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| | issue date = 05/05/1987 | | | issue date = 05/05/1987 |
| | title = LER 87-010-00:on 870322 & 0426,water Flow Switch Fire Detectors Identified Inoperable.Caused by Eroded Flow Sensing Mechanism.Two Detectors Replaced & Remaining Units Will Be replaced.W/870505 Ltr | | | title = LER 87-010-00:on 870322 & 0426,water Flow Switch Fire Detectors Identified Inoperable.Caused by Eroded Flow Sensing Mechanism.Two Detectors Replaced & Remaining Units Will Be replaced.W/870505 Ltr |
| | author name = JOHNSON B D, KOZUP C S | | | author name = Johnson B, Kozup C |
| | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:--,, ,_,-. ...: .. : .... | | {{#Wiki_filter:- - ,, ,_,- ....: ..: .... ~~*-** ... - |
| ... -NllCl'orlll-19-all LICENSEE EVENT REPORT (LER) U.I. NUCLIAll lllGULATOllY A-OYED Ollll NO. 31!!0-0ICM EXPllllH: | | NllCl'orlll- U.I. NUCLIAll lllGULATOllY ~-ION 19-all A-OYED Ollll NO. 31!!0-0ICM EXPllllH: 1131 Ill LICENSEE EVENT REPORT (LER) |
| 1131 Ill FACILITY NAME 111 IDOCKIT --.11121 I Ill! PALISADES NUCLEAR PLANT o 15 Io I 0 Io I 21 515 1 loF 0 I 3 TITLE 141 INOPERABLE WATER FLOW SWITCHES ASSOCIATED WITH FIRE PROTECTION SYSTEM IYINT DATI Ill Liii Ill lllP'OllT DATE 171 OTHEll 'ACILITIU llNOLVID lal fACILITY NAMU DOCKET NUMIElllll N/A o I 3 212 s 1 s 11 -o 11 I o -o I o o I 5. o I 5 s 11 N/A 01S1D1D1D1 I I ONllATING THll llDOllT 11 IUlllllTTED l'UlllUANT TO THI lllOUlllEMINTI OF 10 C'll §: one or,,,.,,.. | | FACILITY NAME 111 IDOCKIT --.11121 I p-~R Ill! |
| of tn. fellowkrf} | | PALISADES NUCLEAR PLANT o 15 Io I 0 Io I 21 515 1 loF 0 I 3 TITLE 141 INOPERABLE WATER FLOW SWITCHES ASSOCIATED WITH FIRE PROTECTION SYSTEM IYINT DATI Ill Liii N~lll Ill lllP'OllT DATE 171 OTHEll 'ACILITIU llNOLVID lal fACILITY NAMU DOCKET NUMIElllll N/A oI3 212 s 1 s 11 - o 11 I o - o I o oI5. o I 5 s 11 N/A 01S1D1D1D1 I I ONllATING THll llDOllT 11 IUlllllTTED l'UlllUANT TO THI lllOUlllEMINTI OF 10 C'll §: I~ one or,,,.,,.. of tn. fellowkrf} 1111 N |
| 1111 MOOE Ill N .,_ _____ | | .,__MOOE I |
| 20.41121111 1--ZO.<IOl!lal | | __ Ill_ _..__"""-~ 20.41121111 1-- ZO.<IOl!lal _ I0.71W112lllwl _ 71.71111 POWEii :llO*.C.1111Cll IO *111111 *.nlallZllwl 7J.711el L~~~L 0 I0 I Q - ao.a1111111111 1-- . . . |
| _ I0.71W112lllwl | | 1-- IO.*CallZI I0.7Sloll211Ylll -;;" OTHlll 16-1"' 1,, Ab1eKr |
| _ 71.71111 POWEii I :llO * .C.1111Cll IO *111111 *.nlallZllwl 7J.711el 0 I 0 I Q -ao.a1111111111 1--. . . -I0.7Sloll211Ylll | | """""' ....... eM /11 Tur. NllC Fomt zumc.11111110 .._ ID.7Jlel121(11 - ...7:111111211YlllllAI .mA.1 NAME |
| -;;" OTHlll 16-1"' 1,, Ab1eKr 1--IO.*CallZI | | - I0.7:1111121101 I0.7Jlal 12111111 LICENIEE CONTACT FOii THll LEll 1121 I0.7111112Jl.aUll91 I0.7Slell211*1 Special Report TELll'HONI NUMIElll AREA CODE CSKozup, Technical Engineer, Palisades 6I 11 6 7 16 I 4 1- 18 I 9 1113 COMPLETE ONE LINE '011 EACH COW'ONENT PAILUlll DEIClllllD IN THll lllP'OllT llJI CAUSE SYSTEM COMPONENT x I I I y I I I I I I I I I I I I I I I I I I I I I IU'l'LEMENTAL lllP'OllT l!Xl'ECTED 11'1 MONTH . DAY l!Xl'ICTID n YES (If l'W. - - fXl'fCTfO StJ*MIS$/ON DATE) |
| -"""""' ....... eM /11 Tur. NllC Fomt zumc.11111110 NAME .._ ID.7Jlel121(11
| | IUIMllllON DATE 11111 I I I AalTllACT 11.imlt ID 14/JO - |
| -... 7:111111211YlllllAI .mA.1 I0.7:1111121101 | | * l.t., -*lmntly ,,,_ rlllf/H1>>ff ty-1mn tin*) 1111 Abstract. |
| -I0.7Jlal 12111111 LICENIEE CONTACT FOii THll LEll 1121 I0.7111112Jl.aUll91 I0.7Slell211*1 AREA CODE Special Report TELll'HONI NUMIElll CSKozup, Technical Engineer, Palisades 6 I 11 6 7 1 6 I 4 1 -1 8 I 9 1 113 COMPLETE ONE LINE '011 EACH COW'ONENT PAILUlll DEIClllllD IN THll lllP'OllT llJI CAUSE SYSTEM COMPONENT x I I I y I I I I I I I IU'l'LEMENT AL lllP'OllT l!Xl'ECTED 11'1 n YES (If l'W. --fXl'fCTfO StJ*MIS$/ON DATE) AalTllACT 11.imlt ID 14/JO -* l.t., -*lmntly ,,,_ rlllf/H1>>ff ty-1mn tin*) 1111 Abstract.
