|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000302/LER-1997-040, Corrected Page 1 of LER 97-040-00,adding Rept Date in Block 7.On 971110,inadequate Engineering Documentation for safety- Related Large Bore Piping Analysis & Pipe Supports Noted. Caused by Personnel Error1997-12-0404 December 1997 Corrected Page 1 of LER 97-040-00,adding Rept Date in Block 7.On 971110,inadequate Engineering Documentation for safety- Related Large Bore Piping Analysis & Pipe Supports Noted. Caused by Personnel Error 05000302/LER-1997-039, Corrected Page 1 to LER 97-039-00,adding Rept Date in Block 7.On 971108,unqualified Matl Discovered Left in Reactor Bldg During Const.Caused by Personnel Error.Polystyrene Permanently Installed1997-12-0303 December 1997 Corrected Page 1 to LER 97-039-00,adding Rept Date in Block 7.On 971108,unqualified Matl Discovered Left in Reactor Bldg During Const.Caused by Personnel Error.Polystyrene Permanently Installed 3F0397-01, LER 97-S01-00:on 970130,maint Activities in Circulating Water Sys Resulted in Protected Area Breach.Caused by Failure to Identify Security Function of Plant.Armed Security Was Established1997-03-0303 March 1997 LER 97-S01-00:on 970130,maint Activities in Circulating Water Sys Resulted in Protected Area Breach.Caused by Failure to Identify Security Function of Plant.Armed Security Was Established 05000302/LER-1990-0101990-07-27027 July 1990 LER 90-010-00:on 900626,determined That Voltage Dips Caused by Sluggish Voltage Regulator Response Exceed Reg Guide 1.9 Limits.Caused by Improper Load Sequence Interval.Test Plan Being Developed for Testing Voltage regulator.W/900727 Ltr 05000302/LER-1989-013, Corrected LER 89-013-01:on 890409,when Time Delay Satisfied & Voltage Had Not Recovered,Emergency Diesel Generator Start Signal Was Initiated.Caused by Degraded Voltage on Engineered Safeguard 4,160 Volt Buses1989-07-0505 July 1989 Corrected LER 89-013-01:on 890409,when Time Delay Satisfied & Voltage Had Not Recovered,Emergency Diesel Generator Start Signal Was Initiated.Caused by Degraded Voltage on Engineered Safeguard 4,160 Volt Buses 05000302/LER-1984-001, Updated LER 84-001-01:on 840113,end Cap on Reactor Bldg Side of Spare Penetration 3531 Mistakenly Cut Off.Caused by Personnel Failure to Follow Applicable Engineering Procedures.Personnel Retrained1984-06-26026 June 1984 Updated LER 84-001-01:on 840113,end Cap on Reactor Bldg Side of Spare Penetration 3531 Mistakenly Cut Off.Caused by Personnel Failure to Follow Applicable Engineering Procedures.Personnel Retrained 05000302/LER-1983-058, Updated LER 83-058/03L-1:on 831103,while Performing Maint on 120-volt Ac Vital Bus Transfer Switch,Fuse Blew,Rendering Inverter 3A Inoperable.Caused by Personnel Inadvertently Shorting Out Lamp Base.Inverter repaired.W/840106 L1984-01-0606 January 1984 Updated LER 83-058/03L-1:on 831103,while Performing Maint on 120-volt Ac Vital Bus Transfer Switch,Fuse Blew,Rendering Inverter 3A Inoperable.Caused by Personnel Inadvertently Shorting Out Lamp Base.Inverter repaired.W/840106 Ltr 05000302/LER-1983-053, Updated LER 83-053/03L-1:on 831109,safety-related Hydraulic Snubber MSH-252 Declared Inoperable When Lack of Oil Level Indication Noted in Sightglass.Caused by Loose jam-nut on Stationary End of Snubber,Allowing rotation.W/84011984-01-0606 January 1984 Updated LER 83-053/03L-1:on 831109,safety-related Hydraulic Snubber MSH-252 Declared Inoperable When Lack of Oil Level Indication Noted in Sightglass.Caused by Loose jam-nut on Stationary End of Snubber,Allowing rotation.W/840106 Ltr 05000302/LER-1983-045, Rev 1 to LER 83-045/03X-1:on 