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| {{#Wiki_filter:PRIORITY (ACCELERATED RIDS PROCESSIi' REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION'NBR:9502160155 DOC.DATE: 95/02/07'OTARIZED: | | {{#Wiki_filter:}} |
| NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 AUTH.NAME AUTHOR AFFILIATION GRABO,B.A.
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| Arizona Public Service Co.(formerly Arizona Nuclear Power LEVINE,J.M.
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| Arizona Public Service Co.(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION
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| ==SUBJECT:==
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| LER 94-010-00:on 930409,misalignment of limitorque torque switch contact bar prevented remote operation of MOVs.Evaluation of all flex wedge gate valves&SB type MOVs was ,performed.W/950207 ltr.DISTRIBUTION CODE IE22T COPIES'ECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:STANDARDIZED PLANT 05000528 RECIPIENT ID CODE/NAME PD4-2 PD TRAN, L I INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DOPS/OECB NRR/DRCH/HICB NRR/DRSS/PRPB NRR/DSSA/SRXB RGN4 FILE 01 EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G.A NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME HOLIAN, B AEOD/SPD/RAB
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| ~FIL'E CENTE~R-02 NRR/DE/EELB NRR/DI S P/PI PB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DSSA/SPLB RES/DSIR/EIB LITCO BRYCE,J H NOAC POORE,W.NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 VOTE TO ALL"Rl DS" RECIPIENTS:
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| PLEASE HELP US TO REDUCE iVASTE!COVTACTTHE DOCl:MEVT CONTROL DESK, ROOM Pl-37 (EXT.504-2083)TO ELIXIIN'ATE W'OI'R NAME FROM DISTRIBUTION LISTS I'OR DOCL'MEV'I'S YOL'Oi"I'L'I'-D!
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| FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 28 t V Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O.BOX 52034~PHOENIX, ARIZONA 85072-2034 JAMES M.'EVINE VICE PRESIDENT NUCLEAR PRODUCTION U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Mail, Station P1-37 Washington, DC 20555 192-00920-JML/BAG/BE February.7, 1995 ,
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| ==Dear Sirs:==
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| ,
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| ==Subject:==
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| Palo Verde Nuclear Generating Station (PVNGS)Units 1,.2, and 3 Docket Nos.STN 50428, 50429, 50430 License Nos.NPFX1, NPF-51, NPF-74 Licensee Event Report 9441040 File: 9520<04 Attached please find Licensee Event Report (L'ER)94-:010'repared and submitted pursuant'to 10CFR50.73.
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| This LER reports the identification of a condition that resulted in the Unit 3 changing Modes.and not satisfying TS 3.0;4.Also, this LER reports the identification of a generic failure with MOVs that alone could have prevented the fulfillment of the safety function of systems, needed to remove residual heat and mitigate the consequences of, an accident.In accordance with 10CFR50.73(d), a copy, of this LER is being forwarded.to the Regional Administrator,.NRC Region IV.If you have any-questions,.
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| please contact Burton.A.Grabo, Section Leader, Nuclear Regulatory Affairs, at (602),393-6492.
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| JML/BAG/BE/pv Attachment Sincerely,.
