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| {{#Wiki_filter:REGULATORY AFORMATION DISTRIBUTION SY~EM (RIDS)ACCESSION NBR: 8707310295 DOC.DATE: 87/07/29 NOTARIZED: | | {{#Wiki_filter:REGULATORY AFORMATION DISTRIBUTION SY ~EM (RIDS) |
| NO DOCKET 0 FACIL: 50-250 Turkeg Point Planti Unit 3>Florida Poujer and Light C 05000250 AUTH.NAME AUTHOR AFFILIATION WAGER'.Florida Power&Light Co.WOODYi C.O..Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION | | ACCESSION NBR: 8707310295 DOC. DATE: 87/07/29 NOTARIZED: NO DOCKET 0 FACIL: 50-250 Turkeg Point Planti Unit 3> Florida Poujer and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION WAGER'. Florida Power & Light Co. |
| | WOODYi C. O.. |
| | RECIP. NAME Florida Power & Light Co. |
| | RECIPIENT AFFILIATION |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 87-021-00: | | LER 87-021-00: on 870701i auto safety inJection initiated fr om spurious containment high pressure signal. Nitrogen supply valve manipulated to verify closed causing pressure spike thus actuating Train A. Test seitch replaced. W/87072'9 ltr. |
| on 870701i auto safety inJection initiated fr om spurious containment high pressure signal.Nitrogen supply valve manipulated to verify closed causing pressure spike thus actuating Train A.Test seitch replaced.W/87072'9 ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR i ENCL i SIZE: TITLE: 50.73 Licensee Event Report (LER)i Incident Rpti etc.NOTES: REC IP IENT ID CODE/NAME PD2-2 LA McDONALDI D INTERNAL: ACRS MICHELSON AEOD/DO*AEOD/DSP/ROAB DEDRO NRR/DEST/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEST/PSB NRR/DEST/SGB NRR/DLPG/GAB NRR/DREP/RAB NRR/PMAS/ILRB QEG=Pg~02 RES 4lELFORDi J RGN2 FILE 01 EXTERNAL: EG&G GROHz M LPDR NSIC HARRIS'COPIES LTTR ENCL 1 1 1 1 1 1 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 5 1 1'1 1 RECIPIENT ID CODE/NAME PD2-2 PD ACRS MOELLER*EOD/DSP/NAS AEOD/DSP/TPAB NRR/DEST/ADE NRR/DEBT/CEB NRR/DEST/I CSB NRR/DEST/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RPB NRR/PMAS/PTSB RES DEPY GI RES/DE/EIB H ST LOBBY WARD NRC PDR NSIC MAYST G COPIES LTTR ENCL 1 2 2 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 43 NRC Forn~355 (983 I LtCENSEE EVENT REPORT (LER)U.S.NUCLEAII REGULATOR Y COMMISSION APPROVED OMB NO.31500105 EXPIRES: 4/31/44 FACILITY NAME (II Turke Point Unit 3 DOCKET NUMBER (2)0 5 0 0 0 PA 1 OF TI'TLE MI Train A Safeguards Actuation due to Containment High Pressure Signal EVENT DATE (SI MONTH OAY YEAR YEAR LER NUMBER (SI 55QVCNTIAL NVMSER R5VrsrQN NVMSER MONTH DAY YEAR'EPORT DATE (7)N/A FAC/LITY NAMES OOCKFT NUMBER(SI o s 0 o o OTHER FACILITIES INVOLVED (SI 07 018 8 7 0 2 1 0 0 07 29 8 7 N/A 0 5 0 0 0 OPERATINO MODE (4)POWER LEY EL 0 0'a+jet: 4~')'/o',",'0.402(5) 20AOS(~Ill~)IB 20l05(aHI IIE)20A05(s)(1)((5)20.405(s)l1)0 I 20.405(a)l1)(r)20.405(c)SOM(c)(I)50M(c)(21 50,73(a I (2)Ill 50.73(sl(2)(ii)50.73(sl(2) | | DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR i ENCL i SIZE: |
| (5/I LICENSEE CONTACT FOR THIS LER (12)50.734)(2)(hl 50.734)(2)(rl 50.734)(2)(rBI 50.73(a I (2)l r(II)(A)50.73(sl(2)(r(dl(B)50.73(~)l2)(x)THIS REPORT IS SUBMITTED PURSVANT T 0 THE REQUIREMENTS OF 10 CFR gt/Crrocn ons or mao of tns fo//ort/nt/
| | TITLE: 50. 73 Licensee Event Report (LER)i Incident Rpti etc. |
| l11 73.7((5)73.71(c)Q7HEII fspsc/fy in Aortrsct/rs/ow and/n Tsxt HRC Form 388lf NAME Virgil Wager TELEPHONE NUMBER AREA CODE 3 5 246-6 76 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TVRER EPDATASL~'~$$+$5 CAUSE YkÃ4)r(Fo'I SYSTEM COMPONENT MANUFAC.TVRER EPORTABLE TO NPRDS)~4)'~i%(ÃR SUPPLEMENTAL REPORT EXPECTED (Iol FXPECTED SU 5 M I SS IO N DATE II SI MONTH OAY YEAR YES fif ym, COmp/ttt EXPECTED Si/Ett/$$/OH DATE/NO ABSTRACT fLim/t to to00 tpocst,/o., approx/moto/y fi/toon t/no/oopsco typorrritton
| | NOTES: |
| //nN/(14)On July 1, 1987, at 0148, while Unit 3 was at cold shutdown (Mode 5)an auto safety injection was initiated from a spurious Containment High Pressure signal.The electrical department required a hose to test the penetration canisters on Unit 4 which was in hot standby (Mode 3).They borrowed a pressure rig on Unit 3 that was to be utilized for initiating a Containment High Pressure signal for Safeguards testing.The nitrogen supply valve to the pressure rig was opened in the process of verifying it was closed, thereby causing a Containment High Pressure signal.This resulted in an actuation of the ESFs All equipment lined up for operation on Train A functioned normally.Train B did not receive an actuation signal.Safety injection is not required to be operable in Mode 5.The normal'eat sink (RHR)was not lost during the event since there was no loss of offsite power.Also, there was no safety injection flow to the reactor since MOV 3-843 A and B, and MOV 3-869 were tagged closed on the cold shutdown clearance.The unit was returned to the normal configuration for Mode 5 at 0155.8707310295 870729 PDR ADOCK 05000250 S PDR NRC Form 345 (943)
| | REC IP IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 McDONALDI D 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DO* 1 *EOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 DEDRO 1 1 NRR/DEST/ADE 1 0 NRR/DEST/ADS 1 0 NRR/DEBT/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ I CSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 NRR/PMAS/ILRB 1 1 NRR/PMAS/PTSB 1 1 QEG=Pg~ 02 1 RES DEPY GI 1 RES 4lELFORDi J 1 1 RES/DE/EIB 1 1 RGN2 FILE 01 1 EXTERNAL: EG&G GROHz M 5 5 H ST LOBBY WARD LPDR 1 1 NRC PDR NSIC HARRIS' '1 1 NSIC MAYST G TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 43 |
| I!RC Form rr38A (9831 LICENSEE EVENT EPORT{LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OM8 NO.3150M104 EXPIRES'/31/88 FACILITY NAME (11 Turkey Point Unit 3 OOCKET NUMBER (2(LER NUMBER (8(YEAR'4M SEQUENTIAL-i%%!REVISION igS NUMSER 9"N NUMEER PAGE (3)Tm(T/O'RNoo<<Moo is/o9uoed, INo aAtdonal HRC Furr/I 3////A'4/(17(0 5 0 0 0 2 5 0 87-0 21 0 0 0 2 or-0 3 EVENT On July 1, 1987, at 0148 , while Unit 3 was in cold shutdown (Mode 5)and Unit 4 was in hot shutdown (Mode 3), a spurious Containment High Pressure signal actuated Safety Injection and Phase A Containment Isolation on Unit 3.The safety injection components and Phase A containment isolation valves that were lined up for operation on Train A functioned normally.The A Emergency Diesel Generator did not start because it was out of service for governor maintenance. | | |
| The Train B safety injection components and containment isolation valves did not operate and the B Emergency Diesel Generator did not start because Train B did not receive an actuation signal.The normal heat sink (RHR)was not lost during the event as there was no loss of offsite power.There was no safety injection flow to the reactor as MOV 3-843 A&B and MOV 3-869 were tagged closed on the cold shutdown clearance.
