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| {{#Wiki_filter:* 0119 llO. | | {{#Wiki_filter:llii'------------------------------"'7li11iii~~U~A:L"::.:11:1;.~LUl~UGUU::::::::~TOll;nY;"'Q;:::;.:c:Ol":-1 |
| LICENSEE EVENT REPORT (LERI IXNtU: 1n11* PM:IUT'f'
| | * ~ID 0119 llO. J1~10il LICENSEE EVENT REPORT (LERI IXNtU: 1n11* |
| ..... 111 I DOClln .-.. m 1 *-* ,.,. PALISADES NUCLEAR PLANT o I 5 Io *Io Io I 2 t 51 5 1 loF 0 15 TITU i. IN-PROGRESS PLANT DEB.ATE RESULTS IN FAILURE TO PERFORM REQUIRED SURVEILLANCE IVINT DA ft Ill OTMlll PACIUTIU *VOLVID Ill ,ACll..ITY
| | DOClln . - . . m I |
| ........ CIOCXST NUMMIUll N/A 0111010101 I I 0 1 1 2 1 7 8 9 8 9 0 0 fl 0 0 . I -I -I N/A 0111010101 I I --*.awcn --*.awm --*.n1111cm111
| | PM:IUT'f' ..... 111 1 * - * ,.,. |
| -ll.nll!CllCll | | PALISADES NUCLEAR PLANT o I 5 Io *Io Io I 2t 51 5 1 loF 0 15 TITU i . |
| --*71411111CllQ.
| | IN-PROGRESS PLANT DEB.ATE RESULTS IN FAILURE TO PERFORM REQUIRED SURVEILLANCE IVINT DAf t Ill OTMlll PACIUTIU *VOLVID Ill |
| 1.ICl ... 1 CONTACT POii THIS I.Ill 1121 C S Kozup, Technical Engineer, Palisades
| | ,ACll..ITY ........ CIOCXST NUMMIUll N/A 0111010101 I I 0 1 2 7 8 9 8 9 0 0 fl 0 0 1 1 . I - I - I N/A 0111010101 I I |
| *.na.tCIHwt
| | --- *.awcn -- *.na.tCIHwt -- 71..71CM 71..71e.t |
| *.nlllCllc.11
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| .. iw *.71W!Cllt.lllC81 | | *.awm |
| *.nc.ICIHal AlllA C:COI ---71..71CM 71..71e.t ontlllll Ab1Mar ._.,.. ,,, rut. NllC "°"" >>Ml Tll.P+40flll MUMllll CAUlll SYST1111 CCWONINT x I *1 I I I I I I I I I I I I I I I I I I I I I I n Yll /It,,_, .....,._ IXl'WCTIO SIJftllSSION OA TWJ ll<,.C'nD SIJIMlllJON CATI 1191 I I I On January 27, 1989 at 0900 the primary coolant system (PCS) [AB] leak rate determination was not completed as required by Plant Technical Specification (TS) Table 4.2.2 Item 8. This determination was not completed due to an in-progress Plant derate resulting from exceeding the 0.1 gallon per minute (gpm) administrative limit for primary to secondary coolant leak.age. | | *.n1111cm111 ll.nll!CllCll |
| The reactor was critical with the Plant operating at 45 percent of rated power at the time of the event. The required le.ak. rate determination. | | -- |
| completed at 1034 resulted in identified PCS leakage being calculated to be 0.0819 gpm. Due to the in-progress Plant derate, General Operation Procedure requirements could not.be met. The primary to secondary system leakage was the result of a leaking steam generator tube in the "B" steam generator. | | - |
| Subsequent eddy current examinations revealed the feak.ing tube contained a | | *.nlllCllc.11 |
| indication (approximately 57 degrees in circumference) near the top, yet within the third support plate. The crack-like indication is believed to be the result of a combination of localized stress, tube denting and support plate | | *.nc.11111. .iw |
| "!'!*;u "::.c-:c'"*., *o*., .. *.: This event is being reported due.to the failure to _perform the required PCS leak rate determination. | | *.71W!Cllt.lllC81 |
| Det°ails thE! steam generator tube leak are provided for information. | | - ontlllll |
| Tc;'l..-2 | | >>Ml I~;,, |
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| | ._.,.. ,,, rut. |
| NRC,_ .... (9-131 LICENSEE EVIJ REPORT (LERJ TEXT CONTINUATlce U.8. lllUCUA" lllGUUTa..'I' C0111111910111 OMtl NO. ltll0-011)1 EXPl"IS: lf.llAla , l'_ACILITY lllAM9 111 DOCXIT M.1191" 121 | | Ab1Mar NllC "°"" |
