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| #REDIRECT [[05000461/LER-1998-024]] | | {{Adams |
| | | number = ML20236Y583 |
| | | issue date = 08/07/1998 |
| | | title = :on 980708,failure to Perform Surveillance Testing on Div II Voltage Relays within Specified Frequency of TS Was Noted.Cause of Event Is Under Investigation.Util Expects to Issue Rev to Rept by 980907 |
| | | author name = Stalter W |
| | | author affiliation = ILLINOIS POWER CO. |
| | | addressee name = |
| | | addressee affiliation = |
| | | docket = 05000461 |
| | | license number = |
| | | contact person = |
| | | document report number = LER-98-024, LER-98-24, NUDOCS 9808120324 |
| | | package number = ML20236Y582 |
| | | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT |
| | | page count = 3 |
| | }} |
| | {{LER |
| | | Title = :on 980708,failure to Perform Surveillance Testing on Div II Voltage Relays within Specified Frequency of TS Was Noted.Cause of Event Is Under Investigation.Util Expects to Issue Rev to Rept by 980907 |
| | | Plant = |
| | | Reporting criterion = 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(iv), 10 CFR 50.73(a)(2)(i)(B) |
| | | Power level = |
| | | Mode = |
| | | Docket = 05000461 |
| | | LER year = 1998 |
| | | LER number = 24 |
| | | LER revision = 0 |
| | | Event date = |
| | | Report date = |
| | | ENS = |
| | | abstract = |
| | }} |
| | |
| | =text= |
| | {{#Wiki_filter:l i |
| | *NAC FORM 3*C U.S. NUCLEAR REGULAToAY COMMISSION A**novso a v a Me no. a s soa isa 44-951 EXPwua 04/30tes (StiMATIO tuf;D(N PEA RE SPON3 TO COM*LY wiTM THIS M ANDATORY |
| | 'N80RM ATION COLuCTION AlOUfST: 60.0 MR$. |
| | REPORTIO LI S$ONS LICENSEE EVENT REPORT (LER) |
| | 't'aato ^at 'acoaao**Tto 'NTO TMt uCaNsNG PROC ss AuO 8 0 sACu T0 INOVETRY. f 081 WARD COMMENTS REGARDING BUROEN ESTiMAT( TO TM( |
| | IN808iM ATION ANO RE COROS M ANAGE ME NT BRANCM (T 6 F 331, U.$. |
| | (See reverse for requsred number of NUCLE AR REGULATORY COMMr$90N. WASHINGTON. DC 20$664001. ANO TO THE PAPERWont REOUCTION PROJE CT 13160 0104). 08FICE 08 digits /chernetere for each block) |
| | M ANAC(Mf MT AND SUDGET. WASHINGTON. OC 20603. |
| | PAcEITY mAMt du DOCKET NUMapi(31 paos p, Clinton Power Station 05000461 1 or 3 Trfu m Feilure to Perform Surveillance Testing On Division 11 Degraded Voltage Relays Within the Specified Frequency of the Technical Specifications EVEf fT DATF BI LER NUMRFR (8 I |
| | REPORT DATF f 71 OTHER Factt ITLES INV 3LVED (B) |
| | MONTH DAY YEAR YEAR SE QU(N TIAL REVISON MONTH DAY YEAR |
| | ' ACiuTY NAME DOCKET NUMeER NUM8t R NUM8tR None 05000 07 08 98 98 024 00 08 07 98 |
| | ' ^c''' " "^"I Docat' "uM. R None 05000 OPERATING THIS REPORT is $UsMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 0; (Check one Or more) (til MODE (9) 4 20.2201(b) 20.2203(eH2Hv) |
| | X 50.73(a)(2Hi) 50.73(aH2Hviii) |
| | POWER 20.2203(a)(1) 20.2203(aH3H!) |
| | 50.73(aH2)(ii) 50.73(a)(2)(x) |
| | LEVEL 110) 000 20.2203(a)(2Hi) 20.2203(aH3Hii) 50.73(a)(2Hiii) 73.71 pg p W W Myg g e 20.2203(e)(2Hii) 20.2203(aH4) 50.73(a)(2)(iv) |
| | OTHER bhyd |
| | * WI 20.2203(aH2Hiii) 50.36tc)(1) 50.73(a)(2Hv) |
| | Specify in Abstract below d k k;I 3 20.2203(eH2Hiv) 50.36(c)(2) 50.73(sH2)(vii) or in NRC Form 366A iIcFNM CONTACT FOR THIS LER (121 NAME TELEPHONE NUMeER (tru:iume Aree Cedel W. G. Stalter, Project Specialist, Work Management (217) 935-8881, Extension 3062 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRISED IN THIS REPORT (13) |
| | |
| | ==CAUSE== |
| | SYSTEM COMPONENT MANUF AC tURER REPORTABLE s.9 |
| | |
| | ==CAUSE== |
| | SYSTEM COMPONENT MANUP ACTURER REPORTABLE TO HPRDS TO NPRDS s |
| | )v s |
| | s g, |
| | O SUPPLEMENTAL REPORT EXPECTED (14] |
| | EXPECTED MONTH DAY YEAR susMisslON DATE (15) |
| | X YES NO Og 07 98 (if ves. comOlete EXPECTED SUBMISSION DATEl. |
| | ABSTRACT (Lunit 10 1400 epeces, Le., approxernately 15 eingle spaced typewritten lines) (16) |
| | On July 8, 1998, at approximately 0630 hours it was discovered that functional testing of the Division II Degraded Voltage Relays had not been performed within the specified frequency of the Technical Specifications (TS). |
| | The time requirement for functional testing of Division II Degraded Voltage Relays was exceeded on July 5, i |