831016,1104 & 08,175-ft Wind Speed Instrumentation & on 831028 & 1102,33-ft Wind Direction Instrumentation Discovered Inoperable.Caused by Severe Weather Damage & Component Failure1983-12-0101 December 1983 Rev 1 to LER 83-045/03X-1:on 831016,1104 & 08,175-ft Wind Speed Instrumentation & on 831028 & 1102,33-ft Wind Direction Instrumentation Discovered Inoperable.Caused by Severe Weather Damage & Component Failure 05000302/LER-1983-031, Supplementary LER 83-031/03L-1:on 830725,containment Isolation Valve CAV-6 & -7 Would Not Close Under Sys Pressure of 1,000 Psi.Caused by Insufficient Design &/Or Inadequate Maint Procedures1983-09-0707 September 1983 Supplementary LER 83-031/03L-1:on 830725,containment Isolation Valve CAV-6 & -7 Would Not Close Under Sys Pressure of 1,000 Psi.Caused by Insufficient Design &/Or Inadequate Maint Procedures 05000302/LER-1983-023, Updated LER 83-023/01T-1:on 830613,fire Damper Discovered Missing.Approx 55 Addl Dampers & Chase Connecting Control Complex 108 & 165 Ft Elevations Degraded Due to Incorrect Fire Rating.Caused by Personnel Error1983-07-20020 July 1983 Updated LER 83-023/01T-1:on 830613,fire Damper Discovered Missing.Approx 55 Addl Dampers & Chase Connecting Control Complex 108 & 165 Ft Elevations Degraded Due to Incorrect Fire Rating.Caused by Personnel Error 05000302/LER-1983-018, Updated LER 83-018/01T-1:on 830413,preliminary Repts Received from B&W Indicated 51 of 120 Upper Core Barrel Bolts W/Ultrasonic Flaw Indications.Caused by Intergranular Stress Corrosion Cracking.Bolts Replaced1983-07-12012 July 1983 Updated LER 83-018/01T-1:on 830413,preliminary Repts Received from B&W Indicated 51 of 120 Upper Core Barrel Bolts W/Ultrasonic Flaw Indications.Caused by Intergranular Stress Corrosion Cracking.Bolts Replaced 05000302/LER-1981-031, Updated LER 81-031/01T-1:on 810624,Henry Pratt Co Notified That Containment Purge Valves AHV-1A,1B,1C & 1D Could Fail During Loca.Cause Unknown.Valves Modified on 810701.Mods Resolved 10CFR100 Dose Rate Excess Identified on 8211982-11-15015 November 1982 Updated LER 81-031/01T-1:on 810624,Henry Pratt Co Notified That Containment Purge Valves AHV-1A,1B,1C & 1D Could Fail During Loca.Cause Unknown.Valves Modified on 810701.Mods Resolved 10CFR100 Dose Rate Excess Identified on 821101 ML20062G2891978-12-19019 December 1978 /01T-0 on 781218:during Routine Oper,Discovered That AHF-14C Was Overloaded & Was Secured to Attempt to Balance Air flow.AHF-14C Was Tripped During Restart & Cause Was Attributed to Not Allowing Sufficient Time for Restart 1997-03-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 3F1099-02, Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20211L1321999-08-31031 August 1999 EAL Basis Document 3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20211B7291999-08-16016 August 1999 Rev 2 to Cycle 11 Colr ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20210U5341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Crystal River,Unit 3 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 3F0799-01, Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With ML20210U5411999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Crystal River,Unit 3 3F0699-07, Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With ML20210U5601999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Crystal River,Unit 3 ML20195C6271999-05-28028 May 1999 Non-proprietary Rev 0 to Addendum to Topical Rept BAW-2346P, CR-3 Plant Specific MSLB Leak Rates ML20196L2031999-05-19019 May 1999 Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-04, Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With