| | On both March 22 and April 26, 1987, two water flow switch fire detectors were |
| I I I I I I I I I I I I I I l!Xl'ICTID IUIMllllON DATE 11111 MONTH . DAY I I On both March 22 and April 26, 1987, two water flow switch fire detectors were *identified to be inoperable by Operations personnel.
| | *identified to be inoperable by Operations personnel. The Plant was in hot shutdown condition on March 22 and at full reactor power on April 26. |
| The Plant was in hot shutdown condition on March 22 and at full reactor power on April 26. The detectors maintained under a static water pressure of 100 psig. When flow is sensed, a alarm is received in the Control Room indicating fire protection system actuation. | | The detectors a~e maintained under a static water pressure of 100 psig. When flow is sensed, a alarm is received in the Control Room indicating fire protection system actuation. The flow is initiated when the.fusible link associated with the sprinkler heads melt due to exposure to heat. |
| The flow is initiated when the.fusible link associated with the sprinkler heads melt due to exposure to heat. New detectors have been installed for detectors WFS-2B and WFS-2G2 which failed on March 22. Detector WFS-2Gl will be replaced by May 8 and WFS-2Bl as soon as parts are available. | | New detectors have been installed for detectors WFS-2B and WFS-2G2 which failed on March 22. Detector WFS-2Gl will be replaced by May 8 and WFS-2Bl as soon as parts are available. Due to the nature of failure being associated with.end of service life, all water flow switch fire detectors identified in Technical Specifications are to be replaced. |
| Due to the nature of failure being associated with.end of service life, all water flow switch fire detectors identified in Technical Specifications are to be replaced. | | S7051ADOCK2 0018 870505 05000255 PDR PDR s |
| NllCF_ .. (11-831 2 0018 870505 S7051ADOCK 05000255 PDR PDR s LER 87-010 I | | NllCF_ . . |
| _ . ___ --**---' . " <* : > ' .. . | | (11-831 LER 87-010 |
| *: :: | | |
| *-* ..-_._ LICENSEE EVENT REPORT (LERI TEXT CONTINUATION . *'' .. | | _. ___ --**- ---~ ::~-=----_--~~-~~- ":-_.,~.~._0;*~*~*-:~;;-;1W;;%!.)R33?:i~i:~lt~*-~"¥£$ITtn~fl;If.}J!.bTli~'~';(f~~~i&~~;.~:.*:\~;~;~'~****,:I*~Ih:~cl~~*J~:. |
| '-: --* | | ~ - -' . " <* :>' .. ~ . ?;:*,*{:~~~-:~~ *: :: *-,~ *- |
| * ' ' . ' EXPIRES: 8131 /BS ...-.:_: --.. : < :'* FACILITY NAME 111 Palisades Nuclear Plant *:, . TEXT (If -.,_,. -. requltetl, -Ntl/rionel NRC Form .-A '111171 * .: Description DOCKET NUMBER IZI . .' . 'LUI NuMIEll 111 -**r* '*. _l'-,--* *** \. o o* b a* oi= * 'o 3 *, *.*.* | | LICENSEE EVENT REPORT (LERI TEXT CONTINUATION |
| 22, 1987, while performing a quarterly flow. alarm operability, Operations personnel | | - * :\::~~c'**;:::::E:~~~;;!t:lllON |
| **_switch | | . *'' . ~:~''."'*: '-: ~ |
| <' detectors WFS-2B_ and WFS-2G2 [KP ;FIS] were | | *' '. ' EXPIRES: 8131 /BS . .-.:_: - -.. : <:'* |
| ..... .h9t condition (primary coolant system: 2033 psia, s32 | | FACILITY NAME 111 DOCKET NUMBER IZI . .' . 'LUI NuMIEll 111 - |
| .. *w1fell:'.;tli.e:.*"d'E!tectors we're. -determined to be inoperable.