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| ~/~~/U~(all with attachment) cc: L.J.Callan K.E.Perkins K E.Johnston INPO Records Center 9502160155 950207 PDR ADOCK, 05000528 S PDR il'I P LICENSEE EVENT REPORT (LER)FACILITY NAME (1)Palo Verde Unit 1 DOCKET NUMBER (2)PAGE (3)0 5 0 0 0 5 2 8 1~oF 0 8 TLE (4)Misali nmentof Limitor ue Tor ue Switch Contact Bar Prevented Remote 0 eration of MOVs EVENT DATE 5 MONTH DAY YEAR YEAR LER NUMBER 6 SEQUENTIAL NUMBER REVISON NUMBER REPORT DATE MONTH DAY YEAR OTHER FACIUTIES INVOLVED 6 FAQLITY NAMES Palo Verde Unit 2 NUMBERS 0 5 0 0 0 5 2 9 0 4 0 9 9 3 9 4 0 1 0 0 0 0 2 0 7 9.5 Palo Verde Unit 3 0 5 0 0 0 5 3 0 E REQUIREMENTS OF 10 CFR Q (Check one or more of tbe fobovvin6)
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| (11)REPORT IS SUBMITTED PURSUANT To TH LEVEL(to)P P P 20.402(b)20.405(a)(1)(()
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| 20.405(a)(1)(ii)20.405(a)(1)(iii) 20.405(a)(1)
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| Ov)20.405(a)(1)(v)20.405(c)50.36(c)(1)50.36(c)(2) 5073(a)(2)(0
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| '50.73(a)(2)(ii) 50.73(a)(2)(iii)
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| LICENSEE CONTACT FOR THIS LER (12)50.73(a)(2)(iv) 5(L73(a)(2)(v) 5(k73(a)(2)(vb) 50.73(a)(2)(vei)(A) 50.73(a)(2)(VIIB(B)5073(a)(2)(r)
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| EPHONE NUMBER 73.71 (b)73.71(c)OTHER (Specify in Abstract bekrvv an(f in Te((L NRC Form 366A)Burton A.Grabo, Section Leader, Nuclear Regulatory Affairs REA CODE 602393-6492 COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPOR T(13)CAUSE SYSTEM COMPONENT MANU FAG.TURER CAUSE MANUFAC.TVRER REPORTABLE To NPRDS B B P 2 0 L 2 0 0 Y SUPPLEMENTAL REPORT EXPECTED (14))(No YES 0f yes.complete EXPECTED SUBNSSON DATE)sr((Icr grid H N00 wtcol.I~~(~wlpMcNco Igewcell@el)(1()EXPECTED SUBMISSION DATE (1 5)DAY YEAR At approximately 1900 MST on April 9, 1993, Palo Verde Unit 2 was DEFUELED, when it was identified by Valve Services personnel that the close torque switch contact bar for Shutdown Cooling suction isolation valve 2JSIAUV0655, was misaligned.
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| The evaluation at the time determined the misalignment of the close torque switch contact bar to be an isolated incident.Similar events happened on January 27, 1994 (Unit 1), and June 7, 1994 (Unit 3).Based upon further evaluation, the above events were determined to have a common-mode failure.On January 10, 1995, the above events were determined to be reportable per 10CFR 50.73.There have been no previously similar events reported pursuant to 10CFR 50.73,.
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| LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE PALO VERDE UNIT 1 EXT 1 REPORTING REQUIREMENT:
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| YEAR 0 5 0'0 0 5 2 8 9 4 SEQUENTIAL NUMBER 0 1 0 X.<<8.'y,'5 EVISIO NUMBER 0 0 0 2 OF 0 8 This LER 528/529/530/94-010 is being written to report events that resulted in a condition prohibited by the plant's Technical Specifications (TS)as specified in 10 CFR 50.73(a)(2)(i)(B).
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| Also, these events identified a condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to: (B)Remove residual heat, and (D)Mitigate the consequences of an accident as specified in 10 CFR 50.73(a)(2)(v).
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| Specifically, at approximately 1900 MST on April 9, 1993, APS Valve Services personnel (utility, non-licensed) identified that during the performance of a preventive maintenance (PM)task for Shutdown Cooling suction isolation valve 2JSIAUV0655, the close torque switch contact bar was found to be mi.saligned.
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| On January 27, 1994, at approximately 0500 MST, it was identified by Operations personnel, that Containment Spray valve 1JSIAUV0672 would not close after being, opened for Surveillance Testing (ST).Troubleshooting of the valve identified that the contact bar was found to be on its side between the contact spring and bracket at a 90 degree angle.No indication of degradation to the torque switch other than the flipped contact bar was identified.
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| On June 6, 1994, Unit 3 Operations was performing procedure 430P-3SI02"Recovery from Shutdown Cooling to Normal Operating Lineup".During performance of step 4.3.4', Shutdown Cooling suction isolation valve 3JSIAUV0655 was given a closing signal by the control room hand.switch in an effort to lineup Safety Injection (SI)Train A for power operation.
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| The valve stroked partially closed and then stopped.Troubleshooting of the valve identified that the contact bar was found to be on its side between the contact spring and'bracket at a 90 degree angle.No visible signs of damage or degradation were noted other than the spread retaining brackets Upon further investigation and evaluating the above events combined a common-mode failure existed.Also, on June 6, 1994, Unit 3 changed from Mode 5 (COLD SHUTDOWN)to Mode 4 (HOT SHUTDOWN)with valve 3JSIAUV0655 inoperable as determined by post event analysis.This condition is in violation of TS 3.0.4.