| ' PALISADES NUCLEAR PLANT TP'T ,,, _ -*----_.....,.NlfC | | *71411111CllQ. *.nc.ICIHal 1.ICl. . .1 CONTACT POii THIS I.Ill 1121 Tll.P+40flll MUMllll AlllA C:COI C S Kozup, Technical Engineer, Palisades CAUlll SYST1111 CCWONINT x I *1 I I I I I I I I I I I I I I I I I I I I I I ll<,.C'nD n Yll /It,,_, .....,._ IXl'WCTIO SIJftllSSION OA TWJ SIJIMlllJON CATI 1191 I I I On January 27, 1989 at 0900 the primary coolant system (PCS) [AB] leak rate determination was not completed as required by Plant Technical Specification (TS) Table 4.2.2 Item 8. This determination was not completed due to an in-progress Plant derate resulting from exceeding the 0.1 gallon per minute (gpm) administrative limit for primary to secondary coolant leak.age. The reactor was critical with the Plant operating at 45 percent of rated power at the time of the event. |
| ,_,...'I.I (171 Description On January 27, 1989 at 0900 the primary coolant system (PCS) [AB] leak rate determination was not completed as required by Plant Technical Specification (TS) Table 4.2.2 Item 8. This determination was not completed due to an in-progress Plant derate resulting from exceeding the O.l gallon per minute (gpm) administrative limit for primary to secondary coolant leakage. The reactor was critical with the Plant operating at 45 percent of rated power at the time of the event. TS Table 4.2.2 Item 8 requires that leakage be evaluated daily. TS 4.02 allows for extending the surveillance time interval up to 25 percent of the required time. The January 26, 1989 PCS leak rate was completed at approximately 0300. Therefore, the next leak rate would be required to be completed by approximately 0900 on January 27, 1989. Due to the requirements of Plant General Operating Procedure (GOP) 13, "Primary System Leakage Calculation" and the Plant derate in-progress as detailed below, the PCS leakage calculation was not completed until 1034 on January 27, 1989. GOP 13 requires that Plant power level be stabilized and remain so during the duration of the three hour PCS leak rate determination. | | The required le.ak. rate determination. completed at 1034 resulted in identified PCS leakage being calculated to be 0.0819 gpm. Due to the in-progress Plant derate, General Operation Procedure requirements could not.be met. The primary to secondary system leakage was the result of a leaking steam generator tube in the "B" steam generator. Subsequent eddy current examinations revealed the feak.ing tube contained a crac~-like indication (approximately 57 degrees in circumference) near the top, yet within the third support plate. The crack-like indication is believed to be the result of a combination of localized stress, tube denting and support plate displa~'ement~'*: "!'!*;u "::.c-:c'"*., *o*., |
| * Date January 22, 1989 0445 January 22, 1989 0810-1053 January 22, 1989 1405-1500 January 24, 1989 1035-1155 . LER 89001-LIOl Description With the Plant at 100 percent of rated power, condensor off-gas radiation monitor RIA-0631 [SG;RI] count rate increased from approximately 1260 to 1700 counts per minute (cpm). Condensor of £-gas flow rate and PCS radioactivity were essentially constant. | | .. *.: |
| Chemistry samples indicated no activity increases in either steam generator | | This event is being reported due.to the failure to _perform the required PCS leak rate determination. Det°ails ~eg~rding thE! steam generator tube leak are provided for information. |
| [AB;SG]. Estimated primary to secondary leakage was determined to be 0.006 gpm. RIA-0631 count rate increased to 3700 cpm. Primary to secondary leakage determined to be 0.008 gpm. With the Plant at 99.9 percent of rated power, RIA-0631 :* I LICENSEE EVE.EPORT (LERJ TEXT CONTINUATIO._ | | Tc;'l..-2 / |
| U.I. llUCLIAll lllQUUTOtlY -OVID OMe NO.