| | **r* '*. |
| .. | | Palisades Nuclear Plant |
| * _ _,,,:," _, -. :_*;:}T< _ The: detectors are Notifier, model NVR-2BZ and are normall'f-maint:ained | | *:, _l'-,- - * *** \. |
| *under a stafic -water pressure of approximately 100 psig. The Fire | | o o* b a* oi= *'o 3 |
| -(FPS) with these detectors is actuated by the melting of .the heads. . When a fusible link releases' it causes the spray head' :pressure to drop a . pilot valve to open. Water is then permitted to pass through' :the water flow switch fire detectors which sense the flow and annunciate in the Control Room. Subsequent to the March 22. detector failures, two additional detectors, WFS-2Gl and WFS-2Bl, were identified to be inoperable during the performance of a Technical Specification Surveillance Test on April 26. On April 26 a.fire watch patrol was initiated within one hour of the inoperable declaration. | | . TEXT (If - .,_,. -. requltetl, - Ntl/rionel NRC Form .-A '111171 |
| Cause of the Event The failure of the water flow switch fire detectors identified above was caused by erosion of the flow sensing mechanism (ie, flapper). | | * .: Description o~*:March 22, 1987, while performing a quarterly tesf**~{).;:'~r"ift~~£fi~~y;~ppre$sion: ;~i'~t~m flow. alarm operability, Operations personnel identif~~4. .t~~e*;i~~¥~r.,'.~'.f~~~ **_switch :;~~+/-~e: <' |
| This erosion is believed to have been propagated by the detectors being exposed to approximately 100 pounds of static water pressure during their service life. It is believed 'that these failures resulted due* to the equipment reaching the end of its service life. | | detectors WFS-2B_ and WFS-2G2 [KP ;FIS] were inoperable~~ .....Tlie,Jtl~n;,.:~asj-ln .h9t .,shu~~9wn condition (primary coolant system: 2033 psia, s32 ''d'~sl:e~sY. *w1fell:'.;tli.e:.*"d'E!tectors we're. - |
| | determined to be inoperable. -..~:~~J,,"~~;~;i'.:D. {;~t~t~~:}:;~;~*.;:;i~':'._.-: *__,, :," ~: _, -. :_*;:}T< _ |
| | The: detectors are Notifier, model NVR-2BZ and are normall'f-maint:ained *under a stafic - |
| | water pressure of approximately 100 psig. The Fire P*1d;*te_~t~o~;;~$ys~em -(FPS) *associ~'i:e-d with these detectors is actuated by the melting of ~'~fusilfie;~'.linl(:within .the --~p~f~er heads. . When a fusible link releases' it causes the spray head' :pressure to drop ~nd a |
| | . pilot valve to open. Water is then permitted to pass through' :the water flow switch fire detectors which sense the flow and annunciate in the Control Room. |
| | Subsequent to the March 22. detector failures, two additional detectors, WFS-2Gl and WFS-2Bl, were identified to be inoperable during the performance of a Technical Specification Surveillance Test on April 26. On April 26 a.fire watch patrol was initiated within one hour of the inoperable declaration. |
| | Cause of the Event The failure of the water flow switch fire detectors identified above was caused by erosion of the flow sensing mechanism (ie, flapper). This erosion is believed to have been propagated by the detectors being exposed to approximately 100 pounds of static water pressure during their service life. I t is believed 'that these failures resulted due* to the equipment reaching the end of its service life. |
| * The detectors were | | * The detectors were |
| * original Plant installed equipment, which until their failure of 22 and April .26, performed their designed function. | | * original Plant installed equipment, which until their failure of ~arch 22 and April |
| Corrective Action Plant Technical Specification | | .26, performed their designed function. |
| : 3. 22 .1, Fire Detection Ins.trumentation,, :.requires that when detectors are inoperable, within one hour, establish .a f.ire:'watch patrol to inspect the zones with the inoperable instruments at least once per_ hour until the detector is returned.to service. This fire watch patrol was estab:+ished as specified for the zones governed by the detectors which were dec.lared*:i:D.9p:arabi.e*
| | Corrective Action Plant Technical Specification 3. 22 .1, Fire Detection Ins.trumentation,, :.requires that when detectors are inoperable, within one hour, establish .a f.ire:'watch patrol to inspect the zones with the inoperable instruments at least once per_ hour until the detector is returned.to service. This fire watch patrol was estab:+ished as specified for the zones governed by the detectors which were dec.lared*:i:D.9p:arabi.e* on-April 26. |