| | 1998. The immediate corrective action taken for this event was performance of surveillance procedure Clinton Power Station (CPS) No. 9333.30, " Division II 4.16 KV l |
| | Degraded Voltage Trip - Functional Test." |
| | Performance of this surveillance procedure |
| | { |
| | satisfies the functional testing requirements of TS Surveillance Requirement (SR) 3.3.8.1.2 for the Division II Degraded Voltage Relays. A revision to this report will be issued identifying the cause, corrective actions to prevent recurrence, and safety significance of this event. |
| | Illinois Power (IP) expects to issue a revision to this report by September 7, 1998. |
| | 9808120324 9sogo7 I |
| | gDR ADOCK 05000461 i |
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| | NRC FORM 366 (4 95) |
| | |
| | l e |
| | 's s |
| | NRC FORM 361A U.S. NUCLEAR REGULATORY COMMISSION (4-954 LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY NAME fil DOCKET LER NUMRFR m) |
| | PAGE f M YEAR SEOVENTIAL |
| | "' " 0" NUMRTR kUMBIR Chnton Power Station 05000461 98 024 00 2 |
| | OF 3 |
| | 1EKT ut more space os required, use additionet copies of NRC form 366A) l11} |
| | DESCRIPTION OF EVENT-On July 8, 1998, the plant was in Mode 4 (COLD SHUTDOWN), reactor coolant temperature was b2ing maintained between 95 and 115 degrees Fahrenheit (F), and reactor coolant pressure was atmospheric. At approximately 0630 hours the Clinton Power Station (CPS) Surveillance Coordinator was reviewing completed surveillance and discovered the surveillance that performs testing of the Division II Degraded Voltage Trip Relays (RLY), as required by T3chnical Specification (TS) Surveillance Requirement (SR) 3.3.8.1.2, had not been j |
| | performed and was past its late date. |
| | Further investigation discovered that the Limiting Condition for Operation (LCO) Actions were not being taken per LCO 3.3.8.1, " Loss of Power l |
| | (LOP) Instrumentation," for the late surveillance. At approximately 0635 the Shift Manager (SM) was notified of this condition. The SM directed the performance of the missed surveillance and entered the actions of TS SR 3.0.3 which allows for a 24 hour delay in d2claring-a system inoperable te, perform a missed surveillance. |
| | Surveillance procedure CPS No. 9333.30, " Division II 4.16 KV Degraded Voltage Trip - |
| | Functional Test," satisfies the functional testing Surveillance Requirements (SR) for the-Division II Degraded Voltage Relays and is required to.be performed every 31 days per TS SR 3.3.8.1.2. |
| | CPS No. 9333.30 had been satisfactorily completed on May 28, 1998, and had a due date of June 24,.1998. |
| | TS SR 3.0.2 establishes an allowance that the specified frequency for each SR is met if the Surveillance is performed within 1.25 times the frequency interval specified as measured from the previous performance or as measured from the time a specified condition of the frequency is met. |
| | Using this allowance, the 1.25 times the frequency date was exceeded on July 5, 1998, and the Actions per LCO 3.3.8 1.2' w:re not taken. On July 8, 1998,.at approximately 1017 hours, CPS No. 9333.30 was completed octisfactorily. Condition Report 1-98-07-057 was written to in,vestigate and track this issue to resolution. |
| | No automatic or manually initiated safety system responses were necessary to place the plant in a safe and stable condition. This event was not directly affected by other inoperable equipment or components. |
| | |
| | ==CAUSE OF EVENT== |
| | The cause of this event is under investigation. A revision will be issued to this report identifying the cause, corrective actions, and safety significance. |
| | Illinois Power (IP) s;xpects to issue a revision to this report by September 7, 1998. |
| | |
| | ==CORRECTIVE ACTIONS== |
| | The immediate corrective action for this event was to perform CPS No. 9333.30 to satisfy TS SR 3.3.8.1.2. |
| | CPS No. 9333.30 was completed satisfactorily on July 8, 1998, at approximately 1017 hours. |
| | Corrective actions to prevent further similar events have not b2en determined and will be supplied in a revision to this report. |
| | .I |
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| | . s s |
| | NRC FORM 3MA U.S. NUCLEAR REGULATORY COMMISSION M 9M LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION |
