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| {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONS REGULATORY XNFORMATION DISTRIBUTION SYSTEM,.(RIDS) | | {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONS REGULATORY XNFORMATION DISTRIBUTION SYSTEM,.(RIDS) |
| ACCESSION NBR:9101160001 DOC.DATE'1/01/11 NOTARIZED: | | ACCESSION NBR:9101160001 DOC.DATE'1/01/11 NOTARIZED: NO DOCKET FACIL:50-316 Do Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION CARTEAUX P.F. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele BLIND,A.A. Xndiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION |
| NO FACIL:50-316 Do Donald C.Cook Nuclear Power Plant, Unit 2, Indiana&05000316 DOCKET AUTH.NAME AUTHOR AFFILIATION CARTEAUX P.F.Indiana Michigan Power Co.(formerly Indiana&Michigan Ele BLIND,A.A. | |
| Xndiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER 90-012-00:on 901212,reactor tripped as result of steam-to-feedwater flow mismatch&one turbine-driven main feedwater pump tripped due to erroneous actuation of thrust bearing.Bearing bench calibr.W/910111 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL'IZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD3-1 LA COLBURN,T. | | LER 90-012-00:on 901212,reactor tripped as result of steam-to-feedwater flow mismatch & one turbine-driven main feedwater pump tripped due to erroneous actuation of thrust bearing. Bearing bench calibr.W/910111 ltr. |
| INTERNAL: ACNW AEOD/DS P/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D LB8D1 G F 02 RGN3 FILE 01 EXTERNAL EG&G BRYCE I J~H NRC PDR NSIC MURPHY,G.A COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD AEOD/DOA AEOD/ROAB/DS P NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB 8E RES/DSXR/EIB L ST LOBBY WARD NSIC MAYS,G NUDOCS FULL TXT COPIES LTTR ENCL'1 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, RAOil PI-37 (EXT.20079)TO FI.IXIINATE YOUR NAP!E I ROTI DISTRIBUTION LISTS I.OR DOCUXIENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 r~Mf (Indiana michigan Paar er Corn pany Cook Nuclear Plan~One Cook Piece Bridgman.MI 49306 616 465 5901 INDMNA MlCHlaaN PONt'R January 11, 1991 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-75 Docket No.50-316 Document Control Manager: Xn accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem the following report is being submitted: | | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| 90-012-00 Sincerely, A.A.Blind Plant Manager AAB:sb Attachment c'P-;PPP g D.H.Williams, Jr.A.B.Davis, Region III M.P.Alexich P.A.Barrett J.E.Borggren R.F.Kroeger B.Walters-Ft.Wayne NRC Resident Inspector T.Colburn-NRC J.G.Keppler M.R.Padgett G.Charnoff, Esq.Dottie Sherman, ANI Library D.Hahn INPO S.J.Brewer/B.P.
| | ENCL 'IZE: |
| Lauzau B.A.Svensson~gO)d')C'/rgb F,i Jgf 83 f9% | | NOTES: |
| NRC FORM 366 (BSD)U.S.NUCLEAR REGULATORY COMMISSION LlCENSEE EVENT REPORT (LER)APPROVED OMS NO.31604104 EXPIRES: CISOIB2 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 60J)HRS.FORWARD COMMENTS REQAROINQ BURDFN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P030).U.S.NUCLEAR REGULATORY COMMISSION. | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' PD3-1 LA 1 1 PD3-1 PD 1 COLBURN,T. 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DS P 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 LB8D1 1 1 NRR/DST/SRXB 8E 1 1 G F 02 1 1 RES/DSXR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL EG &G BRYCE I J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, RAOil PI-37 (EXT. 20079) TO FI.IXIINATEYOUR NAP!E I ROTI DISTRIBUTION LISTS I.OR DOCUXIENTS YOU DON'T NEED! |
| WASHINGTON. | | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 |
| DC 20666, AND TO THE PAPERWORK REDUCTION PROJECT (31600'IOC). | | |
| OFFICE OF MANAQFMENT ANO BUDGET, WASHINGTON. | | ( |