| on-April 26. However, for the detectors identified to be inoperable*: | | However, for the detectors identified to be inoperable*: on MB.r~h'.,22:; ::the fire watch patrol was not initiated until April 20. This failure '.to'*'ill:f:tiate.. th.is fire watch patrol as specified is under investigation and will be det.lii:iled i1La separate Licensee |
| on | | _Event Report to be submitted by May 20 as required by, .10CFR50~73~--:*" ._*:. |
| ::the fire watch patrol was not initiated until April 20. This failure '.to'*'ill:f:tiate | | - ..--*~ --~ -. ~ ,~~~:.*.:~~.t!~~,~.:¥;.~::_S{;~~~i\ ~-~~~:.~~:~;/~~'.::::*:*:;~~~~? ._: . |
| .. th.is fire watch patrol as specified is under investigation and will be det.lii:iled i1La separate Licensee _Event Report to be submitted by May 20 as required by, | | New detectors have been installed for WFS-2B and WFS-2G2~;*: **A*~::rep1:8:cf!~Ut det.ector for WFS-2Gl is to be installed by May 8. Replacement of WFS...:2Bl'':w~ll:~~ l:completed in a |
| ._*:. -. | | * timely fashion when parts are available. Fire patro:i"watchea** wil!':be maintained until this replacement is complete. Due to the nature of failure ident.ified -for the detectors being associated with end of service life, additional ~etectors ~re being ordered and will be installed upon arrival for the remaining like~*detectors identified in Technical Specifications. .!!~~(<:,,.:,! |
| --. | | NllC FORM 386A 19 |
| ._: . New detectors have been installed for WFS-2B and det.ector for WFS-2Gl is to be installed by May 8. Replacement of l:completed in a | | ~ER 87-010-NL02 |
| * timely fashion when parts are available. | | |
| Fire patro:i"watchea** | | NRC Farm..,_ U.1. NUCLEAR llEOULATORV COMMISSION C9-(3l LICENSEE EVENT REPORT (LER) TEXT;C::()NTINUATION . APPROVED OMll ND. 3160--0104 EXPIRES: 8/31 /85 |
| wil!':be maintained until this replacement is complete. | | 'f FACILITV NAME 111 DOCKET NUMaEll 121 LEA NUMBER Cll PAGE C3l J;>alisades Nuclear Plant o 1s 101<1.101~~2(51 5; 817 - 01110 - o Io 013 OF o 13 TEXT f/I , _ - t. tflqllitwJ, - eddltioMI NllC Fonn ,-..**11171 The repla~ement detectors are equipped with a nqn-ferrous flapper and connecting ' |
| Due to the nature of failure ident.ified -for the detectors being associated with end of service life, additional being ordered and will be installed upon arrival for the remaining identified in Technical Specifications. | | mechanism to eliminate the possibility of a similar-failure. ' |
| NllC FORM 386A 87-010-NL02 | | Analysis Of The Event -. _ . , .. |
| ,.-.' ---------------------
| | Operability of the fire *detec'tiori_ instrumentation ensures that adequate warning capability is available *:ftjr*- the prompt detection~'of :'£°ires. This capability is requir~.~ in order ~o detect:and l()cate tirer;i ,in:_*'~Q.-~i-~**::*early stages. Prompt detection o:f''f :l..res' will reduce 'the' potential' for damage '1:6' 'safety..:related equipment and is an int regal element in the overall facility*' fir~ .protec~ion program. |
| *, .:.'"
| | In the eve~t that a portion of the fire deted:ion instrumentation is inoperable, the establishment of frequent fire patrols in the affected.areas is required to provide detection capability until the inoperable instrumentation is returned to service. |
| 'f . . . .*
| | The intent and requirements of Technical Specifications have been met for the April 26 failure, thus, no additional hazard was presented. During the period between March 22 and April 20, no fire watch patrol was maintained, nor were fire detection capabilities maintained for zones associated with detectors WFS-2B and WFS-2G2 (ie, the cable spreading room and the 1-2 diesel generator room). The effects of this lack of detection will be detailed in the separate LER to be submitted by May 20. |
| * NRC Farm..,_ C9-(3l LICENSEE EVENT REPORT (LER) TEXT;C::()NTINUATION U.1. NUCLEAR llEOULATORV COMMISSION . APPROVED OMll ND. 3160--0104 EXPIRES: 8/31 /85 FACILITV NAME 111 DOCKET NUMaEll 121 LEA NUMBER Cll PAGE C3l J;>alisades Nuclear Plant o 1s 5; 817 -01110 -o Io 013 OF o 13 TEXT f/I ,_ -t. tflqllitwJ, -eddltioMI NllC Fonn ,-..**11171 The detectors are equipped with a nqn-ferrous flapper and connecting
| | NllC FOllM 3118A CH3.l...ER 87-010 |
| ' mechanism to eliminate the possibility of a similar-failure.