| | ) |
| | FACILITY NAME fi t DO CKET LER NUMRFR M1 PAGF (31 YEAR SEQUENTIAL |
| | (( |
| | NUMBER Clinton Power Station 05000461 98 024 00 3 |
| | 0F 3 |
| | TEXT (11more space is required, use addaronalcopies of NRC Form 366A) (11) |
| | |
| | ==ANALYSIS OF EVENT== |
| | This event is reportable under the provisions of 10CFR50.73 (a) (2) (i) (B) p.s an operation or condition prohibited by the Technical Specifications. Testing of the Division II 4.16 KV Degraded voltage Trip Relays was not performed within the specified frer,uency of TS SR 3.3.8.1.2 and allowance provided by TS SR 3.0.2, and the Actions per LCO 2.3.8.1 were not met. |
| | An assessment of the safety consequences and implications of this event will be provided in a revision to this report. |
| | |
| | ==ADDITIONAL INFORMATION== |
| | No equipment or components failed during this event. |
| | CPS has not reported similar events involving missed TS SR testing in recent history. |
| | For further information regarding this event, contact William G. Stalter, Project Specialist Work Management, at (217) 935-8881, extension 3062. |
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| | {{LER-Nav}} |
:on 980708,failure to Perform Surveillance Testing on Div II Voltage Relays within Specified Frequency of TS Was Noted.Cause of Event Is Under Investigation.Util Expects to Issue Rev to Rept by 980907| ML20236Y583 |
| Person / Time |
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| Site: |
Clinton  |
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| Issue date: |
08/07/1998 |
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| From: |
Stalter W ILLINOIS POWER CO. |
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| To: |
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| Shared Package |
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| ML20236Y582 |
List: |
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| References |
|---|
| LER-98-024, LER-98-24, NUDOCS 9808120324 |
| Download: ML20236Y583 (3) |
|
text
l i
- NAC FORM 3*C U.S. NUCLEAR REGULAToAY COMMISSION A**novso a v a Me no. a s soa isa 44-951 EXPwua 04/30tes (StiMATIO tuf;D(N PEA RE SPON3 TO COM*LY wiTM THIS M ANDATORY
'N80RM ATION COLuCTION AlOUfST: 60.0 MR$.
REPORTIO LI S$ONS LICENSEE EVENT REPORT (LER)
't'aato ^at 'acoaao**Tto 'NTO TMt uCaNsNG PROC ss AuO 8 0 sACu T0 INOVETRY. f 081 WARD COMMENTS REGARDING BUROEN ESTiMAT( TO TM(
IN808iM ATION ANO RE COROS M ANAGE ME NT BRANCM (T 6 F 331, U.$.
(See reverse for requsred number of NUCLE AR REGULATORY COMMr$90N. WASHINGTON. DC 20$664001. ANO TO THE PAPERWont REOUCTION PROJE CT 13160 0104). 08FICE 08 digits /chernetere for each block)
M ANAC(Mf MT AND SUDGET. WASHINGTON. OC 20603.
PAcEITY mAMt du DOCKET NUMapi(31 paos p, Clinton Power Station 05000461 1 or 3 Trfu m Feilure to Perform Surveillance Testing On Division 11 Degraded Voltage Relays Within the Specified Frequency of the Technical Specifications EVEf fT DATF BI LER NUMRFR (8 I
REPORT DATF f 71 OTHER Factt ITLES INV 3LVED (B)
MONTH DAY YEAR YEAR SE QU(N TIAL REVISON MONTH DAY YEAR
' ACiuTY NAME DOCKET NUMeER NUM8t R NUM8tR None 05000 07 08 98 98 024 00 08 07 98
' ^c " "^"I Docat' "uM. R None 05000 OPERATING THIS REPORT is $UsMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 0; (Check one Or more) (til MODE (9) 4 20.2201(b) 20.2203(eH2Hv)
X 50.73(a)(2Hi) 50.73(aH2Hviii)
POWER 20.2203(a)(1) 20.2203(aH3H!)
50.73(aH2)(ii) 50.73(a)(2)(x)
LEVEL 110) 000 20.2203(a)(2Hi) 20.2203(aH3Hii) 50.73(a)(2Hiii) 73.71 pg p W W Myg g e 20.2203(e)(2Hii) 20.2203(aH4) 50.73(a)(2)(iv)
OTHER bhyd
- WI 20.2203(aH2Hiii) 50.36tc)(1) 50.73(a)(2Hv)
Specify in Abstract below d k k;I 3 20.2203(eH2Hiv) 50.36(c)(2) 50.73(sH2)(vii) or in NRC Form 366A iIcFNM CONTACT FOR THIS LER (121 NAME TELEPHONE NUMeER (tru:iume Aree Cedel W. G. Stalter, Project Specialist, Work Management (217) 935-8881, Extension 3062 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRISED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUF AC tURER REPORTABLE s.9
CAUSE
SYSTEM COMPONENT MANUP ACTURER REPORTABLE TO HPRDS TO NPRDS s
)v s
s g,
O SUPPLEMENTAL REPORT EXPECTED (14]
EXPECTED MONTH DAY YEAR susMisslON DATE (15)
X YES NO Og 07 98 (if ves. comOlete EXPECTED SUBMISSION DATEl.
