text
LICENSEE EVENT REPCIT (LER)
Form R:v. 2.0 Facihty N.mo (1)
Docket Numbwr (2)
Pags (3)
Quad Cities Unit One 0 l 5 l 0 l 0 l o l 2 l 5 l 4 l 1 l of l 0 l 4 Title (4)
High Pressure Coolant Injection Inoperable Due To Terning Gear Failure.
Event Date (5)
LER Number (6)
Report Date (7)
Other Facihtaa involved (8)
Month Day Year Year Sequential Revision Month Day Year Facihty Docket Numberta)
Number Number Names 0j5l0l0l0l l
l 0l4 ol2 9l7 9l7 0l0l8 0lo 0l4 2l9 9
7 0l5l0l0l0l l
l OPERATING THis REPORT IS SUBMflTED PURSUANT TO THE REQU REN ENTS OF 10CFR MODE (9)
(Check one or more of the following) (11) 1 20A02(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)
POWER 20.405(a)(1)G) 50.36(c)(1)
T50.73(a)G)(v) 73.71(c)
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LEVEL
- - 20.405(a)(1)Gi) 50.36(c)G)
- - 50.73(a)G)(vii)
Other (Specify (10) 1 l0l 0
- - 20A05(a)(1)0ii) 50.73(a)c)0) 50.73(a)C)(viii)(A) an Abstract 20.405(a)(1)(iv) 50.73(a)G)(ii) 50.73(a)G)(viii)(B) below and in 20 405(a)(1)(v) 50.73(a)C)0ii) 50.73(a)G)(x)
Text)
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LICENSEE CON Tact FOR THis LER (la)
NAME TELEPHONE NUMBER AREA CODE Ch.rlis Peterson, Regulatory Affairs Manager. ext. 3609 3
0l9 6l5l4l-l2l2l4l1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEL; IN THIS REPORT (13)
CAU$E SYSTEM (X)MPONENT MANUFACTURER REPORTA1.lf.
CAUSE
OSTEM COMPONENT MANUFACTURER REPORTABLE 10 NPRDS 70 NPRDS I
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I SUP "I.EMENTAL REPORT EXPEca t.u (14)
Expected Month Day Year Subnussion lYES (If yes. complete EXPECTED SUBMIS$10N DATE)
~E"]NO Date (15) l l
l ABSTRACT (Lanut to 1400 spaces i.e.. appromanniety fWieen ample-epnee typewrmen imes) (16)
ABSTRACT On 040297 at approximately 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> the High Pressure Coolant Injection (HPCI)[BJ)
Subsystem turbine was shutdown after quarterly flow rata testing. When the turbine came to rest the turning gear railed to automatically engage. After subsequent testing of the turning gear it was determined that there was a problem with the turning gear engage linkage and the Unit 1 HPCI system was declared inoperable at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 040297.
Unit 1 entered a 14 day Limiting condition for Operation per Technical Specification 3.5.A.3 Action 3.
The turning gear engagement linkages were repaired on 040397 and the HPCI Subsystem was declared operable on 040497 after review of the cause of the failure.
The failure was caused by improper adjustments to the turning gear engagement mechanism on 031397 while the reactor was shutdown.
These adjustments were made at the direction of the system engineer who had an improper understanding of the turning gear mechanism. These adjustments were then improperly tested prior to start-up on 031797. Therefore the failure was not detected until the turbine run perfrrmed on 040297.
There was no effect on the public or the control room personnel due to this event and the safety consequences were minimal.
The person involved in providing the instructions for the turning gear adjustments has been counseled on his failure. The procedure used for testing the turning gear will be revised and appropriate turning gear adjustment instructions will be incorporated into the vendor manual.
LER7497\\003.WPF 9705070298 970429 PDR ADOCK 05000254 S
PDR
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rov. 2.0 FACIllTY NAME (1)
DOuxI NUMBER (2)
LER NUMBER (6)
PAGE (3)
Year Sequential Revision Nurnber Number Quad Cities Unit One 0l5l0l0}Oj2l5)4 9l7 0l0l8 0l0 2 lOFl 0 l 4 TEXI Energy Industry identafication 5ystem (EII5) coces are identified in the text es (XXj
PLANT AND SYSTEM IDENTIFICATION
General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power EVENT IDENTIFICATION:
High Pressure Coolant Injection Inoperable due to turning gear failure A.
