1-30 minute or 30 minute-1 hour load intervals. All of these loads may not-l add concurrently. The turbine loads engage as the turbine rolls to a stop, and the 4
IACs and fire pumps engage on low header pressure. This notwithstandin5, there
. , r .. ,,..p' cal reason <nown that would preclude their concurrent auto-connectlen to the EDG. Additionally, the operator would not have prior knowledge of these auto-load additions. Thus, success of any operator diagnostic and corrective actions to mitigate a potential EDG overloading condition is i questionable.
Based on the above, there was a potential for loading the EDGs to the following sevels prior to November 1983:
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7 JPE-L-86-73 l Rev.0 Page 4 of 4 f
1-30 MinJtes_ 30 Minutes - : Hour i j
2873 kW 2794 kW i
December 1983 Estimate !
t
+45 +33 .
Increase in Pump kW !
i
+186 +186 r UNCs
+178 +178 Turbine Loads i
+210 +210 ,
! Fire Pump
+50 3LO, 4
CRDM Fans 3344 kW 3431kW l'
. i These potential EDG toad levels exceed the highest F5AR value of 3030 kW by a l substantial margin. There is no test data available to demonstrate that the EDG could accept these load levels.
i Conclusions '
i 2
Based on the above, the following can be concluded with regard to EDG loadings prior to November 1985: ;
- ' The 2730 kW Technical Specification auto-connect limit could have been ,
exceeded.
- The F5AR 3030 kW 1/2 hour exceptional rating could have been exceedad. l I
- EDG loadings could have reached levels that could t-lp the EDG.
l
$1nce the Technical Specification 11rntt could have been exceeded and the i probability of malfunction of the I,DG was increased, operation prio.- to -
f November 1955 involved an unreviewed safety questjon.
i
! Since the one (1) operating EDG could have been overloaded to the point where it l woule trip, operation prior to November 1985 involved a substantial safety-l l
hazard. !
l l
1r/ Disc 0PTP EMERG.4/JPE L-86-73/0586/PG l
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