ABSTRACT (Lunit 10 1400 epeces, Le., approxernately 15 eingle spaced typewritten lines) (16)
On July 8, 1998, at approximately 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> it was discovered that functional testing of the Division II Degraded Voltage Relays had not been performed within the specified frequency of the Technical Specifications (TS).
The time requirement for functional testing of Division II Degraded Voltage Relays was exceeded on July 5, i
1998. The immediate corrective action taken for this event was performance of surveillance procedure Clinton Power Station (CPS) No. 9333.30, " Division II 4.16 KV l
Degraded Voltage Trip - Functional Test."
Performance of this surveillance procedure
{
satisfies the functional testing requirements of TS Surveillance Requirement (SR) 3.3.8.1.2 for the Division II Degraded Voltage Relays. A revision to this report will be issued identifying the cause, corrective actions to prevent recurrence, and safety significance of this event.
Illinois Power (IP) expects to issue a revision to this report by September 7, 1998.
9808120324 9sogo7 I
gDR ADOCK 05000461 i
PDR i
I j
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NRC FORM 366 (4 95)
l e
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NRC FORM 361A U.S. NUCLEAR REGULATORY COMMISSION (4-954 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME fil DOCKET LER NUMRFR m)
PAGE f M YEAR SEOVENTIAL
"' " 0" NUMRTR kUMBIR Chnton Power Station 05000461 98 024 00 2
OF 3
1EKT ut more space os required, use additionet copies of NRC form 366A) l11}
DESCRIPTION OF EVENT-On July 8, 1998, the plant was in Mode 4 (COLD SHUTDOWN), reactor coolant temperature was b2ing maintained between 95 and 115 degrees Fahrenheit (F), and reactor coolant pressure was atmospheric. At approximately 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> the Clinton Power Station (CPS) Surveillance Coordinator was reviewing completed surveillance and discovered the surveillance that performs testing of the Division II Degraded Voltage Trip Relays (RLY), as required by T3chnical Specification (TS) Surveillance Requirement (SR) 3.3.8.1.2, had not been j
performed and was past its late date.
Further investigation discovered that the Limiting Condition for Operation (LCO) Actions were not being taken per LCO 3.3.8.1, " Loss of Power l
(LOP) Instrumentation," for the late surveillance. At approximately 0635 the Shift Manager (SM) was notified of this condition. The SM directed the performance of the missed surveillance and entered the actions of TS SR 3.0.3 which allows for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> delay in d2claring-a system inoperable te, perform a missed surveillance.
Surveillance procedure CPS No. 9333.30, " Division II 4.16 KV Degraded Voltage Trip -
Functional Test," satisfies the functional testing Surveillance Requirements (SR) for the-Division II Degraded Voltage Relays and is required to.be performed every 31 days per TS SR 3.3.8.1.2.
CPS No. 9333.30 had been satisfactorily completed on May 28, 1998, and had a due date of June 24,.1998.
TS SR 3.0.2 establishes an allowance that the specified frequency for each SR is met if the Surveillance is performed within 1.25 times the frequency interval specified as measured from the previous performance or as measured from the time a specified condition of the frequency is met.
Using this allowance, the 1.25 times the frequency date was exceeded on July 5, 1998, and the Actions per LCO 3.3.8 1.2' w:re not taken. On July 8, 1998,.at approximately 1017 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.869685e-4 months <br />, CPS No. 9333.30 was completed octisfactorily. Condition Report 1-98-07-057 was written to in,vestigate and track this issue to resolution.
No automatic or manually initiated safety system responses were necessary to place the plant in a safe and stable condition. This event was not directly affected by other inoperable equipment or components.
CAUSE OF EVENT
The cause of this event is under investigation. A revision will be issued to this report identifying the cause, corrective actions, and safety significance.
Illinois Power (IP) s;xpects to issue a revision to this report by September 7, 1998.
CORRECTIVE ACTIONS
The immediate corrective action for this event was to perform CPS No. 9333.30 to satisfy TS SR 3.3.8.1.2.
CPS No. 9333.30 was completed satisfactorily on July 8, 1998, at approximately 1017 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.869685e-4 months <br />.
Corrective actions to prevent further similar events have not b2en determined and will be supplied in a revision to this report.
.I
e.
. s s
NRC FORM 3MA U.S. NUCLEAR REGULATORY COMMISSION M 9M LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
)
FACILITY NAME fi t DO CKET LER NUMRFR M1 PAGF (31 YEAR SEQUENTIAL
((
NUMBER Clinton Power Station 05000461 98 024 00 3
0F 3
TEXT (11more space is required, use addaronalcopies of NRC Form 366A) (11)
ANALYSIS OF EVENT
This event is reportable under the provisions of 10CFR50.73 (a) (2) (i) (B) p.s an operation or condition prohibited by the Technical Specifications. Testing of the Division II 4.16 KV Degraded voltage Trip Relays was not performed within the specified frer,uency of TS SR 3.3.8.1.2 and allowance provided by TS SR 3.0.2, and the Actions per LCO 2.3.8.1 were not met.
An assessment of the safety consequences and implications of this event will be provided in a revision to this report.
ADDITIONAL INFORMATION
No equipment or components failed during this event.
CPS has not reported similar events involving missed TS SR testing in recent history.