CONDITIONS PRIOR TO EVENT
Unit: One Event Date: 040297 Event Time: 1700 Reactor Mode: 1 Mode Name: POWER OPERATION Power levei: 100%
This report was initiated by Licensee Event Report 254\\97-008.
POWER OPERATION Mode (1): Mode switch in the RUN position with average reactor coolant temperature at any temperature.
B.
EVENT DESCRIPTION
On 031397 the Unit 1 High Pressure Coolant Injection (HPCI)[BJ) subsystem turbine turning gear was adjusted under Nuclear Work Request (NWR) #9608080571.
This adjustment was made at the direction of the System Engineer. He had consulted with a Maintenance Work Analyst and the available vendor information prior to providing this direction.
This work was tested by performing manipulations under QCOP 2300-13, "HPCI Turning Gear Operation". On 031797 at 0202 hours0.00234 days <br />0.0561 hours <br />3.339947e-4 weeks <br />7.6861e-5 months <br /> Unit I reactor pressure exceeded 150 pounds per square inch gauge (psig) during start-up from forced outage QlF39. The reactor operated above 150 psig until 032297 at 1404 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.34222e-4 months <br />. Reactor pressure was again increased to greater than 150 psig on 032897 at 2017 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.674685e-4 months <br />. HPCI is required to be operable per Technical Specification 3.5.A.3 Action 3 any time that the reactor pressure is above 150 psig.
On April 2, 1997 at approximately 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> the HPCI turbine was shutdown after quarterly flow rate testing. When the turbine came to rest, the turning gear failed to automatically engage.
The operator in attendance manually engaged the turbine turning gear by pushing on the engagement lever.
After subsequent testing of the turning gear, it was determined that the automatic engagement feature was inoperable. Since the turning gear was inoperable, the Unit 1 HPCI system was declared inoperable at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 040297.
Unit 1 entered a 14 day Limiting Condition for Operation per Technical Specification 3.5.A.3 Action 3.
On 040397 at about 1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br /> adjustments were completed on the Unit 1 HPCI turning gear and this repair had been tested three times. One additional test, a HPCI Pump Operability run (QCOS 2300-01), was completed at 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br /> on 040397. The Operating Department declared the HPCI subsystem operable again on 040497 at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> after verifying that the cause of the turning gear failure had been corrected by the adjustments performed on 040397.
LER254\\9"n008 WPF
I UCENSEE EVENT REPCOT (LER) TEXT CONTINUATION Form Rcv. 2.o FACILrrYJ4AME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
Year Sequennal Revision Number Number Quad Cities Unit One 0l5l0l0l0l2l5l4 9l7 0l0l8 0l0 3 lOFl 0 l 4 TEXT Energy Industry idennficanon System (EIIS) coces are identified in the text as [XXj C.
APPARENT CAUSE OF THE EVERT The apparent cause of this event was cognitive personnel error, in that improper instructions were provided by the System Engineer on how to adjust the HPCI turning gear when the work was performed under Nuclear Work Request #960080571 on 031397.
The System Engineer provided these instructions after consulting with a Maintenance Work Analyst and the available vendor information.
Based on this information and his understanding of turning gear operation, the System Engineer then instructed maintenance personnel on how to adjust the turning gear.
These instructions caused the failure of the automatic engagement feature of the turning gear.
This work was performed while the reactor was shutdown due to a forced outage.
Additionally, an inadequate test was performed to verify the operability of the turning gear after these adjustments were made prior to reactor start-up on 031797.
The testing was performed in accordance with station procedure QCOP 2300-13,
" Turning Gear Operation," which does not provide for fully disengaging and re-engaging the turbine turning gear.
D.
SAFETY ANALYSIS OF THE EVENT The consequences of this event were minimal. The Unit 1 HPCI subsystem was available to start automatically from 031797 to 040397 even though the turning gear was inoperable. The turbine rotor had been properly cooled on the turning gear prior to the adjustments made to the gear on 031397. Had a design basis accident occurred while the turning gear was inoperable and HPCI was required to operate, from 031797 to 040397, HPCI would have started and refilled the reactor vessel as designed.
If the operator had taken manual control of HPCI as directed by the emergency procedures, the subsystem would have remained in operation and would have continued to maintain reactor level in the flow control mode and there would have been no reason to use the turbine turning gear. The HPCI subsystem was unavailable for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> on 040397 while the turning gear was being adjusted to correct this failure.
In the event that the HPCI subsystem tripped with the turbine turning gear inoperable, the turning gear would not have automatically engaged when the turbine coasted to a stop. An operator would have had to be sent to the HPCI room to manually engage the turbine. The HPCI subsystem may have automatically restarted prior to the operator manually engaging the turning gear.