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| LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME PALO VERDE UNIT 1 DOCKET NUMBER YEAR LER NUMBER SEQUENTIAL NUMBER EVISIO NUMBER PAGE EXT 2.EVENT DESCRIPTION:
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| 0 5 0 0 0 5 2 8 9 4 0 1 0 0 0 0 3 OF 0 8 On April 9, 1993, Unit 2 was DEFUELED, when it was identified by Valve Services personnel that the close torque switch contact bar for valve 2JSIAUV0655 was misaligned.
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| The functional requirement of 2JSIAUV0655 is to provide containment isolation in Modes 1-4 and tertiary isolation between the Reactor Coolant System (RCS)and Shutdown Cooling suction line during Modes 1-3.During power operation, the valve is normally closed (passive)and must remain in its closed position for these functions..
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| As part of the evaluation, queries of the national Nuclear Plant Reliability Data System (NPRDS)and Palo Verde's Failure Data Trending were performed.
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| Neither of the two queries produced any evidence that the problem had occurred before at PVNGS or nationwide.
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| Also, Limitorque Corporation had no prior knowledge of the problem occurring before with any other Limitorque torque switch.The investigation concluded that the misalignment of the close torque switch contact bar was an isolated incident.Because the problem has never before been encountered, and since the condition could not be duplicated during testing.The apparent cause of the misalignment of the close torque switch contact bar was its impact against the close torque switch contact posts during unseating.
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| On January 27, 1994, Unit 1 was in Mode 1 (POWER OPERATIONS) at approximately 85 percent power, when it was identified by Operations personnel, that 1JSIAUV0672 would not close after being opened for Surveillance Testing (ST).Troubleshooting of the valve identified that the contact bar was found to be on its side between the contact spring and bracket at a 90 degree angle.No indication of degradation to the torque switch other than the flipped contact bar was identified.
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| The functional requirement of 1JSIAUV0672 is to provide containment spray header isolation during power operation and shutdown cooling.The valve is normally closed (passive)and must remain in its closed position for these functions.
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| The valve must open on receipt of a containment spray, actuation signal (CSAS)and must close on control room demand to terminate containment spray.
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| il C LICENSEE EVENT REPORT (LER)TEXT CONTINUATION I'ACIUTY NAME DOCKET NUMBER LER NUMBER PAGE PALO VERDE UNIT 1 YEAR$$;SEOUENTIAL NUMBER EVISIO NUMBER 0 5 0 0 0 5 2 8 9 4'0,1 0 0 0 0 4 oF0 8 Procedure 36ST-9SA01,"ESFAS Train A Subgroup Relay Monthly Functional Test", has been performed seven times during, the course of the year prior to the MOV's latest static diagnostic test.Because this valve is required to be left in the closed position following completion of this relay tests, and the closing.valve stroke is controlled remotely via control room handswitch, it can be concluded that the close torque switch contact bar must have flipped on its side during the opening stroke just prior to the closing stroke on January 27, 1994'f it had done so during any relay test prior to January 27, 1994, the valve, would not have been able to close.Thus, MOV 1JSIAUV0672 was fully operational prior to the relay test during which the.failure occurred.On June 6, 1994, Unit 3 Operations was performing procedure 43OP-3SI02"Recovery from Shutdown Cooling to Normal Operating Lineup".During performance of step 4.3.4.3, valve 3JSIAUV0655 was given a closing signal by the control room hand switch in an effort to lineup Safety Injection (SI)Train A for power operation.
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| The valve stroked partially closed and then stopped.Troubleshooting of the valve identified that the contact bar was found to be on its side between the contact spring and bracket at a 90 degree angle.No visible signs of damage or degradation were noted other than the spread retaining bracket.'I The functional requirement of 3JSIAUV0655 is to provide containment isolation in Modes 1-4 and tertiary isolation between the Reactor Coolant System (RCS)and Shutdown Cooling suction line during Modes 1-3.During power operation, the valve is normally closed (passive)and must remain in its closed position for these functions.