ML20210U5631999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Crystal River,Unit 3 3F0499-04, Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With ML20204D9661999-03-31031 March 1999 Non-proprietary Rev 1,Addendum a to BAW-2342, OTSG Repair Roll Qualification Rept 3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease1999-03-10010 March 1999 Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease 3F0399-03, Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With ML20203A4381999-02-0303 February 1999 Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 ML20206E9891998-12-31031 December 1998 Kissimmee Utility Authority 1998 Annual Rept ML20206E9021998-12-31031 December 1998 Florida Progress Corp 1998 Annual Rept ML20206E9701998-12-31031 December 1998 Ouc 1998 Annual Rept. with Financial Statements from Seminole Electric Cooperative,Inc 3F0199-05, Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With ML20206E9261998-12-31031 December 1998 Gainesville Regional Utilities 1998 Annual Rept 3F1298-13, Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With 3F1198-05, Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20155J2701998-10-28028 October 1998 Second Ten-Year Insp Interval Closeout Summary Rept 3F1098-06, Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With ML20206E9461998-09-30030 September 1998 Utilities Commission City of New Smyrna Beach,Fl Comprehensive Annual Financial Rept Sept 30,1998 & 1997 ML20206E9561998-09-30030 September 1998 City of Ocala Comprehensive Annual Financial Rept for Yr Ended 980930 ML20206E9101998-09-30030 September 1998 City of Bushnell Fl Comprehensive Annual Financial Rept for Fiscal Yr Ended 980930 ML20206E9811998-09-30030 September 1998 City of Tallahassee,Fl Comprehensive Annual Financial Rept for Yr Ended 980930 ML20195E3121998-09-30030 September 1998 Comprehensive Annual Financial Rept for City of Leesburg,Fl Fiscal Yr Ended 980930 3F0998-07, Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document 3F0898-02, Monthly Operating Rept for Jul 1998 for Crystal River,Unit 11998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Crystal River,Unit 1 ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept 3F0798-01, Monthly Operating Rept for June 1998 for Crystal River Unit 31998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Crystal River Unit 3 ML20236Q4611998-06-30030 June 1998 SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History 3F0698-02, Monthly Operating Rept for May 1998 for Crystal River Unit 31998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Crystal River Unit 3 1999-09-30
[Table view] |
LER-2089-013, Corrected LER 89-013-01:on 890409,when Time Delay Satisfied & Voltage Had Not Recovered,Emergency Diesel Generator Start Signal Was Initiated.Caused by Degraded Voltage on Engineered Safeguard 4,160 Volt Buses |
Event date: |
|
---|
Report date: |
|
---|
3022089013R00 - NRC Website |
|
text
_ _ _ _ _
.4 y _ ' Aes e .
- e e
3 Power COR POR ATION July 5, 1989 3F0789-03 U. S. Nuclear Regulatory Comission Attention: Mment Control Desk Washington, D. C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Licensee Event Report No. 89-13-01
Dear Sir:
i i
Florida Power Corporation's letter 3F0689-20 dated June 30, 1989 to transmit supplement one to IER 89-13 was sent without the revision lines arxi contained several other errors.
. Please disregard the June 30, 1989 supplement to IER 89-13 and replace it with the attached IER 89-13-01 supplement.
We are sorry for any inconvenience this may have caused. Should there be any questions, please contact this office.