| | NRC Forn~ 355 U.S. NUCLEAII REGULATOR Y COMMISSION (983 I APPROVED OMB NO. 31500105 LtCENSEE EVENT REPORT (LER) EXPIRES: 4/31/44 FACILITY NAME (II DOCKET NUMBER (2) PA Turke Point Unit 3 0 5 0 0 0 1 OF TI'TLE MI Train A Safeguards Actuation due to Containment High Pressure Signal EVENT DATE (SI LER NUMBER (SI DATE (7) OTHER FACILITIES INVOLVED (SI MONTH OAY YEAR YEAR 55QVCNTIAL R5VrsrQN MONTH DAY YEAR'EPORT FAC/LITY NAMES OOCKFT NUMBER(SI NVMSER NVMSER Ill N/A o s 0 o o 07 018 8 7 0 2 1 0 0 07 29 8 7 N/A 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSVANT T 0 THE REQUIREMENTS OF 10 CFR gt /Crrocn ons or mao of tns fo//ort/nt/ l11 OPERATINO MODE (4) 20.405(c) 50.734) (2) (hl 73.7((5) |
| At 0155, the operators entered the appropriate Emergency Operating Procedures; 3-EOP-E-O, Reactor Trip or Safety Injection and 3-EOP-ES-1.1, Safety Injection Termination, and returned the unit to normal configuration for Mode 5.CAUSE OF EVENT The Electrical Department needed to connect a hose to the plant nitrogen system and the penetration cannisters on Unit 4 for a pressure test.They borrowed an I&C pressure rig from Unit 3 that was going to be utilized for initiating a Containment High Pressure signal for the Integrated Safeguards Test.There were no tags of any kind on the nitrogen supply valve or hose that would have prohibited removal of the rig.Before disconnecting the hose, the nitrogen supply valve was manipulated to verify it was closed thereby causing a pressure spike greater than 4 psig on Channels I and III which actuated Train A of the ESF.Test switch S-23 (PC-456D)which simulates a Pressurizer Safety Injection signal was mechanically faulty and had been disconnected in conformance with an I&C Plant Work Order.The negative terminal (J-2)of the switch had two leads one of which completed the negative side of the DC circuit for the safety injection signal to Train B.A replacement switch which had to be ordered, had not been installed at the time of the event.The open DC circuit precluded the actuation of Train B Safety Injection.
| | POWER 20AOS( ~ )IB SOM(c) (I) 50.734) (2) (rl 73.71(c) |
| NRC FORM 3ESA (94(31 o U.S.GPO:(988.0 824 538/455 N':IC Form SSSA (94)3)LICENSEE EVENT R PORT (LER)TEXT CONTINUATION U.S, NUCLEAR REOULATORY COMMISSION APPROVEO OMB NO.3150&104 EXPIRES: 8/31/88 FACILITY, NAME l1)OOCKET NUMBER (2)YEAR LER NUMBER (8)SEOVSNTIAL NVMSSR REVISION NVMSSR PACE (3)Turkey Point Unit 3 TS/T//PM/o FPSrrF/4'/rrSod, INo rrSWcnal HRC For/II 3854'4/l (T)o s o o o 2 5 0 8 7 0 2 1 00 03 DF0 3 ANALYSIS OF EVENT At the time of the event Unit 3 was in Cold Shutdown (Mode 5).Safety Infection and Containment Isolation are not required to be operable in Mode 5.However, the requirements for ESF equipment response to a safety injection signal depends on the status of the equipment.