| DC 20603 FACILITY NAME lll D.C, Cook Nuclear Plant-Unit 2 DOCKET NUMBER 121 PA 6 0 5 0 0 0 3 1 6 1 OFO Reactor Protection System Actuation (-aused by a Steam-to-ceedwater Flow Nismatch in Combination with Low Steam Generator Level EVKNT DATE (5)LER NVMSER (6l REPORT DATF.O)OTHER FACILITIKS INVOLVED ISI MONTH DAY YEAR YEAR@~M;.56OUDNTtAL i~n)NVMDDII (SS"6"0 MONTH NVMODR DAY YEAR r*CILITY NAMES DOCXET NUMBER(3)0 5 0 0 0 1 2 1 2 90 90 0 1 2 000 1 9 1 0 5 0 0 0 OPERATINQ MODE (Dl 1 POWER LEvEL 1 0 0 20A02(D)20A00(c)(1)(B 20A054)(1)(5) 20A054)(I)(61)20ACB lc)l1)(Ir I 20A054)Ill(rl 20A05(c)50M(c)(I I 50.35(cll2) 50.734)l2)(II IN.1 3 4 I (1 I I 6 I 50.734)(1)BII) 6073(c)(2) | | Indiana michigan r~ Paar er Corn pany Mf Cook Nuclear Plan~ |
| Vr)50.734)(1)4) 60.73(r I (2)lrD I 50.734)(2)lr)IIIIAI 50.73(cl(2)(rIDI(SI 50.734)l1)(cl THIS REPORT IS SUBMITTFD tVRSUANT TO THE REQUIREMENTS Of 10 CFR ()t ICnrcn onr orms ot tnrtoDo~ti (111 73.7)(6)73.71(c)OTHER ISprcitt In AOtpoct Dcccw rmt In I'rrt, HRC fcnn 36SAJ NAME LICENSEE CONTACT FOR THIS LER (12)F.Carteaux-Safety and Assessment Superintendent TELEPHONE NVMSEII AREA CODE 61 646 5-901 COMPLETE ONK LINE FOR EACH COMtONENT fAILURE DESCRIBED IN THIS REPORT)13)CAUSE SYSTEM COMPONENT MANUFAC.TUNER EPORTABLE TO NPROS F6&4 CAUSK SYSTEM CQMtONENT MANVFAC.TURER Nurg'Pn.~))3)NJPPLEMENTAL REPORT EXPECTED IW EXPECTED SUBMISSION DATE (16)OAY YEAR YKS III yrt.con pirrr EXPECTED SVdltlSSIDH OA tdi NO ABSTRACT IL(mlt to tc()0 lprcrt, I.r., rpptocntrrtrtr Iittrrn pntlr.tooer trprtnrtttrn Imrti (16)On December 12, 1990 at 0318 hours, the Unit 2 reactor tripped as a result of steam-to-feedwater flow mismatch (difference between steam and feed flows on one of two measured channels of each parameter for a steam generator (SG))in coincidence with low SG level (one of two SG narrow range channels for a SG)conditions in the number 4 SG.These conditions arose following a trip of one of the two Turbine Driven Main Feedwater Pumps (TD-MFWP)due to an erroneous actuation of the turbine thrust bearing wear/shaft position detection alarm and trip device.No malfunctions of safety-related systems or components occurred.The turbine thrust bearing wear/shaft position detection device was removed from the MFWP turbine driver and inspected.
| | One Cook Piece Bridgman. MI 49306 616 465 5901 INDMNA MlCHlaaN PONt'R January 11, 1991 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-75 Docket No. 50-316 Document Control Manager: |
| This device, and the similar device on the other turbine driver, were bench calibrated and properly set-up on the MFWP turbines at turning gear and no-load operating speeds.NRC Porto 366 (BBD)
| | Xn accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem the following report is being submitted: |
| I NRC FORM 366A)669)I U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILER)TEXT CONTINUATION APPROY EO OM6 NO.3150010l EXPIR'ESI ll30)92 ESTIMATEO SUROEN PER RFSPONSE TO COMPLY WTH THIS INFORMATION COLLFCTION REOUESTI 50O HRS.FORWARO COMMENTS REGAROING SUROEN ESTIMATE TO THE RECOROS ANO REPORTS MANAGEMENT SRANCH IP630), U.S.NVCLEAR REGULATORY COMMISSION.
| | 90-012-00 Sincerely, A.A. Blind Plant Manager AAB:sb Attachment D.H. Williams, Jr. |
| WASHINGTON, OC 20555, ANO TO 1)IE PAPERWORK REDUCTION PRO)ECT (3)50410l).
| | A.B. Davis, Region M.P. Alexich III P.A. Barrett J.E. Borggren R.F. Kroeger B. Walters Ft. Wayne NRC Resident Inspector T. Colburn NRC J.G. Keppler M.R. Padgett G. Charnoff, Esq. |
| OFFICE OF MANAGF MENT ANO SUOGET,VIASHINGTON,OC20503.
| | Dottie Sherman, ANI Library D. Hahn INPO S.J. Brewer/B.P. Lauzau '/rgb c'P-;PPP B.A. Svensson F,i Jgf 83 f9% |
| 'ACILITY NAME ll)COCKET NVMSER 12)LER NUMSER (6)560USNTIAI)y>.NUMO5 A"i I IIEY'ISION NUMO f 4 PAGE 131 D.C.Cook Nucleat Plant-Unit 2 TEXT N mo>>)of co If>>Ouuod.uw ouoeooff NRC%%dnn 366AY)l)T)Q 6 Q Q Q 3 9 0-0 1 2 00 02"0 Conditions Prior to Occurence Unit 2 in Node 1 at 100 percent of Rated Thermal Power (RTP).Descri tio of Event At approximately 0318 hours on December 12, 1990 the Unit 2 (U2)West MFWP (EXIS/SJ-P) turbine (EIIS/SJ-TRB) tz'ipped due to a signal from the turbine thrust beaz'ing wear/shaft position detector device (EIIS/JK-38).