If the turbine restarted without being on turning gear while still hot, severe vibrations and bearing failures may have occurred causing failure of the HPCI subsystem to fulfill its design function.
The Automatic Depressurization System (ADS)[RV] and the Low Pressure Coolant Injection (LPCI)[B0] systems were operable during this event and would also have provided protection for the fuel in the event of a Loss of Coolant Accident.
E.
CORRECTIVE ACTIONS
Immediate corrective actions completed were to manually engage the turbine turning gear when the failure was discovered.
LER254\\97\\008.WPF
\\
LJCENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rw,2.0 FACILITY NAME (1)
DOurl NUMBER (2)
LER NUMBER (6)
PAGE (3)
Year Sequential Revision f
)
Number Number i
Quad Cities Unit Oae 0l5l0l0l0l2l5l4 9l7 0l0l8 0l0 4 lOFl 0 l 4
'I IAT Energy Industry Identification System (tils) coc es are M
- - w in the text as [XX)
Corrective actions which have been completed are:
1.
The turbine turning gear was adjusted on 040397 and tested four times to verify operability of the automatic engagement function.
2.
The engineer who gave the turning gear adjustment instructions has been i
counseled to ensure that the technical information he is providing is correct.
i Future corrective actions are:
1.
Revise QCOP 2300-13 to include steps to fully disengage the turning gear if j
i necessary for testing purposes. (NTS #2541809700801, OPS) This will be
]
completed by 060197.
2.
System Engineer to review with General Electric available information on this type of turning gear to ensure that correct repair instructions are included in the vendor manual and are available for future repairs. (NTS
- 2541809700802, SED).
This will be completed by 090197.
i F.
PREVIOUS EVENTS A review of the PIF and LER databases for the last two years revealed the following I
HPCI Turning Gear failures.
There were no LERs caused by inadequate instructions given to maintenance personnel by engineering:
l 1.
LER 2-95-007 Unit 2 HPCI Turning Gear Motor failed to start due to an unknum cause - This turning gear failure could not be recreated. Turning gear i
operation was monitored during multiple HPCI runs with no further failures.
2.
PIF #96-1642 Unit 2 HPCI Turbine Failed to go on Turning Gear after Surveillance - The turbine was immediately placed onto gear by the operator in j
attendance and the inability to place the turbine on gear could not be recreated. This event was attributed to alignment of the ring gear to clash gear when the turbine came to rest. The procedure was changed to require multiple attempts to engage the turning gear from the control room.
G.
COMPONENT FAILURE DATA
1.
Component Description: Turbine Turning Gear Manufacturer:
General Electric Model Number: M 567 LER254\\97\\008.WPF i
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| | | Reporting criterion |
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| 05000254/LER-1997-001, :on 970117 & 07,discovered TS Required,Once Per Shift Channel Check Readings Not Completed within Required Twelve H Time Interval Plus 25% Max Allowable Extension. Caused by Personnel Error.Readings Performed |
- on 970117 & 07,discovered TS Required,Once Per Shift Channel Check Readings Not Completed within Required Twelve H Time Interval Plus 25% Max Allowable Extension. Caused by Personnel Error.Readings Performed
| 10 CFR 50.73(a)(2)(1) | | 05000265/LER-1997-001-01, :on 970227,initiation of High Pressure Coolant Injection Occurred Due to Deficient Procedures.Will Revise Surveillance Procedures,Will Review Prerequisites of All Im Procedures & Will Communicate Mgt Expectations to Personne |
- on 970227,initiation of High Pressure Coolant Injection Occurred Due to Deficient Procedures.Will Revise Surveillance Procedures,Will Review Prerequisites of All Im Procedures & Will Communicate Mgt Expectations to Personnel
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(B) | | 05000265/LER-1997-001, Forwards LER 97-001-00 Re Automatic Actuation of Any Esf. Commitments Made by Ltr,Listed | Forwards LER 97-001-00 Re Automatic Actuation of Any Esf. Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation | | 05000265/LER-1997-001-07, :on 970227,instrument Maintenance Dept Was Performing Procedure to Test HPCI Initiation Logic.Caused by Deficient Procedure.Order Was Issued for All non-routine |