| | LEY EL ~')'/o',",'0.402(5) 0 0 20l05(aHI IIE) 50M(c) (21 50.734)(2)(rBI Q7HEII fspsc/fy in Aortrsct |
| Certain valves and equipment were out of service under the cold shutdown clearance and various maintenance clearances. | | /rs/ow and/n Tsxt HRC Form |
| But all equipment that was lined up for operation on Train A functioned normally upon receipt of the SI signal.Based on the above the health and safety of the public were not affected.CORRECTIVE ACTIONS 1)The replacement for test switch (S-23)has been received and the I&C Department installed it on 7-2-87.2)The operators returned Unit 3 to the normal configuration for Mode 5 utilizing EOP-E-O, Reactor Trip or Safety Injection and EOP-ES-1.1, Safety Injection Termination. | | 'a+jet: 4 20A05(s) (1)((5) 50,73(a I (2) Ill 50.73(a I (2) l r(II)(A) 388lf 20.405(s) l1) 0 I 50.73(sl(2) (ii) 50.73(sl(2) (r(dl(B) 20.405(a)l1) (r) 50.73(sl(2) (5/I 50.73( ~ ) l2)(x) |
| 3)The Engineered Safeguards Integrated Test procedure will be changed to provide for additional protection to avoid inadvertent initiation of the ESF components. | | LICENSEE CONTACT FOR THIS LER (12) |
| Section 7.1.11 of the procedure will have a step added to require the placement of caution tags on the source connection that provides the test signal to the pressure switches.ADDITIONAL DETAILS The original test switch (S-23)was supplied by the'EES company.However, the specific model had been discontinued and a different model manufactured by REES, had to be ordered and approved for replacement. | | NAME TELEPHONE NUMBER Virgil Wager AREA CODE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) 3 5 246 -6 76 CAUSE SYSTEM COMPONENT MANUFAC. |
| Similar Occurrences: | | TVRER EPDATASL ~ '~$ |
| none NRC FORM SSSA (94)3)o U S GPO'1986 0.824 538/455 P.O.BOX 1 JUNO BEACH, FL 33408.0420 JULy'Ivy~L-87-3 I 7 IO CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gen t I emen: Re: Turkey Point Unit 3 Docket No.,50-250 Reportable Event: 87-2 I Date of Event: July I, l987 Train A Safeguards Actuation, Due To Containment Hi h Pressure Si nal The attached Licensee Event Report is being submitted pursuant to the requirements of IO CFR 50.73 to provide notification of the subject event.Very truly yours, C.0.ody Group Vice President Nuc I ear Energy COW/SDF/pm At tachment cc: Dr.J.Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant, SDF I/0O5/I an FPL Group company}} | | $+$ 5 CAUSE SYSTEM COMPONENT MANUFAC. |
| | TVRER EPORTABLE TO NPRDS YkÃ4)r(Fo'I )~4)'~i%(ÃR SUPPLEMENTAL REPORT EXPECTED (Iol MONTH OAY YEAR FXPECTED SU 5 M I SS IO N DATE II SI YES fifym, COmp/ttt EXPECTED Si/Ett/$ $ /OH DATE/ NO ABSTRACT fLim/t to to00 tpocst, /o., approx/moto/y fi/toon t/no/oopsco typorrritton //nN/ (14) |
| | On July 1, 1987, at 0148, while Unit 3 was at cold shutdown safety injection was initiated from a spurious (Mode 5) an auto The electrical department required a hose Containment High Pressure signal. |
| | to test the penetration canisters on Unit 4 which was in hot standby (Mode 3 a pressure rig on Unit 3 that was to be ). They borrowed a Containment High Pressure signal for utilized for initiating supply valve to the pressure rig was opened in the testing. |
| | Safeguards The nitrogen closed, thereby causing a Containment High Pressure process of verifying it was actuation of the ESFs All equipment lined up for operation signal. This resulted in an normally. Train B did not receive an actuation signal. on Train A functioned is not required to be operable in Mode 5. The normal'eat sink Safety injection not lost during the event since there was no loss (RHR) was Also, there was no safety injection flow to the reactor since of offsite power. |
| | MOV 3-843 A and B, and MOV 3- 869 were tagged closed on the cold shutdown clearance . The unit was returned to the normal configuration for at 0155. Mode 5 8707310295 870729 PDR ADOCK 05000250 S PDR NRC Form 345 (943) |
| | |
| | I!RC Form rr38A U.S. NUCLEAR REGULATORY COMMISSION (9831 LICENSEE EVENT EPORT {LER) TEXT CONTINUATION APPROVEO OM8 NO. 3150M104 EXPIRES'/31/88 FACILITY NAME (11 OOCKET NUMBER (2( LER NUMBER (8( PAGE (3) |
| | YEAR '4M SEQUENTIAL -i%%! REVISION Turkey Point Unit 3 igS NUMSER 9"N NUMEER 0 5 0 0 0 2 5 0 87 0 21 0 0 0 2 or- 0 3 Tm(T /O'RNoo <<Moo is /o9uoed, INo aAtdonal HRC Furr/I 3////A'4/ (17( |
| | EVENT On July 1, 1987, at 0148 , while Unit 3 was in cold shutdown (Mode 5) and Unit 4 was in hot shutdown (Mode 3), a spurious Containment High Pressure signal actuated Safety Injection and Phase A Containment Isolation on Unit 3. The safety injection components and Phase A containment isolation valves that were lined up for operation on Train A functioned normally. The A Emergency Diesel Generator did not start because it was out of service for governor maintenance. The Train B safety injection components and containment isolation valves did not operate and the B Emergency Diesel Generator did not start because Train B did not receive an actuation signal. The normal heat sink (RHR) was not lost during the event as there was no loss of offsite power. There was no safety injection flow to the reactor as MOV 3-843 A&B and MOV 3-869 were tagged closed on the cold shutdown clearance. At 0155, the operators entered the appropriate Emergency Operating Procedures; 3-EOP-E-O, Reactor Trip or Safety Injection and 3-EOP-ES-1.1, Safety Injection Termination, and returned the unit to normal configuration for Mode 5. |
| | CAUSE OF EVENT The Electrical Department needed to connect a hose to the plant nitrogen system and the penetration cannisters on Unit 4 for a pressure test. |
| | They borrowed an I&C pressure rig from Unit 3 that was going to be utilized for initiating a Containment High Pressure signal for the Integrated Safeguards Test. There were no tags of any kind on the nitrogen supply valve or hose that would have prohibited removal of the rig. Before disconnecting the hose, the nitrogen supply valve was manipulated to verify it was closed thereby causing a pressure spike greater than 4 psig on Channels I and III which actuated Train A of the ESF. |