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| Because the torque switch failure occurs during unseating of the valve, the torque switch failure happened during the last open stroke prior to the failure discovery.
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| The last open stroke prior to the failure discovery must have occurred when 3JSIAUV0655 was cycled open to lineup Train A SDC for service because 3JSIAUV0655 cannot be cycled with Train A SDC in service.It is therefore, determined that 3JSIAUV0655 was not capable of remote manual closure from the time at which the valve was opened to place Train A SDC in service to the time that the failure was discovered and corrected.
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| Therefore, 3JSIAUV0655 was inoperable from May 31, 1994 (last time Train A SDC was placed in service), to June 6, 1994 (the discovery date).
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| il LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACIUTY NAME PALO VERDE UNIT 1 DOCKET.NUMBER , YEAR LER NUMBER SEQUENTIAL;,'.P.
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| :EVISIO NUMBER.:'~~:.'UMBER PAGE 0 5 0 0 0 5 2 8 9 4 0 1 0 0 0 0 50F 0 8 3.Unit 3 entered Mode 4 at 2036 MST on June 6, 1994.The valve was discovered inoperable at 2253 MST and Limiting Condition of Operations (LCO)3.6.3 Action b was met at 0118 MST on June 7, 1994.The Operations staff was timely in complying with TS, however, according to the above evaluation 3JSIAUV0655 was inoperable prior to going into Mode 4.Therefore, TS 3.0.4 was not satisfied unbeknown to the Operations.
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| staff.ASSESSMENT OF THE'SAFETY CONSEQUENCES AND IMPLICATION OF THIS EVENT: An Equipment Root Cause of Failure Analysis (ERCFA)was performed on 1JSIAUV0672 and 3JSIAUV0655.
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| As part of this evaluation test data on the torque switch springs from 1JSIAUV0672 and 3JSIAUV0655 were compared to the springs removed from 2JAFBUV0035 and new springs from the warehouse.
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| The springs from 1JSIAUV0672 and 3JSIAUV0655 were determined not to be in a degraded or out of design condition.
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| Further, it is reasonable to assume that the same springs are present in other PVNGS MOVs and may be susceptible to the same failure.A Probabilistic Risk Assessment (PRA)was performed to determine if a known deficient condition has a significant impact on the reliability of certain motor operated gate valves (MOVs).This study calculated the fail to close (FTC)probability for all MOVs susceptible to this condition in addition to a smaller grouping of MOVs whose static diagnostic displacement measuring transducer (DMT)signature may indicate a higher susceptibility to this type of failure.Of the 52 valves identified only 2 are currently credited in the PVNGS PRA for any type of FTC function.Valves that are included in the PRA are 1)SIA/BHV0699/698 (HPSI cold leg injection isolation valves)and 2)CHA/BHV0531/530 (RWT to SI isolation valves).SIA/BHV0699/698 are credited in the PRA to reduce the HPSI flow via the cold legs to allow for HPSI flow via the hot legs (hot leg injection) within 2-3 hours following a Loss of Coolant Accident (LOCA).CHA/BHV0531/530 are credited to isolate the RWT post LOCA once a Refueling Water Tank (RWT)low level is reached and containment recirculation occurs.There are a number of additional valves however, that due to operational concerns or due to postulated events which may require a need for valve closure.The calculated FTC probabilities from industry data, which range from 1.08 E-03 to 1.91 E-02, for all susceptible MOVs with a weighted average value of 7.69 E-03.
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| LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACIUTY NAME PALO VERDE UNIT 1 DOCKET NUMBER LER NUMBER SEQUENTIAL NUMBER EVISIO NUMBER PAGE EXT 0 5 0 0 0 5 2 8 9 4 0 1 0 0 0 0 6 OF 0 8 The calculated FTC probabilities for PVNGS specific failures (flipped torque switch bar)range from 1.71 E-04 to 5.41 E-04, with the 1.71 E-04 value representing all susceptible MOVs and 5.41 E-04 representing MOVs whose static diagnostic DMT signatures indicate a potentially higher susceptibility.
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| The results indicate that the failures associated with the failed torque switches are bounded and represent a small increase (FTC mean demand rate value)to the total MOV estimated failure probabilities.