| | ~ gO) g d')C |
| The Operators responded to the control room annunciators (EIIS/XB)by starting an additional condensate boostez pump (EIZS/SD-P)(to assist the remaining MFWP), manually increased speed of the remaining MFWP, and began reducing unit power in an attempt to keep the unit on line.However, in the 43 seconds that ensued between the West MFWP turbine trip and reactor trip,, they were not able to offset the loss of one MFWP at the existing unit power level and the mismatch in steam-to-feedwater flow (EXXS/JF-FFS)coincident with low steam generator (EIIS/AB-BLR) level (EIXS/JE-LS)(all in the loop 4 SG)initiated the reactor trip.Opening of the reactor trip breakers (EXXS/JE-BKR), tuzbine trip (EXIS/TA-TRB), control rod insertion, feedwater isolation (EXIS/JB), and automatic starting (EIZS/JB}of the two MDAFPFs (EIIS/BA-P} | | |
| and the TDAFP(EIIS/BA-P) occurred as expected.Operating personnel concurrently performed the applicable Emergency Operating Procedures (EOPs')to verify proper automatic protection system responses and assess appropriate recovery actions for the indicated plant conditions. | | NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO. 31604104 (BSD) |
| Cause o the Event The event is believed to have resulted from some combination of the following three factors related to the Hest MFWP tuzbine shaft position device: Improper adjustment of the device during installation and/or later trouble-shooting, leaving the device with much less than the expected margin to'trip, 2~3~Shifting of the device on the turbine as a result of normal vibration despite the hold-down bolts, Foreign material becoming trapped (or wedged)between the shaft thrust bearing face and the sliding shoe (which rides on the face).NRC FonII 366A (569) | | EXPIRES: CISOIB2 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 60J) HRS. FORWARD LlCENSEE EVENT REPORT (LER) COMMENTS REQAROINQ BURDFN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENTBRANCH (P030). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20666, AND TO THE PAPERWORK REDUCTION PROJECT (31600'IOC). OFFICE OF MANAQFMENTANO BUDGET, WASHINGTON. DC 20603 FACILITY NAME lll DOCKET NUMBER 121 PA 6 D. C, Cook Nuclear Plant Unit 2 0 5 0 0 0 3 1 6 1 OFO Reactor Protection System Actuation (-aused by a Steam-to-ceedwater Flow Nismatch in Combination with Low Steam Generator Level EVKNT DATE (5) LER NVMSER (6l REPORT DATF. O) OTHER FACILITIKSINVOLVED ISI MONTH DAY YEAR YEAR 56OUDNTtAL i~n) "6"0 MONTH DAY YEAR r*CILITYNAMES DOCXET NUMBER(3) |
| NRC FOAM 368A 16491 U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVEO OM8 NO.3150010i EXPIRES: C130/93 E5TIMATEO SUAOEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 500 HRS.FORWARO COMMENTS AEGAROING SUAOEN ESTIMATE TO THE RECOROS ANO REPORTS MANAGEMENT BRANCH IP430), U.S.NUCLEAR RE'GULATORY COMMISSION. | | @~M;. NVMDDII (SS NVMODR 0 5 0 0 0 1 2 1 2 90 90 0 1 2 000 1 9 1 0 5 0 0 0 OPERATINQ THIS REPORT IS SUBMITTFD tVRSUANT TO THE REQUIREMENTS Of 10 CFR ()t ICnrcn onr orms ot tnrtoDo~ti (111 MODE (Dl 1 20A02(D) 20A05(c) 6073(c)(2) Vr) 73.7) (6) |
| WASHINGTON. | | POWER 20A00(c)(1) (B 50M(c) (I I 50.734)(1)4) 73.71(c) |
| OC 30555.ANO TO THE PAPERWORK AEOUCTION PROJECT I31500IOCI. | | LEvEL 1 0 0 20A054)(1)(5) 50.35(cll2) 60.73(r I (2) lrDI OTHER ISprcitt In AOtpoct Dcccw rmt In I'rrt, HRC fcnn 20A054) (I)(61) 50.734) l2)(II 50.734)(2)lr)IIIIAI 36SAJ 20ACB lc) l1 ) (IrI IN.1 3 4 I (1 I I 6 I 50.73(cl(2)(rIDI(SI 20A054) Ill(rl 50.734)(1)BII) 50.734) l1)(cl LICENSEE CONTACT FOR THIS LER (12) |
| OFI'ICE OF MANAGEMENT ANO SUOGET.WASHINGTON, OC 30503.FACILITY NAME III COCKET NUMSER 131 LER NUMSEA (SI SEQUENTIAL NVMOEA AEVOION NVMOSA PAGE IJ)D.C.Cook Nuclear Plant-Unit 2 TEXT ill cooco cpoco e neurrd.Pco acAotioool NRC Form 355ASI IIT)0 5 0 0 0 3 9 0 0 1 2 0 0 03 OF 0 4 These BBC shaft position devices are supposed to be calibrated as part of their manufacturing process, however the post-trip inspection disclosed that all the adjusting screws had been moved from their initial settings.This may have occurred when the device was initially set-up on 0he turbine during the refueling overhaul, or later during trouble-shooting on the device with the turbine in operation. | | NAME TELEPHONE NVMSEII AREA CODE F. Carteaux Safety and Assessment Superintendent 61 646 5- 901 COMPLETE ONK LINE FOR EACH COMtONENT fAILURE DESCRIBED IN THIS REPORT )13) |
| The west MFWP had been overhauled during the refueling with the assistance of the equipment vendor.However, it can not be determined from records if the device had been set as required with the MFWP turbine on turning gear and again at no-load operating speed conditions. | | Nurg Pn CAUSE SYSTEM COMPONENT MANUFAC. |
| Also, eight days after the initial U2 power ascension following the refueling, the shaft position alarm (EIIS/IB-ZA) began intermittently alarming in the control room.The position device was checked locally (at the turbine)and was indicating "0LI deflection. | | TUNER EPORTABLE TO NPROS F6&4 CAUSK SYSTEM CQMtONENT MANVFAC. |