Yours very truly, Rolf C. Widell Director, Nuclear Operations Site Support WIR: mag Enclosuru xc: Regional Administrator, Region II ,
Senior Resident Inspector pAA
) l \
G907110422 990705 PDR ADOCK 05000302 5 PDC POST OFFICE BOX 219 + CRYSTAL RIVER, FLORIDA 32629-0219 e (904) 563-2943 A Florida Progress Company
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _-. _ _ l
l l -
Nec Fwsn JE0 U.S. NUCLEA2 ikE1ULATORY COam88meON
- U8 AP8mOYED OMO teO. 3190-010e UCENSEE EVENT REPORT (LER)
- Aciury NAsse m OOCas? Nummen un rAss <ai CRYSTAL RIVER UNIT 3 o Is I o Io l o i 31012 1 loFl 0 l4
"'* Lack of: Adequate Administrative Controls Results in Overloading ES I Bus Alternate Power Supp1v_and Diesel Generator Start sveNT OATe im Lan Nuessen iaa aseO n oats m OTwan eAC L Ties siev0Lvao esa
"*fM P AC#uTV maape. DOCK 87 NuestGRt3) asONTM DAY YEAR YEA 81 aeuNn'L = neONTH DAY YEAR N/A oisgo,o;og , ;
-~ -
0l4 0l9 8 9 8l9 0l1l3 0)1 0 l7 0 l5 8l9 N/A og5l0lo,0s l l
,,,,,,,,,, THe ne,Oa7 = suenavfeo evneuANT TO THe naouiasusNTs Or is Crn 6: <ca-e -- .r aM == w nu
- i.' 5 ., .. .n ..H n.n =
= n., 0, 0 ,0
. ma n.,
n >H,
= =.in ,
= = . ,
===H.,
. m .H .
nm
_07, 37.g 3o. ass 4.Hutui es.nwt3Ho me.73w eH. WHA .insAs 30 0SI.H1HM se.734.H3Hu, go.73WGH.ellHet
.. . .EBt.Hi tM . 736.H3Hino SP.73wt3Hs)
LICSNESS CONTACT 904 THIS LER III)
NAM 8 TEi.EPHONS NURASER L. W. MNOFFATT, NUCLEAR SAFETY SUPERVISOR " " ' ' ' '
, 9 l0 14 7 l 9 l5 l 1 6 14 l8 l6 COhPLET8 ONE LING FOft (ACW COh89hENT F A8Lunt DSKRIDED IN THIS ASPOWT N3)
" ^O CAUS$ $v8 TEM COMPONENT O PA S CAU$E sy3 TIM COMPONENT "Ay' AO R8 Ajp' f ' [hh e I I I I I I I ,
I 1 i I i i b'
. s
! I I I l I l I I I I I I ( >
SUPPLSAAGNTAL REPORT EMPECTED He gAONTM DAY vtAR SUSMintON
.., ,, es,reftO su,Mt$$10N DATf1 AM H 51 l ve <ir v ]NO ,
Asef n ACT <v,~, , . . ,..-,, .N . ,, ,,-,,,,, ,,,,,,, n ., j l
On April 9,1989 Crystal River Unit 3 was in OPERATIONAL MXE 5 (COID SERJIDOWN) for repair of Reactor Coolant Pumps. Maintenance was beirg performed on the Unit 3 Start-Up Transformer. The 4160V Engineered Safeguards (ES) Buses were being supplied through an underground connection by the Unit 1 and 2 (Coal Fired Plants) Start-Up Transformer. 'Ihe voltage of the ES buses degraded to i the setpoint for actuation of the Second Level Undervoltage Relays and these '
time delay relays actuated. When the time delay was satisfied and the voltage had not recovered, an Emergency Diesel Generatcr (EGDG) start signal was )
initiated. 'Ihis is an actuation of an Engineered Safety feature ard is l therefore reportable. The voltage remained degraded long enough for the EGDG I to come up to full geed. However, the voltage did not stay degraded long l enough to require the diesel to pick up the ES Buses. Appropriate Operator l action was acocxnplished to verify automatic start of both EGDGs and to verify recovery of the ES Bus voltage to the required value. 'Ihe EGDGs were returned 1 to standby status. 'Ibe cause of the degraded voltage was an overload condition l on the Unit 1 & 2 Start-Up Transformer caused by large base loads and by loads added as starting currents. Proper administrative controls governing the !
loading of the transformer were not originally established teame> the need for '
them was not recognized by the original designer. Administrative control of the loading and alarm indication of non-availability of the transformer has been established. l N
C,,.