| | Test switch S-23 (PC-456D) which simulates a Pressurizer Safety Injection signal was mechanically faulty and had been disconnected in conformance with an I&C Plant Work Order. The negative terminal (J-2) of the switch had two leads one of which completed the negative side of the DC circuit for the safety injection signal to Train B. A replacement switch which had to be ordered, had not been installed at the time of the event. The open DC circuit precluded the actuation of Train B Safety Injection. |
| | NRC FORM 3ESA o U.S.GPO:(988.0 824 538/455 (94(31 |
| | |
| | N':IC Form SSSA U.S, NUCLEAR REOULATORY COMMISSION (94)3) |
| | LICENSEE EVENT R PORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3150&104 EXPIRES: 8/31/88 FACILITY,NAME l1) OOCKET NUMBER (2) |
| | LER NUMBER (8) PACE (3) |
| | YEAR SEOVSNTIAL REVISION Turkey Point Unit 3 NVMSSR NVMSSR TS/T //PM/o FPSrrF /4 '/rrSod, INo rrSWcnal HRC For/II 3854'4/ l (T) o s o o o 2 5 0 8 7 0 2 1 00 03 DF0 3 ANALYSIS OF EVENT At the time of the event Unit 3 was in Cold Shutdown (Mode 5). Safety Infection and Containment Isolation are not required to be operable in Mode 5. However, the requirements for ESF equipment response to a safety injection signal depends on the status of the equipment. Certain valves and equipment were out of service under the cold shutdown clearance and various maintenance clearances. But all equipment that was lined up for operation on Train A functioned normally upon receipt of the SI signal. |
| | Based on the above the health and safety of the public were not affected. |
| | CORRECTIVE ACTIONS |
| | : 1) The replacement for test switch (S-23) has been received and the I&C Department installed it on 7-2-87. |
| | : 2) The operators returned Unit 3 to the normal configuration for Mode 5 utilizing EOP-E-O, Reactor Trip or Safety Injection and EOP-ES-1.1, Safety Injection Termination. |
| | : 3) The Engineered Safeguards Integrated Test procedure will be changed to provide for additional protection to avoid inadvertent initiation of the ESF components. Section 7.1.11 of the procedure will have a step added to require the placement of caution tags on the source connection that provides the test signal to the pressure switches. |
| | ADDITIONAL DETAILS The original test switch (S-23) was supplied by the'EES company. |
| | However, the specific model had been discontinued and a different model manufactured by REES, had to be ordered and approved for replacement. |
| | Similar Occurrences: none NRC FORM SSSA o U S GPO'1986 0.824 538/455 (94)3) |
| | |
| | P. O. BOX 1 JUNO BEACH, FL 33408.0420 |
| | ' Ivy ~ |
| | JULy L-87-3 I 7 IO CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gen t I emen: |
| | Re: Turkey Point Unit 3 Docket No.,50-250 Reportable Event: 87-2 I Date of Event: July I, l987 Train A Safeguards Actuation, Due To Containment Hi h Pressure Si nal The attached Licensee Event Report is being submitted pursuant to the requirements of IO CFR 50.73 to provide notification of the subject event. |
| | Very truly yours, C. 0. ody Group Vice President Nuc I ear Energy COW/SDF /pm Attachment cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant, an FPL Group company SDF I/0O5/I}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17355A3891999-07-20020 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 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 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 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 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 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 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 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 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 ML17354A6121997-08-29029 August 1997 LER 97-007-00:on 970730,automatic Reactor Trip Occurred. Caused by Closure of B Main Steam Isolation Valve.Failed W Relay & Equivalent Relays Were replaced.W/970829 Ltr ML17354A6081997-08-18018 August 1997 LER 97-006-00:on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power cabinets.W/970818 Ltr ML17354A5801997-07-14014 July 1997 LER 97-005-00:on 970618,RCP Oil Collection Sys Was Found Outside Design Basis.Caused Because Design Did Not Consider Component Parts to Be Potential Leakage Sources.Entire RCP Oil Collection Sys Was reviewed.W/970714 Ltr ML17354A5141997-05-22022 May 1997 LER 97-002-00:on 970423,automatic Reactor Tripped.Caused by Actuation of Turbine Overspeed Protection Circuit. Administrative Procedures Governing Inadequate Work Controls Will Be Revised to Capture Lessons learned.W/970522 Ltr ML17354A5061997-05-0909 May 1997 LER 97-003-00:on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in drain.W/970509 Ltr ML17354A5051997-05-0909 May 1997 LER 97-004-00:on 970411,auxiliary Feedwater Automatic Start Upon Trip of All Main Feedwater Pumps,Occurred.Caused by Mispositioned Valve Closing.Valves Listed as Inappropriately Positioned Were repositioned.W/970509 Ltr ML17354A4781997-04-25025 April 1997 LER 97-001-00:on 970327,ECCS Recirculation Loop Leakage Was Found to Be in Condition Outside Design Basis Due to Gasket Movement During Installation During Spring 1966 Reassembly. Gasket Replaced & Pump tested.W/970425 Ltr ML17354A4581997-03-28028 March 1997 LER 97-002-00:on 970303,manual Reactor Trip Following Rod Control Urgent Failure Alarm Occurred.Caused by Phase Failure Detection on Stationary a Circuits of 2BD Rod Control Cabinet.Air Conditioning replaced.W/970328 Ltr ML17354A4511997-03-26026 March 1997 LER 97-001-00:on 970118,missed Surveillance on CR Position Verification Occurred Due to Inoperable Rod Deviation Monitor.Faulty Circuit Common Connection Was Corrected & Rdm Operability Was restored.W/970326 Ltr ML17354A4061997-02-0303 February 1997 LER 96-004-03:on 970107,identified Three Instances of Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Surveillance Procedures Revised ML17354A3771996-12-27027 December 1996 LER 96-012-00:on 961204,determined Containment Average Temp Being Determined Based on Only Two Temp Elements Instead of