| Other indications of bearing problems, such as excessive temperature or vibration, also did not exist (for both the alarm problem and the later trip).Plant maintenance personnel at that time tried to adjust the device while it was installed on the MFWP (with it's trip function disabled)using vendor information for guidance.At that time the device was left with free travel in the"+" and"-" directions of shaft motion.Folloving the trip, the device was found with it's travel in the"+" direction entirely used up.The investigation of the device indicated no reason vhy it would suddenly shift from a"trip free" to a"hard trip" condition as all adjustment screws vere found tight.The device is bolted to the thrust bearing housing with two hold-down bolts.The post-trip inspection found some foreign material on the sliding shoe.Anal sis of Event This report is being submitted in accordance with 10 CFR 50.73, paragraph (a)(2)(iv} | | TURER |
| as a result of the unplanned actuation of the Unit 2 RPS and ESF.The automatic protection functions vere verified to have functioned properly.The event did not involve an unreviewed safety question as defined in 10 CFR 50.59 paragraph (a)(2), and did not adversely impact the health and safety of the public.Corrective Action The shaft position device was removed from the W-MFWP turbine driver and inspected. | | .~))3) |
| This device, and the similar device on the E-MFWP turbine driver, were then bench calibrated and properly set-up on the MFWP turbines at turning gear and no-load operating NAC Form 3SSA IS SSI NRC FORM 366A I609)\U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVEOOMS NO.31500)04 EXPIRES: el30192 ESTIMATEO SUROEN PER RESPONSE TO COMPLY WTH THIS INFORMATION CO(.'LECT)ON R'EQUFSTI 500 HRS, FORWARO COMMENTS REGAROING SUROEN ESTIMATE TO THE RECOROS ANO REPORTS MANAGEMENT SRANCH (F030).U.S.NUCLEAR REGULATORY IMMISSION. | | NJPPLEMENTAL REPORT EXPECTED IW OAY YEAR EXPECTED SUBMISSION DATE (16) |
| WASHINGTON. | | YKS IIIyrt. con pirrr EXPECTED SVdltlSSIDH OA tdi NO ABSTRACT IL(mlt to tc()0 lprcrt, I.r., rpptocntrrtrtr Iittrrn pntlr.tooer trprtnrtttrn Imrti (16) |
| OC 20555.ANO TO 1HE PAI'ERWORK REOUC'TION PRO)ECT (3)500)0(I. | | On December 12, 1990 at 0318 hours, the Unit 2 reactor tripped as a result of steam-to-feedwater flow mismatch (difference between steam and feed flows on one of two measured channels of each parameter for a steam generator (SG)) in coincidence with low SG level (one of two SG narrow range channels for a SG) conditions in the number 4 SG. These conditions arose following a trip of one of the two Turbine Driven Main Feedwater Pumps (TD-MFWP) due to an erroneous actuation of the turbine thrust bearing wear/shaft position detection alarm and trip device. No malfunctions of safety-related systems or components occurred. |
| OFFICE OF MANAGEMENT ANO SUOGET, WASHINGTON, OC 20503.FACILITY NAME (1)OOCKET NUMSER (2)YEAR LEA NUMSER (Sl SSOVSNTIAL NVMSER REVISION NVMSSR IrAOE (3)D.C.Cook Nuclear Plant-Unit 2 TExT lit more apace re>>purred, u>>eooe'oool AIRc%%drm 366Asl ()7)o s o o o 3 1 6 9 0 0 1 2 00 04 oF 0 speeds.Lock washers were used with the hold-down bolts for the device on the W-MFWP when it was re-installed, following the post-trip calibration, on the H-MFHP.To prevent recurrence no adjustments of these devices will be attempted while mounted on an operating MFWP turbine.A plant procedure, incorporating the appropriate vendor instructions will be developed to assure the calibration and set-up is done properly.Failed Com onent Identification Manufacturer: | | The turbine thrust bearing wear/shaft position detection device was removed from the MFWP turbine driver and inspected. This device, and the similar device on the other turbine driver, were bench calibrated and properly set-up on the MFWP turbines at turning gear and no-load operating speeds. |
| Model No: EIIS Code: Plant I.D.No.: 2-138-BSPW (Unit 2, West Main Feed Pump Turbine, OME-84W, Thrust Hear Test Open Limit Switch)Brown-Boveri (BBC)Shaft Position Supervisor, drawing no.HTGD 90-142 EIIS/JK-38 revious Si i ar Events None.NRC Purer 3SSA (669)}}
| | NRC Porto 366 (BBD) |
| | |
| | I NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROY EO OM6 NO. 3150010l |
| | )669) EXPIR'ESI ll30)92 I |
| | ESTIMATEO SUROEN PER RFSPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLFCTION REOUESTI 50O HRS. FORWARO COMMENTS REGAROING SUROEN ESTIMATE TO THE RECOROS TEXT CONTINUATION ANO REPORTS MANAGEMENT SRANCH IP630), U.S. NVCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, ANO TO 1)IE PAPERWORK REDUCTION PRO)ECT (3)50410l). OFFICE OF MANAGFMENT ANO SUOGET,VIASHINGTON,OC20503. |
| | NAME ll) COCKET NVMSER 12) LER NUMSER (6) PAGE 131 'ACILITY 560USNTIAI )y>. IIEY'ISION NUMO5 A "i I NUMO f 4 D. C. Cook Nucleat Plant Unit 2 Q 6 Q Q Q 3 9 0 0 1 2 00 02 "0 TEXT N mo>> )ofco If >>Ouuod. uw ouoeooff NRC %%dnn 366AY) l)T) |
| | Conditions Prior to Occurence Unit 2 in Node 1 at 100 percent of Rated Thermal Power (RTP) . |
| | Descri tio of Event At approximately 0318 hours on December 12, 1990 the Unit 2 (U2) |