For further information regarding this event, contact William G. Stalter, Project Specialist Work Management, at (217) 935-8881, extension 3062.
i l
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| | | Reporting criterion |
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| 05000461/LER-1998-001, :on 970929,failure of Division 2 SR Battery Charger Was Noted.Caused by Deficient Supplier Soldered Connections.Insp of Division 1,2 & 4 SR Battery Chargers Are Complete & Have Been Reworked & Repaired |
- on 970929,failure of Division 2 SR Battery Charger Was Noted.Caused by Deficient Supplier Soldered Connections.Insp of Division 1,2 & 4 SR Battery Chargers Are Complete & Have Been Reworked & Repaired
| 10 CFR 50.73(e)(2)(x) 10 CFR 21.21(d)(3) 10 CFR 50.73(a)(2)(ii)(3) | | 05000461/LER-1998-002, :on 980123,loss of Svc & Instrument Air Occurred Due to Trip of Operating Air Compressor.Caused by Inadequate Design in Control of Cooling Water Supply to Compressors Lube Oil Coolers.Will Modify Components |
- on 980123,loss of Svc & Instrument Air Occurred Due to Trip of Operating Air Compressor.Caused by Inadequate Design in Control of Cooling Water Supply to Compressors Lube Oil Coolers.Will Modify Components
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-003, :on 980213,loss of Nuclear Sys Protection Sys Bus Resulted in Inadvertent Isolation of Shutdown Cooling. Cause Is Unknown.Corrective Actions Not Yet Determined |
- on 980213,loss of Nuclear Sys Protection Sys Bus Resulted in Inadvertent Isolation of Shutdown Cooling. Cause Is Unknown.Corrective Actions Not Yet Determined
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000461/LER-1998-003-01, Forwards LER 98-003-01 & Part 21 Rept 21-98-022,re Loss of Nuclear Sys Protection Sys Bus.Commitments Made within Ltr, Listed | Forwards LER 98-003-01 & Part 21 Rept 21-98-022,re Loss of Nuclear Sys Protection Sys Bus.Commitments Made within Ltr, Listed | | | 05000461/LER-1998-004-01, Forwards LER 98-004-01 & 10CFR21 Rept 21-98-004/015, Division 2 Nuclear Systems Protection Sys Inverter Not IAW Plants Design Basis Due to Various Deficiencies. Commitments Made by Util,Listed | Forwards LER 98-004-01 & 10CFR21 Rept 21-98-004/015, Division 2 Nuclear Systems Protection Sys Inverter Not IAW Plants Design Basis Due to Various Deficiencies. Commitments Made by Util,Listed | | | 05000461/LER-1998-004, :on 980127,identified Various Deficiencies in Installed SCR & Power Diodes of Division 2 Nsps Inverter. Caused by Ineffective & Inadequate Preventive Maint. Corrected Deficiencies & Calibr Inverter,Per 10CFR21 |
- on 980127,identified Various Deficiencies in Installed SCR & Power Diodes of Division 2 Nsps Inverter. Caused by Ineffective & Inadequate Preventive Maint. Corrected Deficiencies & Calibr Inverter,Per 10CFR21
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 21.21(d)(4) 10 CFR 21.21(d)(3) | | 05000461/LER-1998-005-01, Forwards LER 98-005-01 Re Failure to Verify Closed Pcivs,Per TS Sr.Commitments Made in Rept,Listed | Forwards LER 98-005-01 Re Failure to Verify Closed Pcivs,Per TS Sr.Commitments Made in Rept,Listed | | | 05000461/LER-1998-006, :on 980131,incorrect Calculation in DG Control Circuitry Results in Insufficient Voltage & Inoperability of Div 1 Dg,Was Discovered.Caused by Initial Error in Calculation.Dg Control Panel Voltage Restored |
- on 980131,incorrect Calculation in DG Control Circuitry Results in Insufficient Voltage & Inoperability of Div 1 Dg,Was Discovered.Caused by Initial Error in Calculation.Dg Control Panel Voltage Restored
| 10 CFR 50.73(a)(2) | | 05000461/LER-1998-007, :on 980322,inadequate Engineering Evaluation Leads to Installation of Temporary Mod on DC Electrical Power Sys,Was Determined.Caused by Misjudgement & Misassumptions.Improvements Made to 10CFR50.59 SE Process |
- on 980322,inadequate Engineering Evaluation Leads to Installation of Temporary Mod on DC Electrical Power Sys,Was Determined.Caused by Misjudgement & Misassumptions.Improvements Made to 10CFR50.59 SE Process
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-008, Forwards LER 98-008-00,re Division I Hydrogen & Oxygen Analyzer Incapable of Meeting Design Basis Due to an Excessive Vibration Condition on Air Compressor.Caused by Personnel Error.Commitments Made within Ltr,Listed | Forwards LER 98-008-00,re Division I Hydrogen & Oxygen Analyzer Incapable of Meeting Design Basis Due to an Excessive Vibration Condition on Air Compressor.Caused by Personnel Error.Commitments Made within Ltr,Listed | | | 05000461/LER-1998-008-01, :on 930213,Division I Hydrogen & Oxygen Analyzer Incapable of Meeting Design Basis Were Noted Due to an Excessive Vibration Condition on Air Compressor.Caused by Personnel Error.Div 1 H202 Air Condition Will Be Corrected |
- on 930213,Division I Hydrogen & Oxygen Analyzer Incapable of Meeting Design Basis Were Noted Due to an Excessive Vibration Condition on Air Compressor.Caused by Personnel Error.Div 1 H202 Air Condition Will Be Corrected