l F
l a.p ,.un mesa u s nuctsaa KsoutAton cowusssion l
LICENSEE EVENT REPORT 'LER) TEXT CONTINUATION maovio ous =o mo-oio4 l EXPimte s/31/95 8 ACluTV NAME 11s DOCKlf NUMBEfl (2)
YEam 88 0W8 NT : -*8 * *'ON CRYSTAL RIVER UNIT 3 o l5 l0 j o l0 l3 l 0l 2 8 [9 -
0 l1 l 3 -
0 l1 0 l2 or 0 l4 TEXT (# snee apose a sagesred, ese adelmonef N#C Fonn Jesrat im EVENT IFE4RIPTIOJ:
On April 9,1989 Crystal River Unit 3 was in OPERATIQaL PODE: 5 (ODID SEUIDOWN) for repair of Reactor Coolant PLmps [AB,P]. Maintenance was being performed on the Unit 3 Start-Up Transformer [EA,XFMR]. 'Ihe 4160V Engineered Safeguards (ES) Buses [EB,BU] were being supplied through an uMerground connection by the Unit 1 (Coal Fired Plant) 4160V buses. At 2349 the voltage of the ES buses degraded to the setpoint for actuation of the Second IcVel Undervoltage Relays
[EB,2] (SWRS) aM the time delay relays actuated. When the time delay was satisfied (5 sec) and the voltage had not recovered above the 95% SLUR setpoint, an Emergency Diesel Generator [EK,DG] (EGD3) engine start signal was initiated. 'Ihe voltage ruminM degraded for greater than 10 seconds which was long enough for both of tm OGDGs to come up to full speed. However, the voltage did not stay degraded long enough,18 seconds, to require stripping of the ES Buses in preparation for placing them on the EGDG. Appwsiate Operator action was accomplished to verify autctnatic start of both EDGs and to verify recovery of the ES Bus voltage to the required value. Both EGris were returned to staMby condition.
CAUSE:
'Ihe cause of the autanatic start of the EGIXss was a degraded voltage on the ES 4160v buses for a period of time sufficient for the Second Isvel Undervoltage Relays to initiate a diesel start signal. 'Ihe cause of the degraded voltage was an overload candition on the primary alternate offsite power source due to the lack of adequate administrative controls to assure reliability of the power source. 'Ihe administrative controls were not in place because the original design failed to consider starting currents in the loading scheme of the transformer. With the transformer loaded to greater than 1.5 Million Volt Amps (MVA) on the X winding, it does not have sufficient capacity to hanile the starting loads of Unit 3 Engineered Safeguards equipment.
EVENP NRIESIjS Crystal River Unit 3 uses power from the Unit 1 and 2 Start-Up Transformer .
(S/UX) as an alternate offsite source of power to the 4160v Engineered I Safeguards Buses. Units 1 & 2 are adjacent to Unit 3 and the Unit 1 & 2 S/UX is supplied from the 230 KV switchyard. 'Iho S/UX has two secoMary windings referred to as "X" and "Y" . 'Ihe alternate offsite power source for Unit 3 4160v ES Buses is the "X" wiMing of the Unit 1 & 2 S/UX. 'Ihe normal offsite power source to the ES Buses is the Unit 3 S/UX supplied directly from the 230kv switchyard. 'Ihat power source was not available because maintenance was being performed on the Unit 3 S/UX. Unit 2 was on line at full power while Urdt 1 was starting up. When the boiler feed pump at Unit 1, which is a 3500 Hp motor, was started, the Unit 1 and 2 S/UX was not able to supply all the required power without a significant voltage decrease. Voltage, as measured at the Unit 3 4160v ES buses, decreased from 4200v to 3680v instantaneously. With the approximately 500v decrease, the protective circuits on the ES buses were g ,o. m
t.
7*.c **,. me. u a =vettaa snoutaron, co==issio.s LICENSEE EVENT REPORT (LER) TEXT CONTINUATION *eeaoveo ous =o mo-mo.
.. soiaes een eacaLov =ame H) DOCKET sevasten m .