- on 970227,instrument Maintenance Dept Was Performing Procedure to Test HPCI Initiation Logic.Caused by Deficient Procedure.Order Was Issued for All non-routine
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(A) | | 05000254/LER-1997-002-02, :on 970127,several Isolable Piping Sections Could Experience Stresses Above Update FSAR Allowables Due to post-loss of Coolant Accident Thermal Pressurization. Initial Operability Evaluation Was Completed on 970124 |
- on 970127,several Isolable Piping Sections Could Experience Stresses Above Update FSAR Allowables Due to post-loss of Coolant Accident Thermal Pressurization. Initial Operability Evaluation Was Completed on 970124
| | | 05000254/LER-1997-002, Forwards LER 97-002-00 Documenting Condition That Was Discovered at Quad Cities Nuclear Power Station.Util Commitments Made within Ltr,Listed | Forwards LER 97-002-00 Documenting Condition That Was Discovered at Quad Cities Nuclear Power Station.Util Commitments Made within Ltr,Listed | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000265/LER-1997-002-05, :on 970228,unit 2 Was Shutdown,Because Four Main Steam Relief Valve Closure Time Did Not Meet IST Program Limits.Ist Acceptance Criteria for PORVs Will Be Revised Using Data Obtained from Qcos 0203-03 on 022897 |
- on 970228,unit 2 Was Shutdown,Because Four Main Steam Relief Valve Closure Time Did Not Meet IST Program Limits.Ist Acceptance Criteria for PORVs Will Be Revised Using Data Obtained from Qcos 0203-03 on 022897
| | | 05000265/LER-1997-002-01, :on 970301,Unit 2 Was Shutdown Per TS 3.5.A & 3.6.F.Caused by Personnel Cognitive Error.Containment Procedure Changes Were Implemented to Prevent Containment Pressure Suppression Bypass |
- on 970301,Unit 2 Was Shutdown Per TS 3.5.A & 3.6.F.Caused by Personnel Cognitive Error.Containment Procedure Changes Were Implemented to Prevent Containment Pressure Suppression Bypass
| | | 05000265/LER-1997-002, Forwards LER 97-002-00 Re Condition Prohibited by Plant Tss. Util Commitments Made by Ltr,Listed | Forwards LER 97-002-00 Re Condition Prohibited by Plant Tss. Util Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(1) | | 05000254/LER-1997-003, Forwards LER 97-003-00 IAW 10CFR50.73(a)(2)(v)(B)(D). Procedure Qcap 0307-02, ASME Section XI Repair & Replacement Program Preparation, Attachment a, Section XI Repair/Replacement Program Will Be Revised Re VT-2 | Forwards LER 97-003-00 IAW 10CFR50.73(a)(2)(v)(B)(D). Procedure Qcap 0307-02, ASME Section XI Repair & Replacement Program Preparation, Attachment a, Section XI Repair/Replacement Program Will Be Revised Re VT-2 | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | | 05000265/LER-1997-003-04, :on 970321,2B Core Spray Room Cooler Fouled Due to Hydrolyzing Debris.Cs Room Cooler Was Cleaned Under Nwr 960039336-01 & Qctp 1110-12, ECCS Room Cooler Trending Program, Has Recently Been Rewritten |
- on 970321,2B Core Spray Room Cooler Fouled Due to Hydrolyzing Debris.Cs Room Cooler Was Cleaned Under Nwr 960039336-01 & Qctp 1110-12, ECCS Room Cooler Trending Program, Has Recently Been Rewritten
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000254/LER-1997-003-05, :on 970429,visual Exam (VT-2) Was Not Performed Due to Procedural Deficiencies Following HPCI Sys Valve Replacement Required by Asme,Section XI & TS Section 4.0.E. Examined VT-2 of 1-2301-45 Valve |
- on 970429,visual Exam (VT-2) Was Not Performed Due to Procedural Deficiencies Following HPCI Sys Valve Replacement Required by Asme,Section XI & TS Section 4.0.E. Examined VT-2 of 1-2301-45 Valve
| | | 05000265/LER-1997-003-01, Forwards LER 97-003-01 Re Core Spray Room Cooler 2B That Fouled Due to Hydrolyzing Debris.Commitment Listed | Forwards LER 97-003-01 Re Core Spray Room Cooler 2B That Fouled Due to Hydrolyzing Debris.Commitment Listed | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000265/LER-1997-004, Forwards LER 97-004-00,IAW 10CFR50.73(a)(2)(ii)(B).Unit 1 DWEDS & DWFDS Will Be Examined to Verify Video Tape Determination During Next Refueling Shutdown to Ensure Covers on Unit Installed Per Applicable Design Drawings | Forwards LER 97-004-00,IAW 10CFR50.73(a)(2)(ii)(B).Unit 1 DWEDS & DWFDS Will Be Examined to Verify Video Tape Determination During Next Refueling Shutdown to Ensure Covers on Unit Installed Per Applicable Design Drawings | 10 CFR 50.73(a)(2) | | 05000265/LER-1997-004-06, :on 970509,drywell Equipment Drain Sump & Floor Drain Sump Covers Were Not Constructed IAW Design Drawings, Due to Original Construction Error.Design Change Package Has Been Completed |