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-009, :on 980203,failure to Account for Design Basis Sys Pressures & Voltages for EDG Air Start Sys Was Noted. Caused by Failure of Design Engineer.Changed Spring Size in Solenoid Valve for Division III EDG Air Start Sys |
- on 980203,failure to Account for Design Basis Sys Pressures & Voltages for EDG Air Start Sys Was Noted. Caused by Failure of Design Engineer.Changed Spring Size in Solenoid Valve for Division III EDG Air Start Sys
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(e)(2)(ii) | | 05000461/LER-1998-010, :on 971217,Divs 1 & 2 H & Oxygen Analyzers Were Declared Inoperable Due to Inadequate Commercial Grade Dedication of safety-related Replacement Parts by Supplier. Evaluated Installed Parts for Acceptability |
- on 971217,Divs 1 & 2 H & Oxygen Analyzers Were Declared Inoperable Due to Inadequate Commercial Grade Dedication of safety-related Replacement Parts by Supplier. Evaluated Installed Parts for Acceptability
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 21.21(d)(4) 10 CFR 21.21(d)(3) | | 05000461/LER-1998-011, :on 980312,CR Ventilation Sys Was Declared Inoperable Due to Broken/Missing Conduit Hold Down Restraints on VC Chiller Skids.Caused by Personnel Walking on Equipment.Generated Work Requests |
- on 980312,CR Ventilation Sys Was Declared Inoperable Due to Broken/Missing Conduit Hold Down Restraints on VC Chiller Skids.Caused by Personnel Walking on Equipment.Generated Work Requests
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000461/LER-1998-012, Forwards LER 98-012-00, High Differential Pressure Required to Close Excess Flow Check Valves Results in Valves Being Outside of Design Basis of Plant, IAW Requirements of 10CFR50.73 | Forwards LER 98-012-00, High Differential Pressure Required to Close Excess Flow Check Valves Results in Valves Being Outside of Design Basis of Plant, IAW Requirements of 10CFR50.73 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-013-01, Forwards LER 98-013-01, Remote Shutdown Panel Operation of Rcics May Be Prevented Following MCR Fire,Due to Supplier Design Lacking Circuit Isolation & 10CFR21 Rept Number 21-98-026.Without Part 21 Rept | Forwards LER 98-013-01, Remote Shutdown Panel Operation of Rcics May Be Prevented Following MCR Fire,Due to Supplier Design Lacking Circuit Isolation & 10CFR21 Rept Number 21-98-026.Without Part 21 Rept | | | 05000461/LER-1998-014-01, Design Failure Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles Resulting in Condition Outside of Design Basis for Plant, Has Been Cancelled | Design Failure Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles Resulting in Condition Outside of Design Basis for Plant, Has Been Cancelled | | | 05000461/LER-1998-014, :on 980325,design Fatigue Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles, Resulting in Condition,Outside Design Basis of Plant Occurred.Cause & Corrective Action,Not Yet Been Determined |
- on 980325,design Fatigue Analysis for FW Piping Does Not Match Fatigue Analysis for FW Nozzles, Resulting in Condition,Outside Design Basis of Plant Occurred.Cause & Corrective Action,Not Yet Been Determined
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000461/LER-1998-015, :on 980405,ESF Actuation Was Noted.Caused by Shorted Diode in Nsps.Replaced Shorted Blocking Diode & Tested Other Diodes for Defects |
- on 980405,ESF Actuation Was Noted.Caused by Shorted Diode in Nsps.Replaced Shorted Blocking Diode & Tested Other Diodes for Defects
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000461/LER-1998-016, :on 870630,failure to Test Valves 1SX013D/E/F IAW IST Program Was Noted.Caused by Personnel Error.Tested Safety Functions of Valves 1SX012D/E/F & Added Valves to IST |
- on 870630,failure to Test Valves 1SX013D/E/F IAW IST Program Was Noted.Caused by Personnel Error.Tested Safety Functions of Valves 1SX012D/E/F & Added Valves to IST
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000461/LER-1998-017, :on 980402,inadequate Implementation of SR Was Noted.Caused by Misinterpretation of TS SR 3.8.6.2 & Table 3.8.6-1.Revised Procedure for Performing Battery Cell Specific Gravity Checks |
- on 980402,inadequate Implementation of SR Was Noted.Caused by Misinterpretation of TS SR 3.8.6.2 & Table 3.8.6-1.Revised Procedure for Performing Battery Cell Specific Gravity Checks
| 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-018, :on 980416,ESFA,occurred.Caused by Deficiencies in Method Used to Perform Nsps Power Supply Adjustment. Developed Maint Procedure for Replacement of Power Supplies Powered by Nsps Bus |
- on 980416,ESFA,occurred.Caused by Deficiencies in Method Used to Perform Nsps Power Supply Adjustment. Developed Maint Procedure for Replacement of Power Supplies Powered by Nsps Bus