| | |
| ' Analysis Of The Event -. _ . , .. -**' * .. ,. -.-' Operability of the fire *detec'tiori_
| | consumers Power POWERING llAICHl&AN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (51-7) 788-0550 May 5, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - |
| instrumentation ensures that adequate warning capability is available | | LICENSEE EVENT REPORT 87-010 - INOPERABLE WATER FLOW SWITCHES ASSOCIATED WITH THE FIRE DETECTION SYSTEM Licensee Event Report (LER) 87-010, (Inoperable Water Flow Switches Associated With The Fire Detection System) is attached. This event is being submitted as a Special Report in accordance with Palisades Technical Specification 3.22.1. |
| *:ftjr*-the prompt | | Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident In$pector - Palisades Attachment OC0587-0056-NL02}} |
| :'£°ires. | |
| This capability is in order detect:and l()cate tirer;i stages. Prompt detection o:f''f :l..res' will reduce 'the' potential' for damage '1:6' 'safety..:related equipment and is an int regal element in the overall facility*' | |
| program. In the that a portion of the fire deted:ion instrumentation is inoperable, the establishment of frequent fire patrols in the affected.areas is required to provide detection capability until the inoperable instrumentation is returned to service. The intent and requirements of Technical Specifications have been met for the April 26 failure, thus, no additional hazard was presented. | |
| During the period between March 22 and April 20, no fire watch patrol was maintained, nor were fire detection capabilities maintained for zones associated with detectors WFS-2B and WFS-2G2 (ie, the cable spreading room and the 1-2 diesel generator room). The effects of this lack of detection will be detailed in the separate LER to be submitted by May 20. NllC FOllM 3118A CH3.l...ER 87-010 | |
| * consumers Power POWERING llAICHl&AN'S PROGRESS
| |
| * General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (51-7) 788-0550 May 5, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -LICENSEE EVENT REPORT 87-010 -INOPERABLE WATER FLOW SWITCHES ASSOCIATED WITH THE FIRE DETECTION SYSTEM Licensee Event Report (LER) 87-010, (Inoperable Water Flow Switches Associated With The Fire Detection System) is attached.
| |
| This event is being submitted as a Special Report in accordance with Palisades Technical Specification 3.22.1. Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident In$pector | |
| -Palisades Attachment OC0587-0056-NL02}} | |
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18066A6271999-09-0202 September 1999
LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr
ML18066A6221999-08-20020 August 1999
LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr
ML18066A3781999-01-20020 January 1999
LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr
ML18068A4851998-10-29029 October 1998
LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18066A2831998-08-18018 August 1998
LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
ML18066A2261998-06-30030 June 1998
LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A1781998-06-0909 June 1998
LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
ML18065B2451998-05-13013 May 1998
LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
ML18065B1151997-12-0909 December 1997
LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability
ML18067A7751997-11-11011 November 1997
LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved
ML18067A7581997-10-30030 October 1997
LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation
ML18067A7461997-10-23023 October 1997
LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure.
ML18067A7191997-10-10010 October 1997
LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed
ML18067A6951997-09-24024 September 1997
LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts
ML18067A5651997-06-0303 June 1997
LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested
ML18067A5461997-05-12012 May 1997
LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities
ML18067A4431997-03-24024 March 1997
LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS
ML18067A4391997-03-21021 March 1997
LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired
ML18067A4401997-03-21021 March 1997
LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr
ML18066A8931997-02-21021 February 1997
LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr
ML18066A8751997-02-0505 February 1997
LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr
ML18066A8041996-12-23023 December 1996
LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment
ML18066A7831996-12-16016 December 1996
LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced
ML18065A9951996-10-0404 October 1996
LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg
ML18065A9171996-09-0909 September 1996
LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr
ML18065A8961996-08-29029 August 1996
LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments
ML18065A8811996-08-20020 August 1996
LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced
ML18065A8741996-08-16016 August 1996
LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected
ML18065A8651996-08-12012 August 1996
LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr
ML18065A8601996-08-0202 August 1996
LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit
ML18065A8321996-08-0101 August 1996
LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board
ML18065A7691996-06-12012 June 1996
LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr
ML18065A6901996-05-0101 May 1996
LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr
ML18065A6681996-04-22022 April 1996
LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr
ML18065A5721996-03-11011 March 1996
LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded
ML18065A5261996-03-0101 March 1996
LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr
ML18065A5111996-02-19019 February 1996
LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr
ML18065A5061996-02-19019 February 1996
LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts
ML18065A5021996-02-15015 February 1996
LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr
ML18065A4581996-01-31031 January 1996
LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr
ML18065A4421996-01-19019 January 1996
LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr
ML18065A4041996-01-15015 January 1996
LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr
ML18065A3291995-12-0404 December 1995
LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr
ML18065A2361995-11-0202 November 1995
LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr
ML18065A2051995-10-20020 October 1995
LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised
ML18065A0841995-09-18018 September 1995
LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr
ML18065A0681995-09-14014 September 1995
LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line
ML18065A0651995-09-0808 September 1995
LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment
ML18064A8781995-08-28028 August 1995
LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage
ML18064A8831995-08-21021 August 1995
LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr
1999-09-02
[Table view]
Category:RO)
MONTHYEARML18066A6271999-09-0202 September 1999
LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr
ML18066A6221999-08-20020 August 1999
LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr
ML18066A3781999-01-20020 January 1999
LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr
ML18068A4851998-10-29029 October 1998
LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18066A2831998-08-18018 August 1998
LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
ML18066A2261998-06-30030 June 1998
LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A1781998-06-0909 June 1998
LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
ML18065B2451998-05-13013 May 1998
LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
ML18065B1151997-12-0909 December 1997
LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability
ML18067A7751997-11-11011 November 1997
LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved
ML18067A7581997-10-30030 October 1997
LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation
ML18067A7461997-10-23023 October 1997
LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure.