| | West MFWP (EXIS/SJ-P) turbine (EIIS/SJ-TRB) tz'ipped due to a signal from the turbine thrust beaz'ing wear/shaft position detector device (EIIS/JK-38). The Operators responded to the control room annunciators (EIIS/XB) by starting an additional condensate boostez pump (EIZS/SD-P) (to assist the remaining MFWP), manually increased speed of the remaining MFWP, and began reducing unit power in an attempt to keep the unit on line. However, in the 43 seconds that ensued between the West MFWP turbine trip and reactor trip,, they were not able to offset the loss of one MFWP at the existing unit power level and the mismatch in steam-to-feedwater flow (EXXS/JF-FFS) coincident with low steam generator (EIIS/AB-BLR) level (EIXS/JE-LS) (all in the loop 4 SG) initiated the reactor trip. |
| | Opening of the reactor trip breakers (EXXS/JE-BKR), tuzbine trip (EXIS/TA-TRB), control rod insertion, feedwater isolation (EXIS/JB), and automatic starting (EIZS/JB} of the two MDAFPFs (EIIS/BA-P} and the TDAFP(EIIS/BA-P) occurred as expected. |
| | Operating personnel concurrently performed the applicable Emergency Operating Procedures (EOPs') to verify proper automatic protection system responses and assess appropriate recovery actions for the indicated plant conditions. |
| | Cause o the Event The event is believed to have resulted from some combination of the following three factors related to the Hest MFWP tuzbine shaft position device: |
| | Improper adjustment of the device during installation and/or later trouble-shooting, leaving the device with much less than the expected margin to 'trip, 2 ~ Shifting of the device on the turbine as a result of normal vibration despite the hold-down bolts, 3 ~ Foreign material becoming trapped (or wedged) between the shaft thrust bearing face and the sliding shoe (which rides on the face). |
| | NRC FonII 366A (569) |
| | |
| | NRC FOAM 368A U.S. NUCLEAR REGULATORY COMMISSION 16491 APPROVEO OM8 NO. 3150010i EXPIRES: C130/93 E5TIMATEO SUAOEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 500 HRS. FORWARO COMMENTS AEGAROING SUAOEN ESTIMATE TO THE RECOROS TEXT CONTINUATION ANO REPORTS MANAGEMENTBRANCH IP430), U.S. NUCLEAR RE'GULATORY COMMISSION. WASHINGTON. OC 30555. ANO TO THE PAPERWORK AEOUCTION PROJECT I31500IOCI. OFI'ICE OF MANAGEMENTANO SUOGET. WASHINGTON, OC 30503. |
| | FACILITY NAME III COCKET NUMSER 131 LER NUMSEA (SI PAGE IJ) |
| | SEQUENTIAL AEVOION NVMOEA NVMOSA D. C. Cook Nuclear Plant - Unit 2 0 5 0 0 0 3 9 0 0 1 2 0 0 03 OF 0 4 TEXT illcooco cpoco e neurrd. Pco acAotioool NRC Form 355ASI IIT) |
| | These BBC shaft position devices are supposed to be calibrated as part of their manufacturing process, however the post-trip inspection disclosed that all the adjusting screws had been moved from their initial settings. This may have occurred when the device was initially set-up on 0he turbine during the refueling overhaul, or later during trouble-shooting on the device with the turbine in operation. The west MFWP had been overhauled during the refueling with the assistance of the equipment vendor. However, can not be determined from records if the device had been set as it required with the MFWP turbine on turning gear and again at no-load operating speed conditions. Also, eight days after the initial U2 power ascension following the refueling, the shaft position alarm (EIIS/IB-ZA) began intermittently alarming in the control room. |
| | The position device was checked locally (at the turbine) and was indicating "0LI deflection. Other indications of bearing problems, such as excessive temperature or vibration, also did not exist (for both the alarm problem and the later trip). Plant maintenance personnel at that time tried to adjust the device while installed on the MFWP (with it's trip function disabled) using it was vendor information for guidance. At that time the device was left with free travel in the "+" and "-" directions of shaft motion. |
| | Folloving the trip, the device was found with it's travel in the |
| | "+" direction entirely used up. The investigation of the device indicated no reason vhy it would suddenly shift from a "trip free" to a "hard trip" condition as all adjustment screws vere found tight. The device is bolted to the thrust bearing housing with two hold-down bolts. The post-trip inspection found some foreign material on the sliding shoe. |
| | Anal sis of Event This report is being submitted in accordance with 10 CFR 50.73, paragraph (a)(2)(iv} as a result of the unplanned actuation of the Unit 2 RPS and ESF. |
| | The automatic protection functions vere verified to have functioned properly. The event did not involve an unreviewed safety question as defined in 10 CFR 50.59 paragraph (a) (2), and did not adversely impact the health and safety of the public. |
| | Corrective Action The shaft position device was removed from the W-MFWP turbine driver and inspected. This device, and the similar device on the E-MFWP turbine driver, were then bench calibrated and properly set-up on the MFWP turbines at turning gear and no-load operating NAC Form 3SSA IS SSI |
| | |
| | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION I609) APPROVEOOMS NO.31500)04 |
| | \ EXPIRES: el30192 ESTIMATEO SUROEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION CO(.'LECT)ON R'EQUFSTI 500 HRS, FORWARO COMMENTS REGAROING SUROEN ESTIMATE TO THE RECOROS TEXT CONTINUATION ANO REPORTS MANAGEMENT SRANCH (F030). U.S. NUCLEAR REGULATORY IMMISSION. WASHINGTON. OC 20555. ANO TO 1HE PAI'ERWORK REOUC'TION PRO)ECT (3)500)0(I. OFFICE OF MANAGEMENTANO SUOGET, WASHINGTON, OC 20503. |