Three as Required by Tss.Caused by Log Only Requiring One Entry.Log revised.W/961227 Ltr ML17354A3261996-11-0606 November 1996 LER 96-011-00:on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures revised.W/961106 Ltr ML17354A3071996-10-22022 October 1996 LER 96-010-00:on 960924,manual Reactor Shutdown Occurred. Caused by Failed Rod Control Sys Regulation Card in 2AC Power cabinet.2AC Power Cabinet DC Power Supplies,Cabling & Connectors checked.W/961022 Ltr ML17353A8711996-08-27027 August 1996 LER 96-009-00:on 960729,failed to Reflect Heavy Load Design Info in Procedural Controls.Caused by Failure to Incorporate 1982 Procedure Changes.Suspended Lifting of Heavy Loads & Took Turbine Bldg Crane OOS.W/960827 Ltr ML17353A7411996-06-18018 June 1996 LER 96-008-00:on 960521,surveillance Method for Testing Emergency Diesel Generators (EDG) Determined Inadequate. Caused by Personnel Error.All Four EDGs Rapid Start Tested & EDG Surveillance Procedures modified.W/960618 Ltr ML17353A7401996-06-18018 June 1996 LER 96-004-02:on 960524,identified Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Entered Tech Spec Statements,Tested Required Instruments Functions & Revised Plant procedure.W/960618 Ltr ML17353A6901996-05-13013 May 1996 LER 96-004-01:on 960220,identified Potential Tech Spec non-compliance Associated W/Surveillance Testing of AFW Actuation Circuitry on Sg.Caused by Inadequate Surveillance Procedures.Procedures revised.W/960513 Ltr ML17353A6741996-05-0606 May 1996 LER 96-001-00:on 960409,manual Rt Occurred Due to Turbine Governer Control Oil Perturbation.Disassembled & Inspected Governor Valve for Cleanliness & Corrosion products.W/960506 Ltr ML17353A6651996-04-29029 April 1996 LER 96-007-00:on 960329,inadvertent ESF Actuation Occurred During Refueling Outage Due to Cognitive Personnel Error. Personnel Involved Counseled & Integrated Safeguards Test Procedures Being revised.W/960429 Ltr ML17353A6601996-04-25025 April 1996 LER 96-006-00:on 960327,manual Rt Occurred Due to 3C Transformer Lockout & Loss of 3B SG Mfp.Replaced SAM Timer Relay in 3AC16.W/960425 Ltr ML17353A6491996-04-23023 April 1996 LER 96-005-00:on 960326,certain Safety Injection Accumulator Filled Evolutions Resulted in cross-tied Configuration.C/A: Night Order Written & Operations Procedure 3/4-OP-064 revised.W/960423 Ltr ML17353A6051996-03-18018 March 1996 LER 96-003-00:on 960222,two Arpi Inoperable & TS 3.0.3 Entered.Proposed License Amend Submitted to Revise Allowed Misalignment from +/-12 Steps to =/-18 Steps Between Arpi & Dpi at Less than 90% power.W/960318 Ltr ML17353A6041996-03-18018 March 1996 LER 96-004-00:on 960220,surveillance Testing of AFW Actuation Circuitry Was Inadequate.Caused by Inadequate Surveillance Procedures.Tested Untested Portions of Actuation Logic for AFW Automatic Start signal.W/960318 Ltr ML17353A5861996-03-0606 March 1996 LER 96-002-00:on 960209,automatic Turbine Trip/Rt Occurred Due to High SG Level.Caused by Personnel Error.Replaced Both Hinge Pins on B Sgfp Discharge Check valve.W/960306 Ltr ML17353A5761996-03-0101 March 1996 LER 96-001-00:on 960131,intake CWS Flow Rates Found W/ Potential to Be Less than Required by Design Basis.Caused by Influx of Aquatic Grass & Algae Onto Basket Strainers of Icw Flow Path.Mechanically Cleaned strainers.W/960301 Ltr ML17353A4451995-11-0909 November 1995 LER 95-007-00:on 951017,manual Rt Occurred Following Drop of Four Control Rods.Caused by Water Intrusion Into Rod Control Power Cabinet 2BD.Inspected Control Power Cabinet 2BD for Other Water damage.W/951109 Ltr ML17353A4241995-10-12012 October 1995 LER 95-006-00:on 950913,analysis Showed That CCW Exchangers Susceptible to Damage Due to flow-induced Vibration.Ccw Sys Has Been Flow Balanced to Closer tolerances.W/951012 Ltr ML17353A3601995-09-13013 September 1995 LER 95-005-00:on 950818,containment Pressure Testing Procedure Resulted in Inhibiting Both Trains of Containment Pressure from Initiated Esf.Revised Procedure to Require Testing of Each Train separately.W/950913 Ltr ML17353A2951995-07-17017 July 1995 LER 94-005-02:on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer ML17352B1581995-05-0505 May 1995 LER 95-004-00:on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies replaced.W/950505 Ltr ML17352B1181995-04-0707 April 1995 LER 95-003-00:on 950309,intake Cooling Water Flow Rate Through CCW Heat Exchangers Fell Below Assumed Design Basis. Caused by an Influx of Aquatic Grass & Algae Onto Basket Strainers.Strainers cleaned.W/950407 Ltr ML17352B0701995-03-13013 March 1995 LER 95-002-00:on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4.W/950313 Ltr ML17352B0321995-02-0909 February 1995 LER 94-005-01:on 941103,design Defect Found in Safeguards Bus Sequencer Test Logic,Placing Facility Outside Design Basis.Design Mods to Eliminate Software Logic Problems Will Be Implemented During Next Refueling outages.W/950209 Ltr ML17352B0101995-01-20020 January 1995 LER 94-006-00:on 941226,C Main Feedwater Control Valve Failed Closed,Causing Reactor & Turbine Trips.Caused by Loose Screw Terminal Connection.I/P Transducers Replaced W/ New Model W/Different Design Wire connection.W/950120 Ltr ML17352A9511994-12-13013 December 1994 LER 94-006-00:on 941130,Unit 4 Tripped Automatically.Caused by Failure of Flexible Link Connection Between Main Generator B Phase Bus & Associated Isolated Phase Bus Bar. All Bolts on Flexible Link checked.W/941213 Ltr ML17352A8871994-11-10010 November 1994 LER 94-005-00:on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI signal.W/941110 Ltr ML17352A8851994-11-10010 November 1994 LER 94-004-00:on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to automatic.W/941110 Ltr ML17352A8421994-10-21021 October 1994 LER 94-004-00:on 940923,Unit 4 Tripped Automatically from Rated Power.Caused by Faulty Regulator Transistor.Faulty Backup Power Supply Replaced & Maint History for Power Supplies reviewed.W/941021 Ltr ML17352A8431994-10-20020 October 1994 LER 94-005-00:on 940924,Unit 4 Manually Tripped.Caused by Manual Actuation.Light Bulb & Socket replaced.W/941020 Ltr ML17352B1671994-08-16016 August 1994 LER 94-003-00:on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced 1999-07-20