| | - J ( |
| EX"llll: lr.11 Ill PALISADES NUCLEAR PLANT TIXT Ill ___ ......_ --NffC ,_...,.,IJ 1171 January 25, 1989 January 25, 1989 January 26, 1989 January 26, 1989 January 27, 1989 ""C *O"M :IMA 11-131 LER 89001-LIO l OOClllT NUllelll 121 Liii llKMUll Ill 0630 2210 0215-0410 1655-1930 0050 activity increased to 13,000 cpm. This corresponded to a primary to secondary leak rate of 0.046 gpm. Primary to secondary leakage estimated to be 0.050 gpm based on RIA-0631 activity. | | |
| Chemistry personnel reported primary to secondary leakage at 0.114 gpm based on RIA-0631 activity of 24,000 cpm. Operations personnel entered System Operating Procedure 1, "Primary Coolant System" due to the PCS system leakage exceeding the O.l gpm strative limit. TS 3.1.5.d requires Plant shutdown be initiated when primary to secondary leakage in a steam generator exceeds 0.3 gpm for any period of steady state operation greater than 24 consecutive hours. Chemistry personnel reported that the primary to secondary leak rate was 0.059 gpm and that the results reported at 2210 in January 25, 1989 were in error. Operations personnel secured from SOP 1. With the Plant operating at 100 percent of rated power, RIA-0631 activity increased to 40,000 cpm. Chemistry reported primary to secondary leakage at 0.108 gpm. Plant shutdown at a six percent per hour of rated power was ordered. With the Plant at 75 percent of rated power, PCS pressure was reduced from 2060 psi to 2000 psi.
| | NRC,_ . . . . U.8. lllUCUA" lllGUUTa..'I' C0111111910111 (9-131 LICENSEE EVIJ REPORT (LERJ TEXT CONTINUATlce ~V!D OMtl NO. ltll0-011)1 EXPl"IS: lf.llAla |
| lltle_ .. CM31
| | , l'_ACILITY lllAM9 111 DOCXIT M.1191" 121 Llll~"(ll |
| * lllAlll9'C11 1 *** LICENSEE EVE.EPORT (l.EAJ TEXT CONT1NUAT101t U.._ NUC\.IMI lllfWLATa.IY CCIWll.IC. OMe NO.
| | ' PALISADES NUCLEAR PLANT TP'T ,,, _ -*---- _.....,.NlfC ,_,...'I.I (171 Description On January 27, 1989 at 0900 the primary coolant system (PCS) [AB] leak rate determination was not completed as required by Plant Technical Specification (TS) Table 4.2.2 Item 8. This determination was not completed due to an in-progress Plant derate resulting from exceeding the O.l gallon per minute (gpm) administrative limit for primary to secondary coolant leakage. The reactor was critical with the Plant operating at 45 percent of rated power at the time of the event. |
| EX'tl'll: | | TS Table 4.2.2 Item 8 requires that PC~ leakage be evaluated daily. TS 4.02 allows for extending the surveillance time interval up to 25 percent of the required time. The January 26, 1989 PCS leak rate was completed at approximately 0300. Therefore, the next leak rate would be required to be completed by approximately 0900 on January 27, 1989. Due to the requirements of Plant General Operating Procedure (GOP) 13, "Primary System Leakage Calculation" and the Plant derate in-progress as detailed below, the PCS leakage calculation was not completed until 1034 on January 27, 1989. GOP 13 requires that Plant power level be stabilized and remain so during the duration of the three hour PCS leak rate determination. |
| 1131 .. DOCICIT 12t ..... *-" ,. '"°' 131 PALISADES PLANT o 1 s Io I o Io I 21 5 15 a 1 9 -o 1 o 1 i -o 1 o o 1 4 oF o 1 5 TIXT 1*--* i....-. -_,,.NltC ,_..,...,cm January 27, 1989 January 27, 1989 January 27, 1989 January 30, 1989 Cause Of The Event 0630 0711 1034 0805 Chemistry personnel reported that primary to secondary leakage has decreased to 0.017 gpm. Plant derate halted at roximately 45 percent of rated power to perform TS required PCS.leak rate mination. | | * Date Description January 22, 1989 0445 With the Plant at 100 percent of rated power, condensor off-gas radiation monitor RIA-0631 [SG;RI] count rate increased from approximately 1260 to 1700 counts per minute (cpm). Condensor of £-gas flow rate and PCS radioactivity were essentially constant. |
| PCS leak rate determination completed identified leak rate was determined to be 0.819 gpm. Plant power reduction at 12 percent per hour initiated to achieve Plant shutdown for steam generator repairs. The failure to. complete the required PCS leak rate calculation was due to the in-progress Plant reduction resulting from the primary to secondary leakage. The need to reduce Plant power, PCS pressure and the primary to secondary leak rate did not provide stable enough conditions for a three-hour period to perform the PCS leakage determination.