| | FACILITY NAME (1) OOCKET NUMSER (2) LEA NUMSER (Sl IrAOE (3) |
| | YEAR SSOVSNTIAL REVISION NVMSER NVMSSR D. C. Cook Nuclear Plant - Unit 2 o s o o o 3 1 6 9 0 0 1 2 00 04 oF 0 TExT litmore apace re>>purred, u>> eooe'oool AIRc %%drm 366Asl ()7) speeds. Lock washers were used with the hold-down bolts for the device on the W-MFWP when trip calibration, on the H-MFHP. |
| | it was re-installed, following the post-To prevent recurrence no adjustments of these devices will be attempted while mounted on an operating MFWP turbine. A plant procedure, incorporating the appropriate vendor instructions will be developed to assure the calibration and set-up is done properly. |
| | Failed Com onent Identification Plant I.D. No.: 2-138-BSPW (Unit 2, West Main Feed Pump Turbine, OME-84W, Thrust Hear Test Open Limit Switch) |
| | Manufacturer: Brown-Boveri (BBC) |
| | Model No: Shaft Position Supervisor, drawing no. HTGD 90-142 EIIS Code: EIIS/JK-38 revious Si i ar Events None. |
| | NRC Purer 3SSA (669)}} |
Similar Documents at Cook |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:RO)
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr
ML17335A5481999-09-30030 September 1999
Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3).
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17326A0871999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5491999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B4631999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr
ML17325B4621999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
1999-09-30
[Table view] |
Text
ACCELERATED DISTRIBUTION DEMONS REGULATORY XNFORMATION DISTRIBUTION SYSTEM,.(RIDS)
ACCESSION NBR:9101160001 DOC.DATE'1/01/11 NOTARIZED: NO DOCKET FACIL:50-316 Do Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION CARTEAUX P.F. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele BLIND,A.A. Xndiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 90-012-00:on 901212,reactor tripped as result of steam-to-feedwater flow mismatch & one turbine-driven main feedwater pump tripped due to erroneous actuation of thrust bearing. Bearing bench calibr.W/910111 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
ENCL 'IZE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' PD3-1 LA 1 1 PD3-1 PD 1 COLBURN,T. 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DS P 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 LB8D1 1 1 NRR/DST/SRXB 8E 1 1 G F 02 1 1 RES/DSXR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL EG &G BRYCE I J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, RAOil PI-37 (EXT. 20079) TO FI.IXIINATEYOUR NAP!E I ROTI DISTRIBUTION LISTS I.OR DOCUXIENTS YOU DON'T NEED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31
(
Indiana michigan r~ Paar er Corn pany Mf Cook Nuclear Plan~
One Cook Piece Bridgman. MI 49306 616 465 5901 INDMNA MlCHlaaN PONt'R January 11, 1991 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-75 Docket No. 50-316 Document Control Manager:
Xn accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem the following report is being submitted:
90-012-00 Sincerely, A.A. Blind Plant Manager AAB:sb Attachment D.H. Williams, Jr.
A.B. Davis, Region M.P. Alexich III P.A. Barrett J.E. Borggren R.F. Kroeger B. Walters Ft. Wayne NRC Resident Inspector T. Colburn NRC J.G. Keppler M.R. Padgett G. Charnoff, Esq.
Dottie Sherman, ANI Library D. Hahn INPO S.J. Brewer/B.P. Lauzau '/rgb c'P-;PPP B.A. Svensson F,i Jgf 83 f9%
~ gO) g d')C
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO. 31604104 (BSD)
EXPIRES: CISOIB2 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 60J) HRS. FORWARD LlCENSEE EVENT REPORT (LER) COMMENTS REQAROINQ BURDFN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENTBRANCH (P030). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20666, AND TO THE PAPERWORK REDUCTION PROJECT (31600'IOC). OFFICE OF MANAQFMENTANO BUDGET, WASHINGTON. DC 20603 FACILITY NAME lll DOCKET NUMBER 121 PA 6 D. C, Cook Nuclear Plant Unit 2 0 5 0 0 0 3 1 6 1 OFO Reactor Protection System Actuation (-aused by a Steam-to-ceedwater Flow Nismatch in Combination with Low Steam Generator Level EVKNT DATE (5) LER NVMSER (6l REPORT DATF. O) OTHER FACILITIKSINVOLVED ISI MONTH DAY YEAR YEAR 56OUDNTtAL i~n) "6"0 MONTH DAY YEAR r*CILITYNAMES DOCXET NUMBER(3)
@~M;. NVMDDII (SS NVMODR 0 5 0 0 0 1 2 1 2 90 90 0 1 2 000 1 9 1 0 5 0 0 0 OPERATINQ THIS REPORT IS SUBMITTFD tVRSUANT TO THE REQUIREMENTS Of 10 CFR ()t ICnrcn onr orms ot tnrtoDo~ti (111 MODE (Dl 1 20A02(D) 20A05(c) 6073(c)(2) Vr) 73.7) (6)
POWER 20A00(c)(1) (B 50M(c) (I I 50.734)(1)4) 73.71(c)
LEvEL 1 0 0 20A054)(1)(5) 50.35(cll2) 60.73(r I (2) lrDI OTHER ISprcitt In AOtpoct Dcccw rmt In I'rrt, HRC fcnn 20A054) (I)(61) 50.734) l2)(II 50.734)(2)lr)IIIIAI 36SAJ 20ACB lc) l1 ) (IrI IN.1 3 4 I (1 I I 6 I 50.73(cl(2)(rIDI(SI 20A054) Ill(rl 50.734)(1)BII) 50.734) l1)(cl LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NVMSEII AREA CODE F. Carteaux Safety and Assessment Superintendent 61 646 5- 901 COMPLETE ONK LINE FOR EACH COMtONENT fAILURE DESCRIBED IN THIS REPORT )13)
Nurg Pn CAUSE SYSTEM COMPONENT MANUFAC.