[Table view] Category:RO)
MONTHYEARML17355A3891999-07-20020 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 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 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 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 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 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 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 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 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 ML17354A6121997-08-29029 August 1997 LER 97-007-00:on 970730,automatic Reactor Trip Occurred. Caused by Closure of B Main Steam Isolation Valve.Failed W Relay & Equivalent Relays Were replaced.W/970829 Ltr ML17354A6081997-08-18018 August 1997 LER 97-006-00:on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power cabinets.W/970818 Ltr ML17354A5801997-07-14014 July 1997 LER 97-005-00:on 970618,RCP Oil Collection Sys Was Found Outside Design Basis.Caused Because Design Did Not Consider Component Parts to Be Potential Leakage Sources.Entire RCP Oil Collection Sys Was reviewed.W/970714 Ltr ML17354A5141997-05-22022 May 1997 LER 97-002-00:on 970423,automatic Reactor Tripped.Caused by Actuation of Turbine Overspeed Protection Circuit. Administrative Procedures Governing Inadequate Work Controls Will Be Revised to Capture Lessons learned.W/970522 Ltr ML17354A5061997-05-0909 May 1997 LER 97-003-00:on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in drain.W/970509 Ltr ML17354A5051997-05-0909 May 1997 LER 97-004-00:on 970411,auxiliary Feedwater Automatic Start Upon Trip of All Main Feedwater Pumps,Occurred.Caused by Mispositioned Valve Closing.Valves Listed as Inappropriately Positioned Were repositioned.W/970509 Ltr ML17354A4781997-04-25025 April 1997 LER 97-001-00:on 970327,ECCS Recirculation Loop Leakage Was Found to Be in Condition Outside Design Basis Due to Gasket Movement During Installation During Spring 1966 Reassembly. Gasket Replaced & Pump tested.W/970425 Ltr ML17354A4581997-03-28028 March 1997 LER 97-002-00:on 970303,manual Reactor Trip Following Rod Control Urgent Failure Alarm Occurred.Caused by Phase Failure Detection on Stationary a Circuits of 2BD Rod Control Cabinet.Air Conditioning replaced.W/970328 Ltr ML17354A4511997-03-26026 March 1997 LER 97-001-00:on 970118,missed Surveillance on CR Position Verification Occurred Due to Inoperable Rod Deviation Monitor.Faulty Circuit Common Connection Was Corrected & Rdm Operability Was restored.W/970326 Ltr ML17354A4061997-02-0303 February 1997 LER 96-004-03:on 970107,identified Three Instances of Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Surveillance Procedures Revised ML17354A3771996-12-27027 December 1996 LER 96-012-00:on 961204,determined Containment Average Temp Being Determined Based on Only Two Temp Elements Instead of Three as Required by Tss.Caused by Log Only Requiring One Entry.Log revised.W/961227 Ltr ML17354A3261996-11-0606 November 1996 LER 96-011-00:on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures revised.W/961106 Ltr ML17354A3071996-10-22022 October 1996 LER 96-010-00:on 960924,manual Reactor Shutdown Occurred. Caused by Failed Rod Control Sys Regulation Card in 2AC Power cabinet.2AC Power Cabinet DC Power Supplies,Cabling & Connectors checked.W/961022 Ltr ML17353A8711996-08-27027 August 1996 LER 96-009-00:on 960729,failed to Reflect Heavy Load Design Info in Procedural Controls.Caused by Failure to Incorporate 1982 Procedure Changes.Suspended Lifting of Heavy Loads & Took Turbine Bldg Crane OOS.W/960827 Ltr ML17353A7411996-06-18018 June 1996 LER 96-008-00:on 960521,surveillance Method for Testing Emergency Diesel Generators (EDG) Determined Inadequate. Caused by Personnel Error.All Four EDGs Rapid Start Tested & EDG Surveillance Procedures modified.W/960618 Ltr ML17353A7401996-06-18018 June 1996 LER 96-004-02:on 960524,identified Inadequate Surveillance Testing.Caused by Inadequate Surveillance Procedures.Entered Tech Spec Statements,Tested Required Instruments Functions & Revised Plant procedure.W/960618 Ltr ML17353A6901996-05-13013 May 1996 LER 96-004-01:on 960220,identified Potential Tech Spec non-compliance Associated W/Surveillance Testing of AFW Actuation Circuitry on Sg.Caused by Inadequate Surveillance Procedures.Procedures revised.W/960513 Ltr ML17353A6741996-05-0606 May 1996 LER 96-001-00:on 960409,manual Rt Occurred Due to Turbine Governer Control Oil Perturbation.Disassembled & Inspected Governor Valve for Cleanliness & Corrosion products.W/960506 Ltr ML17353A6651996-04-29029 April 1996 LER 96-007-00:on 960329,inadvertent ESF Actuation Occurred During Refueling Outage Due to Cognitive Personnel Error. Personnel Involved Counseled & Integrated Safeguards Test Procedures Being revised.W/960429 Ltr ML17353A6601996-04-25025 April 1996 LER 96-006-00:on 960327,manual Rt Occurred Due to 3C Transformer Lockout & Loss of 3B SG Mfp.Replaced SAM Timer Relay in 3AC16.W/960425 Ltr ML17353A6491996-04-23023 April 1996 LER 96-005-00:on 960326,certain Safety Injection Accumulator Filled Evolutions Resulted in cross-tied Configuration.C/A: Night Order Written & Operations Procedure 3/4-OP-064 revised.W/960423 Ltr ML17353A6051996-03-18018 March 1996 LER 96-003-00:on 960222,two Arpi Inoperable & TS 3.0.3 Entered.Proposed License Amend Submitted to Revise Allowed Misalignment from +/-12 Steps to =/-18 Steps Between Arpi & Dpi at Less than 90% power.W/960318 Ltr ML17353A6041996-03-18018 March 1996 LER 96-004-00:on 960220,surveillance Testing of AFW Actuation Circuitry Was Inadequate.Caused by Inadequate Surveillance Procedures.Tested Untested Portions of Actuation Logic for AFW Automatic Start signal.W/960318 Ltr ML17353A5861996-03-0606 March 1996 LER 96-002-00:on 960209,automatic Turbine Trip/Rt Occurred Due to High SG Level.Caused by Personnel Error.Replaced Both Hinge Pins on B Sgfp Discharge Check valve.W/960306 Ltr ML17353A5761996-03-0101 March 1996 LER 96-001-00:on 960131,intake CWS Flow Rates