- YJI=U CRYSTAL RIVER UNIT 3 0151010 l0 l 3 J Ol 2 8 l9 0l1l3 011 0 l3 or O ' l4 actuated and a time delay relay was started. It should be noted that the safeguards w h ul centers starters have been specified to hold in down to 65%
- of rated voltage for 'a period of two (2) seconds. None of the safeguards equdpnent was lost in this event.
When the Unit 3 Final Safety Analysis Report (ESAR) was prepared prior to zuceipt of a license, certain conditions were aaai-d which allowed us to specify that the Unit 1 & 2 S/UX was capable of supplying the pamaaaary power -
(6.59 MVA) for Unit 3 ES loads. '1his a=== tion was stated in Qiapter 8 "gECIRICAL SYSTENS" Section 8.2.3 " SOURCES OF AUXILTARY IWER" Dages 8-17 through 8-27. 'Ihis assunption was apparently based on the steady state condition of Unit 2 operating, Unit 1 starting up, and Unit 3 in an er wfacy condition with its ES. loads already loaded on the Unit l' & 2 Start-Up Transformer. Included in the a==ntion was a stipulation that. the Unit 1 and 2 S/UX was to be carrying one fully loaded (6.65 MVA) bus, Bus 2B, frun Unit 2 and one 70% loaded (3.54 MVA) bus (Bus 1B) frcan Unit 1.
In 1985 analyses were performed which showed that it was undesirable to allow voltage to drop to significantly less than 95% of nominal voltage at the ES 4160v Buses. For that reason, Second Isvel Undervoltage Relaying (SWRs) was installed on the Unit 3 4160v ES Naan. 'Ibe SWRs are time delayed relays.
'Ibe installation of SERs put a limit of acceptability of 95% of nominal voltage on tha ES Buses which had not been there before. 'Ibe time delay relay's function is to allow same slight and temporary voltage fluctuations without innadiately starting the EDGs. Many unr ary EDG starts are avoided by allowing a few seconds time for the voltage to recover before initiatinJ a start of an EGDG. Evidently, the expected voltage drop under the conditions a=_=d in the ISAR was not considered in the design process for the SWRs.
On the date of this event, the loads on the ES Buses totaled approximately 1670 KW ( 1.8 MVA) which, because there was no sinai f - ucy condition, is far below the FSAR a==d ES loads of 5930 Kw (6.59 MVA) . Unit 2 was operating and Unit 1 was performing a start-up which required the start of a boiler feed punp l motor (3500 Hp) . However, four (4) buses, 1A, 1B, Start-Up mm A, and B, instead of two, were being carried on the Unit 1 & 2 S/UX. 'Ihe "Y" winding was carrying buses 1B and Start 47p Bus B and any loads on those buses contributed )
to the load on the transformer. Because buses 1A and Start-Up Bus A were wisected to the "X" winding of the S/UX in parallel with Unit 3 ES Buses, they also contributed to causing the S/UX to overload when the Unit 1 boiler feed punp was started. This overloading resulted in a significant voltage drop at the 4160v ES buses at Unit 3 even without full ES loads being on the Unit 3 ES .
Buses. Consequently, when Unit 3 ms depeMwit on the power supply frun Units ;
1 & 2 Start-Up Transformer, in was fattnd to be inadelate. >
. ee .
o 4 38 i
gao =.
"' -p.s., u =vetian noutaf ow co==in,o=
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION amovio ous =o mo-oso. !