ML18067A7191997-10-10010 October 1997
LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed
ML18067A6951997-09-24024 September 1997
LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts
ML18067A5651997-06-0303 June 1997
LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested
ML18067A5461997-05-12012 May 1997
LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities
ML18067A4431997-03-24024 March 1997
LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS
ML18067A4391997-03-21021 March 1997
LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired
ML18067A4401997-03-21021 March 1997
LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr
ML18066A8931997-02-21021 February 1997
LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr
ML18066A8751997-02-0505 February 1997
LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr
ML18066A8041996-12-23023 December 1996
LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment
ML18066A7831996-12-16016 December 1996
LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced
ML18065A9951996-10-0404 October 1996
LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg
ML18065A9171996-09-0909 September 1996
LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr
ML18065A8961996-08-29029 August 1996
LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments
ML18065A8811996-08-20020 August 1996
LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced
ML18065A8741996-08-16016 August 1996
LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected
ML18065A8651996-08-12012 August 1996
LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr
ML18065A8601996-08-0202 August 1996
LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit
ML18065A8321996-08-0101 August 1996
LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board
ML18065A7691996-06-12012 June 1996
LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr
ML18065A6901996-05-0101 May 1996
LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr
ML18065A6681996-04-22022 April 1996
LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr
ML18065A5721996-03-11011 March 1996
LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded
ML18065A5261996-03-0101 March 1996
LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr
ML18065A5111996-02-19019 February 1996
LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr
ML18065A5061996-02-19019 February 1996
LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts
ML18065A5021996-02-15015 February 1996
LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr
ML18065A4581996-01-31031 January 1996
LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr
ML18065A4421996-01-19019 January 1996
LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr
ML18065A4041996-01-15015 January 1996
LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr
ML18065A3291995-12-0404 December 1995
LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr
ML18065A2361995-11-0202 November 1995
LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr
ML18065A2051995-10-20020 October 1995
LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised
ML18065A0841995-09-18018 September 1995
LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr
ML18065A0681995-09-14014 September 1995
LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line
ML18065A0651995-09-0808 September 1995
LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment
ML18064A8781995-08-28028 August 1995
LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage
ML18064A8831995-08-21021 August 1995
LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr
1999-09-02
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999
Rev 5 to Palisades Nuclear Plant Colr.
ML18066A6761999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant
ML18066A6271999-09-0202 September 1999
LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr
ML18066A6351999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant
ML18066A6771999-08-31031 August 1999
Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant
ML18066A6221999-08-20020 August 1999
LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr
ML18066A6061999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr
ML18066A5201999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr
ML18066A4841999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr
ML18066A6371999-04-30030 April 1999
Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant
ML18068A5941999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr
ML18066A4161999-04-0101 April 1999
Rev 4 to COLR, for Palisades Nuclear Plant
ML18066A4501999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr
ML18066A4671999-03-31031 March 1999
Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant.
ML18068A5351999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr
ML18066A3931999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr
ML18066A3781999-01-20020 January 1999
LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr
ML20206F6131998-12-31031 December 1998
1998 Consumers Energy Co Annual Rept. with
ML18066A3651998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr
ML18066A3421998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr
ML18066A3301998-11-11011 November 1998
Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used
ML18068A4921998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr
ML18068A4851998-10-29029 October 1998
LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18066A3181998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant
ML18066A2901998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr
ML18066A3191998-08-31031 August 1998
Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant
ML18066A2831998-08-18018 August 1998
LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML20237E0301998-07-31031 July 1998
ISI Rept 3-3
ML18066A2701998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr
ML18066A2311998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Palisades Nuclear Plant
ML18066A2261998-06-30030 June 1998
LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A3061998-06-18018 June 1998
SG Tube Inservice Insp.
ML20249C4951998-06-17017 June 1998
Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review
ML18066A1781998-06-0909 June 1998
LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures
ML18066A1711998-06-0101 June 1998
Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46
ML18066A1741998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr
ML18066A2321998-05-31031 May 1998
Revised MOR for May 1998 for Palisades Nuclear Plant
ML18068A4701998-05-31031 May 1998
Annual Rept of Changes in ECCS Models Per 10CFR50.46.
ML18065B2451998-05-13013 May 1998
LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge
ML18066A2331998-04-30030 April 1998
Revised MOR for Apr 1998 for Palisades Nuclear Plant
ML18068A3461998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr
ML18066A3411998-04-22022 April 1998
Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events.