Found W/ Potential to Be Less than Required by Design Basis.Caused by Influx of Aquatic Grass & Algae Onto Basket Strainers of Icw Flow Path.Mechanically Cleaned strainers.W/960301 Ltr ML17353A4451995-11-0909 November 1995 LER 95-007-00:on 951017,manual Rt Occurred Following Drop of Four Control Rods.Caused by Water Intrusion Into Rod Control Power Cabinet 2BD.Inspected Control Power Cabinet 2BD for Other Water damage.W/951109 Ltr ML17353A4241995-10-12012 October 1995 LER 95-006-00:on 950913,analysis Showed That CCW Exchangers Susceptible to Damage Due to flow-induced Vibration.Ccw Sys Has Been Flow Balanced to Closer tolerances.W/951012 Ltr ML17353A3601995-09-13013 September 1995 LER 95-005-00:on 950818,containment Pressure Testing Procedure Resulted in Inhibiting Both Trains of Containment Pressure from Initiated Esf.Revised Procedure to Require Testing of Each Train separately.W/950913 Ltr ML17353A2951995-07-17017 July 1995 LER 94-005-02:on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer ML17352B1581995-05-0505 May 1995 LER 95-004-00:on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies replaced.W/950505 Ltr ML17352B1181995-04-0707 April 1995 LER 95-003-00:on 950309,intake Cooling Water Flow Rate Through CCW Heat Exchangers Fell Below Assumed Design Basis. Caused by an Influx of Aquatic Grass & Algae Onto Basket Strainers.Strainers cleaned.W/950407 Ltr ML17352B0701995-03-13013 March 1995 LER 95-002-00:on 950215,inadequate Definition of Loops Filled Resulted in Units in Condition Prohibited by Ts. Issued TS Position Statement to Define Term Loops Filled as Used in TS 6.4.1.1.4.W/950313 Ltr ML17352B0321995-02-0909 February 1995 LER 94-005-01:on 941103,design Defect Found in Safeguards Bus Sequencer Test Logic,Placing Facility Outside Design Basis.Design Mods to Eliminate Software Logic Problems Will Be Implemented During Next Refueling outages.W/950209 Ltr ML17352B0101995-01-20020 January 1995 LER 94-006-00:on 941226,C Main Feedwater Control Valve Failed Closed,Causing Reactor & Turbine Trips.Caused by Loose Screw Terminal Connection.I/P Transducers Replaced W/ New Model W/Different Design Wire connection.W/950120 Ltr ML17352A9511994-12-13013 December 1994 LER 94-006-00:on 941130,Unit 4 Tripped Automatically.Caused by Failure of Flexible Link Connection Between Main Generator B Phase Bus & Associated Isolated Phase Bus Bar. All Bolts on Flexible Link checked.W/941213 Ltr ML17352A8871994-11-10010 November 1994 LER 94-005-00:on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI signal.W/941110 Ltr ML17352A8851994-11-10010 November 1994 LER 94-004-00:on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to automatic.W/941110 Ltr ML17352A8421994-10-21021 October 1994 LER 94-004-00:on 940923,Unit 4 Tripped Automatically from Rated Power.Caused by Faulty Regulator Transistor.Faulty Backup Power Supply Replaced & Maint History for Power Supplies reviewed.W/941021 Ltr ML17352A8431994-10-20020 October 1994 LER 94-005-00:on 940924,Unit 4 Manually Tripped.Caused by Manual Actuation.Light Bulb & Socket replaced.W/941020 Ltr ML17352B1671994-08-16016 August 1994 LER 94-003-00:on 940720 & 21,util Discovered That Several Required Valve Stroke Time Surveillances Had Not Been Performed.Caused by Personnel Error.Personnel Reassigned & Procedures and Surveillance Tracking Software Enhanced 1999-07-20
[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
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REGULATORY AFORMATION DISTRIBUTION SY ~EM (RIDS)
ACCESSION NBR: 8707310295 DOC. DATE: 87/07/29 NOTARIZED: NO DOCKET 0 FACIL: 50-250 Turkeg Point Planti Unit 3> Florida Poujer and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION WAGER'. Florida Power & Light Co.
WOODYi C. O..
RECIP. NAME Florida Power & Light Co.
RECIPIENT AFFILIATION
SUBJECT:
LER 87-021-00: on 870701i auto safety inJection initiated fr om spurious containment high pressure signal. Nitrogen supply valve manipulated to verify closed causing pressure spike thus actuating Train A. Test seitch replaced. W/87072'9 ltr.
DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR i ENCL i SIZE:
TITLE: 50. 73 Licensee Event Report (LER)i Incident Rpti etc.
NOTES:
REC IP IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 McDONALDI D 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DO* 1 *EOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 DEDRO 1 1 NRR/DEST/ADE 1 0 NRR/DEST/ADS 1 0 NRR/DEBT/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ I CSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 NRR/PMAS/ILRB 1 1 NRR/PMAS/PTSB 1 1 QEG=Pg~ 02 1 RES DEPY GI 1 RES 4lELFORDi J 1 1 RES/DE/EIB 1 1 RGN2 FILE 01 1 EXTERNAL: EG&G GROHz M 5 5 H ST LOBBY WARD LPDR 1 1 NRC PDR NSIC HARRIS' '1 1 NSIC MAYST G TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 43
NRC Forn~ 355 U.S. NUCLEAII REGULATOR Y COMMISSION (983 I APPROVED OMB NO. 31500105 LtCENSEE EVENT REPORT (LER) EXPIRES: 4/31/44 FACILITY NAME (II DOCKET NUMBER (2) PA Turke Point Unit 3 0 5 0 0 0 1 OF TI'TLE MI Train A Safeguards Actuation due to Containment High Pressure Signal EVENT DATE (SI LER NUMBER (SI DATE (7) OTHER FACILITIES INVOLVED (SI MONTH OAY YEAR YEAR 55QVCNTIAL R5VrsrQN MONTH DAY YEAR'EPORT FAC/LITY NAMES OOCKFT NUMBER(SI NVMSER NVMSER Ill N/A o s 0 o o 07 018 8 7 0 2 1 0 0 07 29 8 7 N/A 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSVANT T 0 THE REQUIREMENTS OF 10 CFR gt /Crrocn ons or mao of tns fo//ort/nt/ l11 OPERATINO MODE (4) 20.405(c) 50.734) (2) (hl 73.7((5)
POWER 20AOS( ~ )IB SOM(c) (I) 50.734) (2) (rl 73.71(c)
LEY EL ~')'/o',",'0.402(5) 0 0 20l05(aHI IIE) 50M(c) (21 50.734)(2)(rBI Q7HEII fspsc/fy in Aortrsct
/rs/ow and/n Tsxt HRC Form
'a+jet: 4 20A05(s) (1)((5) 50,73(a I (2) Ill 50.73(a I (2) l r(II)(A) 388lf 20.405(s) l1) 0 I 50.73(sl(2) (ii) 50.73(sl(2) (r(dl(B) 20.405(a)l1) (r) 50.73(sl(2) (5/I 50.73( ~ ) l2)(x)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER Virgil Wager AREA CODE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) 3 5 246 -6 76 CAUSE SYSTEM COMPONENT MANUFAC.
TVRER EPDATASL ~ '~$
$+$ 5 CAUSE SYSTEM COMPONENT MANUFAC.