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| However, the.study recommended that corrective action for'SGA/BUV0134/138 not be deferred until the next unit outage since the calculated.FTC probability shows an additional 50 percent increase in that valve's FTC probability along with the valve's safety related function to close on a steam line break.Corrective action to replace the torque switch contact bar springs on select MOVs may be prudent from an operational or deterministic standpoint, however, based upon examining the FTC demand failure probability, justification exists from a probabilistic standpoint to defer corrective action until the next refueling outage.This event did not result in any challenges to the fission product barriers or result in any releases of radioactive materials.
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| Therefore, there were no adverse safety consequences or implications as a result of this event.This event did not adversely affect the safe operation of the plant or the health and safety of the public.CAUSE OF THE EVENT: An evaluation for each event was performed in accordance with the APS Incident Investigation Program.The evaluation for the second and third events determined that the root cause of the torque switch contact flipping on its side is attributed to a combination of torque loads experienced by the operator during the unseating of the valve disk, the resiliency of the spring pack dampening those loads and the sudden release of those loads as the disk unseats.During unseating, the torque switch relaxes towards the open direction from its closed rotation and remains in its relaxed state until the valve stem starts to pull on the disk.Once the stem starts to pull on the disk, the torque.switch rotates in the open direction until the disk breaks its static friction with the valve seat and starts to move in the open direction.
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| il 0 LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME DOCKET NUMBER LER NUMBER PAGE PALO VERDE UNIT 1 YEAR SEOUENTNIL NUMBER.:.:"",'";'UMBER 0 5 0 0 0 5 2 8 9 4 0 1 0 0 0 0 70F 0 8 EXT At the instant that the disk breaks its static friction with the guides, the open torque.switch contacts snap closed and the shock from this action rapidly rotates open the closing contacts which then snap back closed.It is possible that the rotational acceleration of the close torque switch contact block assembly from this rapid oscillatory action caused the torque switch contact bar to become misaligned (SALP Cause Code B Design, Manufacturing or Installation Error).As a result of this misalignment, continuity is broken across the close torque switch contact posts.and the surface of the contact bar, therefore, the valve cannot be'ycled closed.5.STRUCTURES, SYSTEMS, OR COMPONENTS INFORMATION:
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| MOV 1JSIAUV0672 is comprised of a Limitorque SB-0 actuator mounted on an eight inch Borg Warner flex wedge gate valve.The actuator and the valve are oriented vertically to the piping through which flow is controlled.
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| The MOV is driven by a 25 FT-LB, 3400 RPM AC motor.MOVs 2JSIAUV0655 and 3JSIAUV0655 are comprised of a Limitorque SMB-1 actuator mounted on a Borg Warner flex wedge gate valve.The actuator and the valve are oriented horizontally to the piping through which flow is controlled.
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| The MOVs are driven by a 40 FT-LB, 1800 RPM AC motor.6.CORRECTIVE ACTIONS TO PREVENT RECURRENCE:
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| As part of the evaluation for the torque switch failures, an evaluation of all flex wedge gate valves and SB type MOVs was performed and identified valves that were susceptible to this type of failure.To prevent reccurrence of the torque switch failure, the contact bar compression springs will be replaced in all of the identified valves.These replacements are to be done no later than their next scheduled maintenance.
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| To date all of the contact bar compression springs for valves identified in Unit 3 have been replaced.The majority of valves identified for, Units 1 and 2 will be replaced in their up coming refueling outages (April and February, 1995, respectively).
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| These actions are being tracked under the APS Commitment Action Tracking System.
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| LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FAG IUTY NAME DOCKET NUMBER LER NUMBER PAGE PALO VERDE'UNIT 1 YEAR'Q>.>iP';SEQUENTIAL::;::.:;:@'..
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| NUMBER:I':."";EVISIO NUMBER.EXT 7.0 5 0 0 0 5'2 8 PREVIOUS SIMILAR EVENTS: 9 4:0 1 0 0'0 0 8 oF0 8 There have been no similar events to this type of failure reported pursuant to 10CFR50.73 where misalignment of the torque switch contact.bar have affected MOV operability in the past three years.LER 1-93-010 was submitted on January 26, 1994, however, this LER dealt with performance criteria established in Generic Letter 89-10.
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