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000461/LER-1998-019, :on 980417,noted Failure to Satisfy TS for Ensuring That Electrical Loads Properly Sequence Onto safety-related Buses.Caused by Inadequate Surveillance Procedures.Will Revise Procedures 9080.21 & 9080.22 |
- on 980417,noted Failure to Satisfy TS for Ensuring That Electrical Loads Properly Sequence Onto safety-related Buses.Caused by Inadequate Surveillance Procedures.Will Revise Procedures 9080.21 & 9080.22
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-020, :on 980609,discovered Flow Gauge in Main CR to Be Reading Greater than Instrument Range.Cause Indeterminate.Will Incorporate Event Info Into Operator Training Program & Verified Calibr of Flow Instrumentation |
- on 980609,discovered Flow Gauge in Main CR to Be Reading Greater than Instrument Range.Cause Indeterminate.Will Incorporate Event Info Into Operator Training Program & Verified Calibr of Flow Instrumentation
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000461/LER-1998-020-01, Forwards LER 98-020-01, Inadequate Flow Balancing of Shutdown SWS Results in Less than Required Flow to SWS Loads. Revised LER Provides Cause of Event & Corrective Actions | Forwards LER 98-020-01, Inadequate Flow Balancing of Shutdown SWS Results in Less than Required Flow to SWS Loads. Revised LER Provides Cause of Event & Corrective Actions | | | 05000461/LER-1998-021, :on 980220,cracks in Medium & High Density Silicone Penetration Seals Were Not Per Design Basis.Caused by Design Error.Inspected Potentially Affected Seals & Repaired Seals as Necessary |
- on 980220,cracks in Medium & High Density Silicone Penetration Seals Were Not Per Design Basis.Caused by Design Error.Inspected Potentially Affected Seals & Repaired Seals as Necessary
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000461/LER-1998-022, :on 980729,discovered That Surveillance Testing of Div 2 DG Fuel Oil Transfer Pump & Div 2 DG Fuel Oil Storage Tank Had Not Been Performed.Caused by Data Input Error.Will Update & Verify Completion Dates in Database |
- on 980729,discovered That Surveillance Testing of Div 2 DG Fuel Oil Transfer Pump & Div 2 DG Fuel Oil Storage Tank Had Not Been Performed.Caused by Data Input Error.Will Update & Verify Completion Dates in Database
| 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-023, :on 980626,determined That TS SR 3.8.1.17 for Division 3 DG Which Verifies ready-to-load Following Receipt of ECCS Signal,Was Not Adequately Satisfied.Cause & Corrective Actions Will Be Provided in Revised LER |
- on 980626,determined That TS SR 3.8.1.17 for Division 3 DG Which Verifies ready-to-load Following Receipt of ECCS Signal,Was Not Adequately Satisfied.Cause & Corrective Actions Will Be Provided in Revised LER
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-024-01, Forwards LER 98-024-01,re Failure to Perform Surveillance Testing on Div II 4.16 Kv Bus Uvr within Specified Frequency.Commitments Listed | Forwards LER 98-024-01,re Failure to Perform Surveillance Testing on Div II 4.16 Kv Bus Uvr within Specified Frequency.Commitments Listed | | | 05000461/LER-1998-024, :on 980708,failure to Perform Surveillance Testing on Div II Voltage Relays within Specified Frequency of TS Was Noted.Cause of Event Is Under Investigation.Util Expects to Issue Rev to Rept by 980907 |
- on 980708,failure to Perform Surveillance Testing on Div II Voltage Relays within Specified Frequency of TS Was Noted.Cause of Event Is Under Investigation.Util Expects to Issue Rev to Rept by 980907
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) | | 05000461/LER-1998-025, :on 860929,repeated Failures of Switchgear Heat Removal Condenser Gasket Occurred.Caused by Inadequate Design Consideration of Pressure Transient Effects of Shutdown SWS Components.Installed blow-out Resistant Gasket |
- on 860929,repeated Failures of Switchgear Heat Removal Condenser Gasket Occurred.Caused by Inadequate Design Consideration of Pressure Transient Effects of Shutdown SWS Components.Installed blow-out Resistant Gasket
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000461/LER-1998-026, :on 860929,inoperable EP Assembly Circuit Cards Which Monitor Power to RPS Scarm & MSIV Sv Were Noted.Caused by Improper Design of EP Assembly Circuit Cards by Supplier. Procured & Installed Correctly Designed Circuit Cards |
- on 860929,inoperable EP Assembly Circuit Cards Which Monitor Power to RPS Scarm & MSIV Sv Were Noted.Caused by Improper Design of EP Assembly Circuit Cards by Supplier. Procured & Installed Correctly Designed Circuit Cards
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-027, :on 980918,failure to Perform Surveillance Testing on Div II 4.16 Bus Uvr within Specified Frequency Was Noted.Caused by Inadequate Software Change Mgt.Performed Testing on Div II 4.16 Kv Bus Uvr |