. ' E s ping s 3 /31 g paceteTV mAmes its DOCu tY NvMSER (28 Lim NuMet A fel Pact 131 ygan st ovemh A6 afveon CRYSTAL RIVER UNIT 3 Yuw ,,, . = ,, .se , , mi. ,m,,
015 l o 10 l o 13 l 012 8l9 -
0j1l3 -
0j1 0 l4 OF 0 [4 q i
Fower to the ES buses was always available. There was no decrease in the -l margin of safety for the public caused by this event. None of the safety i functions of plant equipnent were cxmprmM. All in-plant equipnent functioned as designed and all plant s uc.siures were adequate for the situation. All actions by the operators were proper and timely. If this event j had occurred subsequent to an ES actuation there could have been scane inpact on j the amount of time required to supply High Pressure Injection [BQ) (HPI) water 1 to the reactor core. The delay of HPI would have been a maximum of 28 seconds beyond the ===A delay of 25 seconds for water to reach the core fcllowiJg an HFI Engineered Safeguards actuation. A reanalysis to determine the thermal-hydraulic effects has shown there would not be any significance to a total delay time of 53 seconds instead of 25 seconds for HPI water to enter the core.
umenA:nVE AcrRN:
The systems functioned as they were supposed to when a degraded voltage situation occurs. The Dnargency Diesel Generators were returned to standby status after verifying the ES buses were being properly supplied. No corrective action is required for responding systems /u.aupvimuis. Corrective actions include agreement between the Directors of the Nuclear arx1 Fossil Units as to actions required when the Unit 1 & 2 Start-Up Transformer is cuerloaded. This agreement has been issued to the operating shifts as a Memorandum of Understanding and prwides the appropriate administrative controls to assure that this transformer is not relied upon as a Technical Specification offsite power supply when its configuration will not provide sufficient capacity. An annunciator alarm has been added to the Main Control Board to provide notification to the Nuclear Operator that the Unit 1 and 2 Start-up transformer is loaded to greater than 1.5 Hva. An analysis of the ,!
impact of sequential occurrence of an ES actuation followed by a degraded voltage condition on the ES buses has been performed usiry Thermal-Hydraulic analysis.
PRFNIGJS EVINTS:
An urplanned start of an EGDG has previously occurred seven times in the 12 year operating history of the plant. 2he last event was reported in IER 87-007. This event is the first time the diesel las started due to actual degraded voltage conditions. All other events were either start circuitry problems or total loss of voltage situations. There have not been any observed occurrences of overloading the Start-Up Transformer.
l .ec .... m.
l T5 - _ _ _ _ _ . _ _ _ _ _ _
|
---|
|
|
| | Reporting criterion |
---|
05000302/LER-1989-008, Forwards LER 89-008-01 & Proposed Draft FSAR Change. Reanalysis in LER Initiated to Evaluate Consequences of Operation W/Steam Drain Trap Isolation Valves Open for All Events.Revised FSAR Pages Will Be Incorporated in Rev 12 | Forwards LER 89-008-01 & Proposed Draft FSAR Change. Reanalysis in LER Initiated to Evaluate Consequences of Operation W/Steam Drain Trap Isolation Valves Open for All Events.Revised FSAR Pages Will Be Incorporated in Rev 12 | | 05000302/LER-1989-009, Submits Justification for Restart of Plant as Committed to in LER 89-009.Based on Test & Insp Data,Util Has Determined That Continued Operation W/Existing DHR Pumps Will Not Pose Unresolved Safety Concerns | Submits Justification for Restart of Plant as Committed to in LER 89-009.Based on Test & Insp Data,Util Has Determined That Continued Operation W/Existing DHR Pumps Will Not Pose Unresolved Safety Concerns | | 05000302/LER-1989-013, Corrected LER 89-013-01:on 890409,when Time Delay Satisfied & Voltage Had Not Recovered,Emergency Diesel Generator Start Signal Was Initiated.Caused by Degraded Voltage on Engineered Safeguard 4,160 Volt Buses | Corrected LER 89-013-01:on 890409,when Time Delay Satisfied & Voltage Had Not Recovered,Emergency Diesel Generator Start Signal Was Initiated.Caused by Degraded Voltage on Engineered Safeguard 4,160 Volt Buses | | 05000302/LER-1989-016, Advises That LER-89-016 Re Environ Qualification Items Delayed Until 890630.Several Addl Items Identified & Being Incorporated | Advises That LER-89-016 Re Environ Qualification Items Delayed Until 890630.Several Addl Items Identified & Being Incorporated | |
|