ML18065B2071998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr
ML20217C2741998-03-31031 March 1998
Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts
ML18066A2341998-03-31031 March 1998
Revised MOR for Mar 1998 for Palisades Nuclear Plant
ML18068A3041998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr
ML18066A2351998-02-28028 February 1998
Revised MOR for Feb 1998 for Palisades Nuclear Plant
ML18065B1641998-02-0505 February 1998
Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance.
ML18067A8211998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr
1999-09-30
[Table view] |
Text
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NllCl'orlll- U.I. NUCLIAll lllGULATOllY ~-ION 19-all A-OYED Ollll NO. 31!!0-0ICM EXPllllH: 1131 Ill LICENSEE EVENT REPORT (LER)
FACILITY NAME 111 IDOCKIT --.11121 I p-~R Ill!
PALISADES NUCLEAR PLANT o 15 Io I 0 Io I 21 515 1 loF 0 I 3 TITLE 141 INOPERABLE WATER FLOW SWITCHES ASSOCIATED WITH FIRE PROTECTION SYSTEM IYINT DATI Ill Liii N~lll Ill lllP'OllT DATE 171 OTHEll 'ACILITIU llNOLVID lal fACILITY NAMU DOCKET NUMIElllll N/A oI3 212 s 1 s 11 - o 11 I o - o I o oI5. o I 5 s 11 N/A 01S1D1D1D1 I I ONllATING THll llDOllT 11 IUlllllTTED l'UlllUANT TO THI lllOUlllEMINTI OF 10 C'll §: I~ one or,,,.,,.. of tn. fellowkrf} 1111 N
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- I0.7:1111121101 I0.7Jlal 12111111 LICENIEE CONTACT FOii THll LEll 1121 I0.7111112Jl.aUll91 I0.7Slell211*1 Special Report TELll'HONI NUMIElll AREA CODE CSKozup, Technical Engineer, Palisades 6I 11 6 7 16 I 4 1- 18 I 9 1113 COMPLETE ONE LINE '011 EACH COW'ONENT PAILUlll DEIClllllD IN THll lllP'OllT llJI CAUSE SYSTEM COMPONENT x I I I y I I I I I I I I I I I I I I I I I I I I I IU'l'LEMENTAL lllP'OllT l!Xl'ECTED 11'1 MONTH . DAY l!Xl'ICTID n YES (If l'W. - - fXl'fCTfO StJ*MIS$/ON DATE)
IUIMllllON DATE 11111 I I I AalTllACT 11.imlt ID 14/JO -
- l.t., -*lmntly ,,,_ rlllf/H1>>ff ty-1mn tin*) 1111 Abstract.
On both March 22 and April 26, 1987, two water flow switch fire detectors were
- identified to be inoperable by Operations personnel. The Plant was in hot shutdown condition on March 22 and at full reactor power on April 26.
The detectors a~e maintained under a static water pressure of 100 psig. When flow is sensed, a alarm is received in the Control Room indicating fire protection system actuation. The flow is initiated when the.fusible link associated with the sprinkler heads melt due to exposure to heat.
New detectors have been installed for detectors WFS-2B and WFS-2G2 which failed on March 22. Detector WFS-2Gl will be replaced by May 8 and WFS-2Bl as soon as parts are available. Due to the nature of failure being associated with.end of service life, all water flow switch fire detectors identified in Technical Specifications are to be replaced.
S7051ADOCK2 0018 870505 05000255 PDR PDR s
NllCF_ . .
(11-831 LER 87-010
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LICENSEE EVENT REPORT (LERI TEXT CONTINUATION
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- ' '. ' EXPIRES: 8131 /BS . .-.:_: - -.. : <:'*
FACILITY NAME 111 DOCKET NUMBER IZI . .' . 'LUI NuMIEll 111 -
Palisades Nuclear Plant
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. TEXT (If - .,_,. -. requltetl, - Ntl/rionel NRC Form .-A '111171
- .: Description o~*:March 22, 1987, while performing a quarterly tesf**~{).;:'~r"ift~~£fi~~y;~ppre$sion: ;~i'~t~m flow. alarm operability, Operations personnel identif~~4. .t~~e*;i~~¥~r.,'.~'.f~~~ **_switch :;~~+/-~e: <'
detectors WFS-2B_ and WFS-2G2 [KP ;FIS] were inoperable~~ .....Tlie,Jtl~n;,.:~asj-ln .h9t .,shu~~9wn condition (primary coolant system: 2033 psia, s32 d'~sl:e~sY. *w1fell:'.;tli.e:.*"d'E!tectors we're. -
determined to be inoperable. -..~:~~J,,"~~;~;i'.:D. {;~t~t~~:}:;~;~*.;:;i~':'._.-: *__,, :," ~: _, -. :_*;:}T< _
The: detectors are Notifier, model NVR-2BZ and are normall'f-maint:ained *under a stafic -
water pressure of approximately 100 psig. The Fire P*1d;*te_~t~o~;;~$ys~em -(FPS) *associ~'i:e-d with these detectors is actuated by the melting of ~'~fusilfie;~'.linl(:within .the --~p~f~er heads. . When a fusible link releases' it causes the spray head' :pressure to drop ~nd a
. pilot valve to open. Water is then permitted to pass through' :the water flow switch fire detectors which sense the flow and annunciate in the Control Room.