| | January 22, 1989 0810-1053 Chemistry samples indicated no activity increases in either steam generator [AB;SG]. |
| The primary to secondary system leakage was the result of a leaking steam generator tube in the "B" steam generator. | | Estimated primary to secondary leakage was determined to be 0.006 gpm. |
| Subsequent eddy current examinations revealed the leaking tube contained a crack-like indication (approximately 57 degrees in circumference) near the top, yet within the third support plate. The crack-like indication is believed to be the result of a combination of localized stress, tube denting and support plate displacement. | | January 22, 1989 1405-1500 RIA-0631 count rate increased to 3700 cpm. Primary to secondary leakage determined to be 0.008 gpm. |
| | January 24, 1989 1035-1155 . With the Plant at 99.9 percent of rated power, RIA-0631 LER 89001-LIOl |
| | |
| | U.I. llUCLIAll lllQUUTOtlY ~ |
| | LICENSEE EVE.EPORT (LERJ TEXT CONTINUATIO._ -OVID OMe NO. 3150~104 EX"llll: lr.11 Ill OOClllT NUllelll 121 Liii llKMUll Ill PALISADES NUCLEAR PLANT TIXT Ill _ _ _ ......_ --NffC ,_...,.,IJ 1171 activity increased to 13,000 cpm. This corresponded to a primary to secondary leak rate of 0.046 gpm. |
| | January 25, 1989 0630 Primary to secondary leakage estimated to be 0.050 gpm based on RIA-0631 activity. |
| | January 25, 1989 2210 Chemistry personnel reported primary to secondary leakage at 0.114 gpm based on RIA-0631 activity of 24,000 cpm. |
| | Operations personnel entered System Operating Procedure 1, "Primary Coolant System" due to the PCS system leakage exceeding the O.l gpm admin-strative limit. TS 3.1.5.d requires Plant shutdown be initiated when primary to secondary leakage in a steam generator exceeds 0.3 gpm for any period of steady state operation greater than 24 consecutive hours. |
| | January 26, 1989 0215-0410 Chemistry personnel reported that the primary to secondary leak rate was 0.059 gpm and that the results reported at 2210 in January 25, 1989 were in error. Operations personnel secured from SOP 1. |
| | January 26, 1989 1655-1930 With the Plant operating at 100 percent of rated power, RIA-0631 activity increased to 40,000 cpm. Chemistry reported primary to secondary leakage at 0.108 gpm. Plant shutdown at a six percent per hour of rated power was ordered. |
| | January 27, 1989 0050 With the Plant at 75 percent of rated power, PCS pressure was reduced from 2060 psi to 2000 psi. |
| | ""C *O"M :IMA 11-131 LER 89001-LIO l |
| | |
| | lltle_ . . U.._ NUC\.IMI lllfWLATa.IY CCIWll.IC. |
| | CM31 |
| | * LICENSEE EVE.EPORT (l.EAJ TEXT CONT1NUAT101t ~ID OMe NO. ll!I0~10ot EX'tl'll: 1131 . . |
| | l'~IUTY 1*** |
| | lllAlll9'C11 DOCICIT ~* 12t ..... * - " ,. '"°' 131 PALISADES PLANT o 1s Io I o Io I 21 5 15 a19 - o1o 1i - o 1o o14 oF o 15 TIXT 1*--*i....-. - _,,.NltC ,_..,...,cm January 27, 1989 0630 Chemistry personnel reported that primary to secondary leakage has decreased to 0.017 gpm. |
| | January 27, 1989 0711 Plant derate halted at app-roximately 45 percent of rated power to perform TS required PCS.leak rate deter-mination. |
| | January 27, 1989 1034 PCS leak rate determination completed identified leak rate was determined to be 0.819 gpm. |
| | January 30, 1989 0805 Plant power reduction at 12 percent per hour initiated to achieve Plant shutdown for steam generator repairs. |
| | Cause Of The Event The failure to. complete the required PCS leak rate calculation was due to the in-progress Plant p~wer reduction resulting from the primary to secondary leakage. The need to reduce Plant power, PCS pressure and the primary to secondary leak rate did not provide stable enough conditions for a three-hour period to perform the PCS leakage determination. |