TUNER EPORTABLE TO NPROS F6&4 CAUSK SYSTEM CQMtONENT MANVFAC.
TURER
.~))3)
NJPPLEMENTAL REPORT EXPECTED IW OAY YEAR EXPECTED SUBMISSION DATE (16)
YKS IIIyrt. con pirrr EXPECTED SVdltlSSIDH OA tdi NO ABSTRACT IL(mlt to tc()0 lprcrt, I.r., rpptocntrrtrtr Iittrrn pntlr.tooer trprtnrtttrn Imrti (16)
On December 12, 1990 at 0318 hours0.00368 days <br />0.0883 hours <br />5.257936e-4 weeks <br />1.20999e-4 months <br />, the Unit 2 reactor tripped as a result of steam-to-feedwater flow mismatch (difference between steam and feed flows on one of two measured channels of each parameter for a steam generator (SG)) in coincidence with low SG level (one of two SG narrow range channels for a SG) conditions in the number 4 SG. These conditions arose following a trip of one of the two Turbine Driven Main Feedwater Pumps (TD-MFWP) due to an erroneous actuation of the turbine thrust bearing wear/shaft position detection alarm and trip device. No malfunctions of safety-related systems or components occurred.
The turbine thrust bearing wear/shaft position detection device was removed from the MFWP turbine driver and inspected. This device, and the similar device on the other turbine driver, were bench calibrated and properly set-up on the MFWP turbines at turning gear and no-load operating speeds.
NRC Porto 366 (BBD)
I NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROY EO OM6 NO. 3150010l
)669) EXPIR'ESI ll30)92 I
ESTIMATEO SUROEN PER RFSPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLFCTION REOUESTI 50O HRS. FORWARO COMMENTS REGAROING SUROEN ESTIMATE TO THE RECOROS TEXT CONTINUATION ANO REPORTS MANAGEMENT SRANCH IP630), U.S. NVCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, ANO TO 1)IE PAPERWORK REDUCTION PRO)ECT (3)50410l). OFFICE OF MANAGFMENT ANO SUOGET,VIASHINGTON,OC20503.
NAME ll) COCKET NVMSER 12) LER NUMSER (6) PAGE 131 'ACILITY 560USNTIAI )y>. IIEY'ISION NUMO5 A "i I NUMO f 4 D. C. Cook Nucleat Plant Unit 2 Q 6 Q Q Q 3 9 0 0 1 2 00 02 "0 TEXT N mo>> )ofco If >>Ouuod. uw ouoeooff NRC %%dnn 366AY) l)T)
Conditions Prior to Occurence Unit 2 in Node 1 at 100 percent of Rated Thermal Power (RTP) .
Descri tio of Event At approximately 0318 hours0.00368 days <br />0.0883 hours <br />5.257936e-4 weeks <br />1.20999e-4 months <br /> on December 12, 1990 the Unit 2 (U2)
West MFWP (EXIS/SJ-P) turbine (EIIS/SJ-TRB) tz'ipped due to a signal from the turbine thrust beaz'ing wear/shaft position detector device (EIIS/JK-38). The Operators responded to the control room annunciators (EIIS/XB) by starting an additional condensate boostez pump (EIZS/SD-P) (to assist the remaining MFWP), manually increased speed of the remaining MFWP, and began reducing unit power in an attempt to keep the unit on line. However, in the 43 seconds that ensued between the West MFWP turbine trip and reactor trip,, they were not able to offset the loss of one MFWP at the existing unit power level and the mismatch in steam-to-feedwater flow (EXXS/JF-FFS) coincident with low steam generator (EIIS/AB-BLR) level (EIXS/JE-LS) (all in the loop 4 SG) initiated the reactor trip.
Opening of the reactor trip breakers (EXXS/JE-BKR), tuzbine trip (EXIS/TA-TRB), control rod insertion, feedwater isolation (EXIS/JB), and automatic starting (EIZS/JB} of the two MDAFPFs (EIIS/BA-P} and the TDAFP(EIIS/BA-P) occurred as expected.
Operating personnel concurrently performed the applicable Emergency Operating Procedures (EOPs') to verify proper automatic protection system responses and assess appropriate recovery actions for the indicated plant conditions.