- on 980918,failure to Perform Surveillance Testing on Div II 4.16 Bus Uvr within Specified Frequency Was Noted.Caused by Inadequate Software Change Mgt.Performed Testing on Div II 4.16 Kv Bus Uvr
| 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-028, :on 981205,thermal Induced Pressure Locking of SR Power Operated Gate Valves Was Noted.Caused by Inadequate Initial Design.Evaluated GL 95-07 Valves for Susceptibility to Thermal Induced Pressure Locking |
- on 981205,thermal Induced Pressure Locking of SR Power Operated Gate Valves Was Noted.Caused by Inadequate Initial Design.Evaluated GL 95-07 Valves for Susceptibility to Thermal Induced Pressure Locking
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000461/LER-1998-029, :on 860929,discovered That Conductors in Two Containment Electrical Penetrations Did Not Have Adequate Overcurrent Protection.Caused by Original Design Error for Plant.Will Design & Install Required Protective Devices |
- on 860929,discovered That Conductors in Two Containment Electrical Penetrations Did Not Have Adequate Overcurrent Protection.Caused by Original Design Error for Plant.Will Design & Install Required Protective Devices
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000461/LER-1998-030-01, Insufficient Suppression Pool Makeup Volume to Meet Design Basis Suppression Pool Level Requirements Following LOCA, Has Been Cancelled | Insufficient Suppression Pool Makeup Volume to Meet Design Basis Suppression Pool Level Requirements Following LOCA, Has Been Cancelled | | | 05000461/LER-1998-030, :on 980828,insufficient Sp Makeup Vol to Meet Design Basis Sp Level Requirements Following LOCA Was Noted. Cause of Event Is Under Investigation.Corrective Actions to Event Are Pending Outcome of Investigation |
- on 980828,insufficient Sp Makeup Vol to Meet Design Basis Sp Level Requirements Following LOCA Was Noted. Cause of Event Is Under Investigation.Corrective Actions to Event Are Pending Outcome of Investigation
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000461/LER-1998-031, :on 860929,SP Did Not Adequately Consider Accuracy of Installed Instrumentation in Meeting TS Requirements for DG Loading.Caused by Lack of Rigor in Documentation of Evaluations.Reviewed TS SR Parameters |
- on 860929,SP Did Not Adequately Consider Accuracy of Installed Instrumentation in Meeting TS Requirements for DG Loading.Caused by Lack of Rigor in Documentation of Evaluations.Reviewed TS SR Parameters
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-032, :on 980929,noted That Excessive Voltage Drop in Control Circuit for Division 3 Diesel Output Circuit Breaker Could Result in Plant Being Outside Design Basis.Caused by Inadequate Design.Prepared Design Change of Control Circuit |
- on 980929,noted That Excessive Voltage Drop in Control Circuit for Division 3 Diesel Output Circuit Breaker Could Result in Plant Being Outside Design Basis.Caused by Inadequate Design.Prepared Design Change of Control Circuit
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000461/LER-1998-033, :on 981007,inappropriate Clearing of Caution Tagout Resulted in Improved TS LCO 3.4.10 Action A.1 Not Being Met.Caused by Tunnel Vision & Inattention to Detail. New Caution Tagout for Div 2 Shutdown Svc Water,Established |
- on 981007,inappropriate Clearing of Caution Tagout Resulted in Improved TS LCO 3.4.10 Action A.1 Not Being Met.Caused by Tunnel Vision & Inattention to Detail. New Caution Tagout for Div 2 Shutdown Svc Water,Established
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-035, :on 981016,failure to Comply with TS Action Requirements to Immediately Restore AC & DC Electrical Power Sources,Was Discovered.Caused by Inadequate Communications. LCO Tracking Database for Daily Rept Will Be Revised |
- on 981016,failure to Comply with TS Action Requirements to Immediately Restore AC & DC Electrical Power Sources,Was Discovered.Caused by Inadequate Communications. LCO Tracking Database for Daily Rept Will Be Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(1) | | 05000461/LER-1998-036-01, Forwards LER 98-036-01,re Opening Incorrect Electrical Cubicle,Causing Loss of SD Cooling & Leading to Failure to Meet TS Required Action in Required Time.Encl Rept Contains Listed Commitments | Forwards LER 98-036-01,re Opening Incorrect Electrical Cubicle,Causing Loss of SD Cooling & Leading to Failure to Meet TS Required Action in Required Time.Encl Rept Contains Listed Commitments | | | 05000461/LER-1998-037, :on 981215,identified That SR 3.3.3.1.2,which Requires Channel Calibr of Drywell & Primary Containment Hydrogen & Oxygen Analyzers Not Properly Implemented.Caused by Lack of Info Validation & Verification.Procedure Revised |
- on 981215,identified That SR 3.3.3.1.2,which Requires Channel Calibr of Drywell & Primary Containment Hydrogen & Oxygen Analyzers Not Properly Implemented.Caused by Lack of Info Validation & Verification.Procedure Revised
| 10 CFR 50.73(a)(2)(1) |
|