| | The primary to secondary system leakage was the result of a leaking steam generator tube in the "B" steam generator. Subsequent eddy current examinations revealed the leaking tube contained a crack-like indication (approximately 57 degrees in circumference) near the top, yet within the third support plate. The crack-like indication is believed to be the result of a combination of localized stress, tube denting and support plate displacement. |
| Corrective Action The required PCS leak rate determination was completed at 1034 on January 27, 1989. An evaluation is being conducted to determine the necessity for a TS change regarding the allowance of extending PCS leak rate determinations beyond existing time intervals during Plant shutdowns. | | Corrective Action The required PCS leak rate determination was completed at 1034 on January 27, 1989. An evaluation is being conducted to determine the necessity for a TS change regarding the allowance of extending PCS leak rate determinations beyond existing time intervals during Plant shutdowns. |
| Eddy current testing was performed utilizing the 4C4F technique for the full hot leg length of 104 steam generator tubes and utilizing the Motorized Rotating Absolute Pancaked Coil (MPRC) technique at the third support plate for 40 steam generator tubes. No additional degradation LER 89001-LIOl | | Eddy current testing was performed utilizing the 4C4F technique for the full hot leg length of 104 steam generator tubes and utilizing the Motorized Rotating Absolute Pancaked Coil (MPRC) technique at the third support plate for 40 steam generator tubes. No additional degradation LER 89001-LIOl |
| | |
| | r--~~~~;------:::::======:-:--~~:::~==i, llM3r |
| | * LICENSEE EVE.M REPORT ( |
| | LERJ TEXT CONTINUATIQ. |
| | u.a. 111UC&.u.1t 11 |
| | *ouu.Ta.v C01111 *"'* |
| | ~YID 0... l'IO. l15a~Oot EX,.ltH: 1131119 PACIUTY NAiii 111 DOCICIT NUlimllt 121 Lllt~lt 191 'AQI IJI PALISADES NuCLEAR PLANT o 1s 1o 1o 1o 12 15 15 a19 _ ~ 9i _ o1 o 9 5 oF o 5 1 |
| | was noted during this testing. All active steam generator tubes surrounding-the leaking tube were plugged as a preventive measure. |
| | In addition to the above testing, 240 tubes were inspected utilizing the MRPC technique at the 13th support plate of the "B" steam generator. |
| | The tubes inspected were in the area of previously identified (1987/1988) crack-like indications. Crack-like indications were noted in three tubes. In conjunction with this inspection, three tubes in the 11 11 8 steam generator were deplugged and reinspected utilizing the MRPC technique in order to monitor crack propagation. Two of these tubes exhibited no change from previous inspections, while the third indicated growth from 57 to 150 degrees in circumference. All three tubes were replugged. A to_tal of 238 tubes were plugged in a block. arrangement as a preventive measure to encompass apparent affected areas. This area of plugging also included all active tubes surrounding the leaker. |
| | Analysis Of The Event Technical Specifications regarding primary to secondary system leakage were not approached. In that the FSAR safety analysis (Section 14.15) for a steam generator tube rupture assumes a double ended rupture, no safety consequence resulted from this event. |
| | This event is being reported per 10CFR50.73(a)(2)(i)(B) as an operational condition prohibited by Plant Technical Specifications regarding the failure to perform the required PCS leak rate. |
| | Additional Information For additional information regarding steam generate~ tube leaks, reference Licensee Event Reports 82-012, 88-012 and 88-012-01. |
| | For additional information regarding the failure to perform required TS surveillances, reference Licensee Event Reports 83-078, 84-018, 85-002, 85-004, 85-012, 85-020 and 88-008. |
| | 19-331 LER 89001-LIOl |
|
| |
|
| llM3r
| | POWERING MICHIGAN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 February 27, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - |
| * LICENSEE EVE.M REPORT ( u.a. 111UC&.u.1t 11*ouu.Ta.v C01111 *"'* LERJ TEXT CONTINUATIQ.