TVRER EPORTABLE TO NPRDS YkÃ4)r(Fo'I )~4)'~i%(ÃR SUPPLEMENTAL REPORT EXPECTED (Iol MONTH OAY YEAR FXPECTED SU 5 M I SS IO N DATE II SI YES fifym, COmp/ttt EXPECTED Si/Ett/$ $ /OH DATE/ NO ABSTRACT fLim/t to to00 tpocst, /o., approx/moto/y fi/toon t/no/oopsco typorrritton //nN/ (14)
On July 1, 1987, at 0148, while Unit 3 was at cold shutdown safety injection was initiated from a spurious (Mode 5) an auto The electrical department required a hose Containment High Pressure signal.
to test the penetration canisters on Unit 4 which was in hot standby (Mode 3 a pressure rig on Unit 3 that was to be ). They borrowed a Containment High Pressure signal for utilized for initiating supply valve to the pressure rig was opened in the testing.
Safeguards The nitrogen closed, thereby causing a Containment High Pressure process of verifying it was actuation of the ESFs All equipment lined up for operation signal. This resulted in an normally. Train B did not receive an actuation signal. on Train A functioned is not required to be operable in Mode 5. The normal'eat sink Safety injection not lost during the event since there was no loss (RHR) was Also, there was no safety injection flow to the reactor since of offsite power.
MOV 3-843 A and B, and MOV 3- 869 were tagged closed on the cold shutdown clearance . The unit was returned to the normal configuration for at 0155. Mode 5 8707310295 870729 PDR ADOCK 05000250 S PDR NRC Form 345 (943)
I!RC Form rr38A U.S. NUCLEAR REGULATORY COMMISSION (9831 LICENSEE EVENT EPORT {LER) TEXT CONTINUATION APPROVEO OM8 NO. 3150M104 EXPIRES'/31/88 FACILITY NAME (11 OOCKET NUMBER (2( LER NUMBER (8( PAGE (3)
YEAR '4M SEQUENTIAL -i%%! REVISION Turkey Point Unit 3 igS NUMSER 9"N NUMEER 0 5 0 0 0 2 5 0 87 0 21 0 0 0 2 or- 0 3 Tm(T /O'RNoo <<Moo is /o9uoed, INo aAtdonal HRC Furr/I 3////A'4/ (17(
EVENT On July 1, 1987, at 0148 , while Unit 3 was in cold shutdown (Mode 5) and Unit 4 was in hot shutdown (Mode 3), a spurious Containment High Pressure signal actuated Safety Injection and Phase A Containment Isolation on Unit 3. The safety injection components and Phase A containment isolation valves that were lined up for operation on Train A functioned normally. The A Emergency Diesel Generator did not start because it was out of service for governor maintenance. The Train B safety injection components and containment isolation valves did not operate and the B Emergency Diesel Generator did not start because Train B did not receive an actuation signal. The normal heat sink (RHR) was not lost during the event as there was no loss of offsite power. There was no safety injection flow to the reactor as MOV 3-843 A&B and MOV 3-869 were tagged closed on the cold shutdown clearance. At 0155, the operators entered the appropriate Emergency Operating Procedures; 3-EOP-E-O, Reactor Trip or Safety Injection and 3-EOP-ES-1.1, Safety Injection Termination, and returned the unit to normal configuration for Mode 5.
CAUSE OF EVENT The Electrical Department needed to connect a hose to the plant nitrogen system and the penetration cannisters on Unit 4 for a pressure test.
They borrowed an I&C pressure rig from Unit 3 that was going to be utilized for initiating a Containment High Pressure signal for the Integrated Safeguards Test. There were no tags of any kind on the nitrogen supply valve or hose that would have prohibited removal of the rig. Before disconnecting the hose, the nitrogen supply valve was manipulated to verify it was closed thereby causing a pressure spike greater than 4 psig on Channels I and III which actuated Train A of the ESF.
Test switch S-23 (PC-456D) which simulates a Pressurizer Safety Injection signal was mechanically faulty and had been disconnected in conformance with an I&C Plant Work Order. The negative terminal (J-2) of the switch had two leads one of which completed the negative side of the DC circuit for the safety injection signal to Train B. A replacement switch which had to be ordered, had not been installed at the time of the event. The open DC circuit precluded the actuation of Train B Safety Injection.
NRC FORM 3ESA o U.S.GPO:(988.0 824 538/455 (94(31
N':IC Form SSSA U.S, NUCLEAR REOULATORY COMMISSION (94)3)
LICENSEE EVENT R PORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3150&104 EXPIRES: 8/31/88 FACILITY,NAME l1) OOCKET NUMBER (2)
LER NUMBER (8) PACE (3)
YEAR SEOVSNTIAL REVISION Turkey Point Unit 3 NVMSSR NVMSSR TS/T //PM/o FPSrrF /4 '/rrSod, INo rrSWcnal HRC For/II 3854'4/ l (T) o s o o o 2 5 0 8 7 0 2 1 00 03 DF0 3 ANALYSIS OF EVENT At the time of the event Unit 3 was in Cold Shutdown (Mode 5). Safety Infection and Containment Isolation are not required to be operable in Mode 5. However, the requirements for ESF equipment response to a safety injection signal depends on the status of the equipment. Certain valves and equipment were out of service under the cold shutdown clearance and various maintenance clearances. But all equipment that was lined up for operation on Train A functioned normally upon receipt of the SI signal.
Based on the above the health and safety of the public were not affected.
CORRECTIVE ACTIONS
- 1) The replacement for test switch (S-23) has been received and the I&C Department installed it on 7-2-87.
- 2) The operators returned Unit 3 to the normal configuration for Mode 5 utilizing EOP-E-O, Reactor Trip or Safety Injection and EOP-ES-1.1, Safety Injection Termination.
- 3) The Engineered Safeguards Integrated Test procedure will be changed to provide for additional protection to avoid inadvertent initiation of the ESF components. Section 7.1.11 of the procedure will have a step added to require the placement of caution tags on the source connection that provides the test signal to the pressure switches.
ADDITIONAL DETAILS The original test switch (S-23) was supplied by the'EES company.
However, the specific model had been discontinued and a different model manufactured by REES, had to be ordered and approved for replacement.
Similar Occurrences: none NRC FORM SSSA o U S GPO'1986 0.824 538/455 (94)3)
P. O. BOX 1 JUNO BEACH, FL 33408.0420
' Ivy ~
JULy L-87-3 I 7 IO CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gen t I emen:
Re: Turkey Point Unit 3 Docket No.,50-250 Reportable Event: 87-2 I Date of Event: July I, l987 Train A Safeguards Actuation, Due To Containment Hi h Pressure Si nal The attached Licensee Event Report is being submitted pursuant to the requirements of IO CFR 50.73 to provide notification of the subject event.
Very truly yours, C. 0. ody Group Vice President Nuc I ear Energy COW/SDF /pm Attachment cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant, an FPL Group company SDF I/0O5/I