Subsequent to the March 22. detector failures, two additional detectors, WFS-2Gl and WFS-2Bl, were identified to be inoperable during the performance of a Technical Specification Surveillance Test on April 26. On April 26 a.fire watch patrol was initiated within one hour of the inoperable declaration.
Cause of the Event The failure of the water flow switch fire detectors identified above was caused by erosion of the flow sensing mechanism (ie, flapper). This erosion is believed to have been propagated by the detectors being exposed to approximately 100 pounds of static water pressure during their service life. I t is believed 'that these failures resulted due* to the equipment reaching the end of its service life.
- original Plant installed equipment, which until their failure of ~arch 22 and April
.26, performed their designed function.
Corrective Action Plant Technical Specification 3. 22 .1, Fire Detection Ins.trumentation,, :.requires that when detectors are inoperable, within one hour, establish .a f.ire:'watch patrol to inspect the zones with the inoperable instruments at least once per_ hour until the detector is returned.to service. This fire watch patrol was estab:+ished as specified for the zones governed by the detectors which were dec.lared*:i:D.9p:arabi.e* on-April 26.
However, for the detectors identified to be inoperable*: on MB.r~h'.,22:; ::the fire watch patrol was not initiated until April 20. This failure '.to'*'ill:f:tiate.. th.is fire watch patrol as specified is under investigation and will be det.lii:iled i1La separate Licensee
_Event Report to be submitted by May 20 as required by, .10CFR50~73~--:*" ._*:.
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New detectors have been installed for WFS-2B and WFS-2G2~;*: **A*~::rep1:8:cf!~Ut det.ector for WFS-2Gl is to be installed by May 8. Replacement of WFS...:2Bl:w~ll:~~ l:completed in a
- timely fashion when parts are available. Fire patro:i"watchea** wil!':be maintained until this replacement is complete. Due to the nature of failure ident.ified -for the detectors being associated with end of service life, additional ~etectors ~re being ordered and will be installed upon arrival for the remaining like~*detectors identified in Technical Specifications. .!!~~(<:,,.:,!
NllC FORM 386A 19
~ER 87-010-NL02
NRC Farm..,_ U.1. NUCLEAR llEOULATORV COMMISSION C9-(3l LICENSEE EVENT REPORT (LER) TEXT;C::()NTINUATION . APPROVED OMll ND. 3160--0104 EXPIRES: 8/31 /85
'f FACILITV NAME 111 DOCKET NUMaEll 121 LEA NUMBER Cll PAGE C3l J;>alisades Nuclear Plant o 1s 101<1.101~~2(51 5; 817 - 01110 - o Io 013 OF o 13 TEXT f/I , _ - t. tflqllitwJ, - eddltioMI NllC Fonn ,-..**11171 The repla~ement detectors are equipped with a nqn-ferrous flapper and connecting '
mechanism to eliminate the possibility of a similar-failure. '
Analysis Of The Event -. _ . , ..
Operability of the fire *detec'tiori_ instrumentation ensures that adequate warning capability is available *:ftjr*- the prompt detection~'of :'£°ires. This capability is requir~.~ in order ~o detect:and l()cate tirer;i ,in:_*'~Q.-~i-~**::*early stages. Prompt detection o:ff :l..res' will reduce 'the' potential' for damage '1:6' 'safety..:related equipment and is an int regal element in the overall facility*' fir~ .protec~ion program.
In the eve~t that a portion of the fire deted:ion instrumentation is inoperable, the establishment of frequent fire patrols in the affected.areas is required to provide detection capability until the inoperable instrumentation is returned to service.
The intent and requirements of Technical Specifications have been met for the April 26 failure, thus, no additional hazard was presented. During the period between March 22 and April 20, no fire watch patrol was maintained, nor were fire detection capabilities maintained for zones associated with detectors WFS-2B and WFS-2G2 (ie, the cable spreading room and the 1-2 diesel generator room). The effects of this lack of detection will be detailed in the separate LER to be submitted by May 20.
NllC FOllM 3118A CH3.l...ER 87-010
consumers Power POWERING llAICHl&AN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (51-7) 788-0550 May 5, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
LICENSEE EVENT REPORT 87-010 - INOPERABLE WATER FLOW SWITCHES ASSOCIATED WITH THE FIRE DETECTION SYSTEM Licensee Event Report (LER)87-010, (Inoperable Water Flow Switches Associated With The Fire Detection System) is attached. This event is being submitted as a Special Report in accordance with Palisades Technical Specification 3.22.1.
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident In$pector - Palisades Attachment OC0587-0056-NL02