| | LICENSEE EVENT REPORT 89-001 - IN-PROGRESS PLANT DERATE RESULTS IN FAILURE TO PERFORM REQUIRED SURVEILLANCE) |
| 0... l'IO.
| | Licensee Event Report (LER) 89-001 (In-progress Plant Derate Results in Failure to Perform Required Surveillance) is attached. This event is reportable to the NRC per 10CFR50.73(a)(2)(i). |
| EX,.ltH: 1131119 PACIUTY NAiii 111 DOCICIT NUlimllt 121 19-331 191 'AQI IJI PALISADES NuCLEAR PLANT o 1 s 1 o 1 o 1 o 1 2 1 5 1 5 a 19 _ 9 i _ o 1 o 9 5 oF o 1 5 was noted during this testing. All active steam generator tubes surrounding-the leaking tube were plugged as a preventive measure. In addition to the above testing, 240 tubes were inspected utilizing the MRPC technique at the 13th support plate of the "B" steam generator.
| | Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment OC0289-0066-NL02}} |
| The tubes inspected were in the area of previously identified (1987/1988) crack-like indications.
| |
| Crack-like indications were noted in three tubes. In conjunction with this inspection, three tubes in the 11 8 11 steam generator were deplugged and reinspected utilizing the MRPC technique in order to monitor crack propagation.
| |
| Two of these tubes exhibited no change from previous inspections, while the third indicated growth from 57 to 150 degrees in circumference.
| |
| All three tubes were replugged.
| |
| A to_tal of 238 tubes were plugged in a block. arrangement as a preventive measure to encompass apparent affected areas. This area of plugging also included all active tubes surrounding the leaker. Analysis Of The Event Technical Specifications regarding primary to secondary system leakage were not approached.
| |
| In that the FSAR safety analysis (Section 14.15) for a steam generator tube rupture assumes a double ended rupture, no safety consequence resulted from this event. This event is being reported per 10CFR50.73(a)(2)(i)(B) as an operational condition prohibited by Plant Technical Specifications regarding the failure to perform the required PCS leak rate. Additional Information For additional information regarding steam tube leaks, reference Licensee Event Reports 82-012, 88-012 and 88-012-01.
| |
| For additional information regarding the failure to perform required TS surveillances, reference Licensee Event Reports 83-078, 84-018, 85-002, 85-004, 85-012, 85-020 and 88-008. LER 89001-LIOl POWERING MICHIGAN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 February 27, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -LICENSEE EVENT REPORT 89-001 -IN-PROGRESS PLANT DERATE RESULTS IN FAILURE TO PERFORM REQUIRED SURVEILLANCE)
| |
| Licensee Event Report (LER) 89-001 (In-progress Plant Derate Results in Failure to Perform Required Surveillance) is attached. | |
| This event is reportable to the NRC per 10CFR50.73(a)(2)(i). | |
| Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector | |
| -Palisades Attachment OC0289-0066-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
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IN-PROGRESS PLANT DEB.ATE RESULTS IN FAILURE TO PERFORM REQUIRED SURVEILLANCE IVINT DAf t Ill OTMlll PACIUTIU *VOLVID Ill
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- 71411111CllQ. *.nc.ICIHal 1.ICl. . .1 CONTACT POii THIS I.Ill 1121 Tll.P+40flll MUMllll AlllA C:COI C S Kozup, Technical Engineer, Palisades CAUlll SYST1111 CCWONINT x I *1 I I I I I I I I I I I I I I I I I I I I I I ll<,.C'nD n Yll /It,,_, .....,._ IXl'WCTIO SIJftllSSION OA TWJ SIJIMlllJON CATI 1191 I I I On January 27, 1989 at 0900 the primary coolant system (PCS) [AB] leak rate determination was not completed as required by Plant Technical Specification (TS) Table 4.2.2 Item 8. This determination was not completed due to an in-progress Plant derate resulting from exceeding the 0.1 gallon per minute (gpm) administrative limit for primary to secondary coolant leak.age. The reactor was critical with the Plant operating at 45 percent of rated power at the time of the event.