Cause o the Event The event is believed to have resulted from some combination of the following three factors related to the Hest MFWP tuzbine shaft position device:
Improper adjustment of the device during installation and/or later trouble-shooting, leaving the device with much less than the expected margin to 'trip, 2 ~ Shifting of the device on the turbine as a result of normal vibration despite the hold-down bolts, 3 ~ Foreign material becoming trapped (or wedged) between the shaft thrust bearing face and the sliding shoe (which rides on the face).
NRC FonII 366A (569)
NRC FOAM 368A U.S. NUCLEAR REGULATORY COMMISSION 16491 APPROVEO OM8 NO. 3150010i EXPIRES: C130/93 E5TIMATEO SUAOEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 500 HRS. FORWARO COMMENTS AEGAROING SUAOEN ESTIMATE TO THE RECOROS TEXT CONTINUATION ANO REPORTS MANAGEMENTBRANCH IP430), U.S. NUCLEAR RE'GULATORY COMMISSION. WASHINGTON. OC 30555. ANO TO THE PAPERWORK AEOUCTION PROJECT I31500IOCI. OFI'ICE OF MANAGEMENTANO SUOGET. WASHINGTON, OC 30503.
FACILITY NAME III COCKET NUMSER 131 LER NUMSEA (SI PAGE IJ)
SEQUENTIAL AEVOION NVMOEA NVMOSA D. C. Cook Nuclear Plant - Unit 2 0 5 0 0 0 3 9 0 0 1 2 0 0 03 OF 0 4 TEXT illcooco cpoco e neurrd. Pco acAotioool NRC Form 355ASI IIT)
These BBC shaft position devices are supposed to be calibrated as part of their manufacturing process, however the post-trip inspection disclosed that all the adjusting screws had been moved from their initial settings. This may have occurred when the device was initially set-up on 0he turbine during the refueling overhaul, or later during trouble-shooting on the device with the turbine in operation. The west MFWP had been overhauled during the refueling with the assistance of the equipment vendor. However, can not be determined from records if the device had been set as it required with the MFWP turbine on turning gear and again at no-load operating speed conditions. Also, eight days after the initial U2 power ascension following the refueling, the shaft position alarm (EIIS/IB-ZA) began intermittently alarming in the control room.
The position device was checked locally (at the turbine) and was indicating "0LI deflection. Other indications of bearing problems, such as excessive temperature or vibration, also did not exist (for both the alarm problem and the later trip). Plant maintenance personnel at that time tried to adjust the device while installed on the MFWP (with it's trip function disabled) using it was vendor information for guidance. At that time the device was left with free travel in the "+" and "-" directions of shaft motion.
Folloving the trip, the device was found with it's travel in the
"+" direction entirely used up. The investigation of the device indicated no reason vhy it would suddenly shift from a "trip free" to a "hard trip" condition as all adjustment screws vere found tight. The device is bolted to the thrust bearing housing with two hold-down bolts. The post-trip inspection found some foreign material on the sliding shoe.
Anal sis of Event This report is being submitted in accordance with 10 CFR 50.73, paragraph (a)(2)(iv} as a result of the unplanned actuation of the Unit 2 RPS and ESF.
The automatic protection functions vere verified to have functioned properly. The event did not involve an unreviewed safety question as defined in 10 CFR 50.59 paragraph (a) (2), and did not adversely impact the health and safety of the public.
Corrective Action The shaft position device was removed from the W-MFWP turbine driver and inspected. This device, and the similar device on the E-MFWP turbine driver, were then bench calibrated and properly set-up on the MFWP turbines at turning gear and no-load operating NAC Form 3SSA IS SSI
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION I609) APPROVEOOMS NO.31500)04
\ EXPIRES: el30192 ESTIMATEO SUROEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION CO(.'LECT)ON R'EQUFSTI 500 HRS, FORWARO COMMENTS REGAROING SUROEN ESTIMATE TO THE RECOROS TEXT CONTINUATION ANO REPORTS MANAGEMENT SRANCH (F030). U.S. NUCLEAR REGULATORY IMMISSION. WASHINGTON. OC 20555. ANO TO 1HE PAI'ERWORK REOUC'TION PRO)ECT (3)500)0(I. OFFICE OF MANAGEMENTANO SUOGET, WASHINGTON, OC 20503.
FACILITY NAME (1) OOCKET NUMSER (2) LEA NUMSER (Sl IrAOE (3)
YEAR SSOVSNTIAL REVISION NVMSER NVMSSR D. C. Cook Nuclear Plant - Unit 2 o s o o o 3 1 6 9 0 0 1 2 00 04 oF 0 TExT litmore apace re>>purred, u>> eooe'oool AIRc %%drm 366Asl ()7) speeds. Lock washers were used with the hold-down bolts for the device on the W-MFWP when trip calibration, on the H-MFHP.
it was re-installed, following the post-To prevent recurrence no adjustments of these devices will be attempted while mounted on an operating MFWP turbine. A plant procedure, incorporating the appropriate vendor instructions will be developed to assure the calibration and set-up is done properly.
Failed Com onent Identification Plant I.D. No.: 2-138-BSPW (Unit 2, West Main Feed Pump Turbine, OME-84W, Thrust Hear Test Open Limit Switch)
Manufacturer: Brown-Boveri (BBC)
Model No: Shaft Position Supervisor, drawing no. HTGD 90-142 EIIS Code: EIIS/JK-38 revious Si i ar Events None.
NRC Purer 3SSA (669)