The required le.ak. rate determination. completed at 1034 resulted in identified PCS leakage being calculated to be 0.0819 gpm. Due to the in-progress Plant derate, General Operation Procedure requirements could not.be met. The primary to secondary system leakage was the result of a leaking steam generator tube in the "B" steam generator. Subsequent eddy current examinations revealed the feak.ing tube contained a crac~-like indication (approximately 57 degrees in circumference) near the top, yet within the third support plate. The crack-like indication is believed to be the result of a combination of localized stress, tube denting and support plate displa~'ement~'*: "!'!*;u "::.c-:c'"*., *o*.,
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This event is being reported due.to the failure to _perform the required PCS leak rate determination. Det°ails ~eg~rding thE! steam generator tube leak are provided for information.
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' PALISADES NUCLEAR PLANT TP'T ,,, _ -*---- _.....,.NlfC ,_,...'I.I (171 Description On January 27, 1989 at 0900 the primary coolant system (PCS) [AB] leak rate determination was not completed as required by Plant Technical Specification (TS) Table 4.2.2 Item 8. This determination was not completed due to an in-progress Plant derate resulting from exceeding the O.l gallon per minute (gpm) administrative limit for primary to secondary coolant leakage. The reactor was critical with the Plant operating at 45 percent of rated power at the time of the event.
TS Table 4.2.2 Item 8 requires that PC~ leakage be evaluated daily. TS 4.02 allows for extending the surveillance time interval up to 25 percent of the required time. The January 26, 1989 PCS leak rate was completed at approximately 0300. Therefore, the next leak rate would be required to be completed by approximately 0900 on January 27, 1989. Due to the requirements of Plant General Operating Procedure (GOP) 13, "Primary System Leakage Calculation" and the Plant derate in-progress as detailed below, the PCS leakage calculation was not completed until 1034 on January 27, 1989. GOP 13 requires that Plant power level be stabilized and remain so during the duration of the three hour PCS leak rate determination.
- Date Description January 22, 1989 0445 With the Plant at 100 percent of rated power, condensor off-gas radiation monitor RIA-0631 [SG;RI] count rate increased from approximately 1260 to 1700 counts per minute (cpm). Condensor of £-gas flow rate and PCS radioactivity were essentially constant.
January 22, 1989 0810-1053 Chemistry samples indicated no activity increases in either steam generator [AB;SG].
Estimated primary to secondary leakage was determined to be 0.006 gpm.
January 22, 1989 1405-1500 RIA-0631 count rate increased to 3700 cpm. Primary to secondary leakage determined to be 0.008 gpm.
January 24, 1989 1035-1155 . With the Plant at 99.9 percent of rated power, RIA-0631 LER 89001-LIOl
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LICENSEE EVE.EPORT (LERJ TEXT CONTINUATIO._ -OVID OMe NO. 3150~104 EX"llll: lr.11 Ill OOClllT NUllelll 121 Liii llKMUll Ill PALISADES NUCLEAR PLANT TIXT Ill _ _ _ ......_ --NffC ,_...,.,IJ 1171 activity increased to 13,000 cpm. This corresponded to a primary to secondary leak rate of 0.046 gpm.
January 25, 1989 0630 Primary to secondary leakage estimated to be 0.050 gpm based on RIA-0631 activity.
January 25, 1989 2210 Chemistry personnel reported primary to secondary leakage at 0.114 gpm based on RIA-0631 activity of 24,000 cpm.
Operations personnel entered System Operating Procedure 1, "Primary Coolant System" due to the PCS system leakage exceeding the O.l gpm admin-strative limit. TS 3.1.5.d requires Plant shutdown be initiated when primary to secondary leakage in a steam generator exceeds 0.3 gpm for any period of steady state operation greater than 24 consecutive hours.
January 26, 1989 0215-0410 Chemistry personnel reported that the primary to secondary leak rate was 0.059 gpm and that the results reported at 2210 in January 25, 1989 were in error. Operations personnel secured from SOP 1.
January 26, 1989 1655-1930 With the Plant operating at 100 percent of rated power, RIA-0631 activity increased to 40,000 cpm. Chemistry reported primary to secondary leakage at 0.108 gpm. Plant shutdown at a six percent per hour of rated power was ordered.
January 27, 1989 0050 With the Plant at 75 percent of rated power, PCS pressure was reduced from 2060 psi to 2000 psi.
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lllAlll9'C11 DOCICIT ~* 12t ..... * - " ,. '"°' 131 PALISADES PLANT o 1s Io I o Io I 21 5 15 a19 - o1o 1i - o 1o o14 oF o 15 TIXT 1*--*i....-. - _,,.NltC ,_..,...,cm January 27, 1989 0630 Chemistry personnel reported that primary to secondary leakage has decreased to 0.017 gpm.
January 27, 1989 0711 Plant derate halted at app-roximately 45 percent of rated power to perform TS required PCS.leak rate deter-mination.
January 27, 1989 1034 PCS leak rate determination completed identified leak rate was determined to be 0.819 gpm.
January 30, 1989 0805 Plant power reduction at 12 percent per hour initiated to achieve Plant shutdown for steam generator repairs.
Cause Of The Event The failure to. complete the required PCS leak rate calculation was due to the in-progress Plant p~wer reduction resulting from the primary to secondary leakage. The need to reduce Plant power, PCS pressure and the primary to secondary leak rate did not provide stable enough conditions for a three-hour period to perform the PCS leakage determination.
The primary to secondary system leakage was the result of a leaking steam generator tube in the "B" steam generator. Subsequent eddy current examinations revealed the leaking tube contained a crack-like indication (approximately 57 degrees in circumference) near the top, yet within the third support plate. The crack-like indication is believed to be the result of a combination of localized stress, tube denting and support plate displacement.
Corrective Action The required PCS leak rate determination was completed at 1034 on January 27, 1989. An evaluation is being conducted to determine the necessity for a TS change regarding the allowance of extending PCS leak rate determinations beyond existing time intervals during Plant shutdowns.
Eddy current testing was performed utilizing the 4C4F technique for the full hot leg length of 104 steam generator tubes and utilizing the Motorized Rotating Absolute Pancaked Coil (MPRC) technique at the third support plate for 40 steam generator tubes. No additional degradation LER 89001-LIOl
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was noted during this testing. All active steam generator tubes surrounding-the leaking tube were plugged as a preventive measure.
In addition to the above testing, 240 tubes were inspected utilizing the MRPC technique at the 13th support plate of the "B" steam generator.
The tubes inspected were in the area of previously identified (1987/1988) crack-like indications. Crack-like indications were noted in three tubes. In conjunction with this inspection, three tubes in the 11 11 8 steam generator were deplugged and reinspected utilizing the MRPC technique in order to monitor crack propagation. Two of these tubes exhibited no change from previous inspections, while the third indicated growth from 57 to 150 degrees in circumference. All three tubes were replugged. A to_tal of 238 tubes were plugged in a block. arrangement as a preventive measure to encompass apparent affected areas. This area of plugging also included all active tubes surrounding the leaker.
Analysis Of The Event Technical Specifications regarding primary to secondary system leakage were not approached. In that the FSAR safety analysis (Section 14.15) for a steam generator tube rupture assumes a double ended rupture, no safety consequence resulted from this event.
This event is being reported per 10CFR50.73(a)(2)(i)(B) as an operational condition prohibited by Plant Technical Specifications regarding the failure to perform the required PCS leak rate.
Additional Information For additional information regarding steam generate~ tube leaks, reference Licensee Event Reports82-012, 88-012 and 88-012-01.
For additional information regarding the failure to perform required TS surveillances, reference Licensee Event Reports83-078, 84-018,85-002, 85-004,85-012, 85-020 and 88-008.19-331 LER 89001-LIOl
POWERING MICHIGAN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 February 27, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
LICENSEE EVENT REPORT 89-001 - IN-PROGRESS PLANT DERATE RESULTS IN FAILURE TO PERFORM REQUIRED SURVEILLANCE)
Licensee Event Report (LER)89-001 (In-progress Plant Derate Results in Failure to Perform Required Surveillance) is attached. This event is reportable to the NRC per 10CFR50.73(a)(2)(i).
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment OC0289-0066-NL02