- on 970509,drywell Equipment Drain Sump & Floor Drain Sump Covers Were Not Constructed IAW Design Drawings, Due to Original Construction Error.Design Change Package Has Been Completed
| 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 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1997-004-03, :on 961026,RHR Svc Water Pumps Declared Inoperable Due to Inadequate Evaluation of Replacement Pump Casing Bolts.Rhrsw Pump Bolting Inspected & Questionable Bolting Replaced |
- on 961026,RHR Svc Water Pumps Declared Inoperable Due to Inadequate Evaluation of Replacement Pump Casing Bolts.Rhrsw Pump Bolting Inspected & Questionable Bolting Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1997-005-03, :on 970319,HPCI Subsystem Was Made Inoperable to Protect Equipment Due to Uncertainties Re Abandoned Power Feed Cable,Which Had Been Inappropriately Abandoned. Plant Design Documents Have Been Updated |
- on 970319,HPCI Subsystem Was Made Inoperable to Protect Equipment Due to Uncertainties Re Abandoned Power Feed Cable,Which Had Been Inappropriately Abandoned. Plant Design Documents Have Been Updated
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(viii)(A) | | 05000254/LER-1997-005, Forwards LER 97-005-00 IAW Requirements of 10CFR50.73(a)(2)(v)(D) W/Listed Commitments | Forwards LER 97-005-00 IAW Requirements of 10CFR50.73(a)(2)(v)(D) W/Listed Commitments | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000265/LER-1997-005-01, Forwards LER 97-005-01 Re Unit 2 Reactor Placed in Mode 2 W/O Required Number of Emergency Diesel Generators Operable. Commitment Listed | Forwards LER 97-005-01 Re Unit 2 Reactor Placed in Mode 2 W/O Required Number of Emergency Diesel Generators Operable. Commitment Listed | 10 CFR 50.73(a)(2)(1) | | 05000265/LER-1997-005-02, :on 970608,Unit 2 Reactor Was Placed in Mode 2 W/O Required Number of EDGs Operable.Caused by Installation of Replacement Air Start Motors Which Did Not Have Same Characteristics as Original Motors.Revised Alternate Parts |
- on 970608,Unit 2 Reactor Was Placed in Mode 2 W/O Required Number of EDGs Operable.Caused by Installation of Replacement Air Start Motors Which Did Not Have Same Characteristics as Original Motors.Revised Alternate Parts
| 10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000265/LER-1997-006, Forwards LER 97-006-00 Re Cable in Unit 2 Being in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.List of Commitments Provided | Forwards LER 97-006-00 Re Cable in Unit 2 Being in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.List of Commitments Provided | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | | 05000265/LER-1997-006-01, :on 970729,cable 20865 Was Located in Same Turbine Bldg Fire Area as Fire of Concern & Could Have Been Damaged by Fire.Caused by Poor Work Practices.Revised Qarp 1000-01, Safe Shutdown Procedure C1 |
- on 970729,cable 20865 Was Located in Same Turbine Bldg Fire Area as Fire of Concern & Could Have Been Damaged by Fire.Caused by Poor Work Practices.Revised Qarp 1000-01, Safe Shutdown Procedure C1
| | | 05000254/LER-1997-006-03, :on 970327,loss of Reactor Coolant Inventory in Excess of Design Basis Limits Occurred Due to Inadequate Procedural Guidance.Procedure Qcop 1200-07 Was Revised to Administratively Control Power Feed Breaker |
- on 970327,loss of Reactor Coolant Inventory in Excess of Design Basis Limits Occurred Due to Inadequate Procedural Guidance.Procedure Qcop 1200-07 Was Revised to Administratively Control Power Feed Breaker
| | | 05000254/LER-1997-006, Forwards LER 97-006,Rev 00 & Submits Commitments Related to LER | Forwards LER 97-006,Rev 00 & Submits Commitments Related to LER | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000265/LER-1997-006-06, :on 970729,cable for Unit 2 in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.Rev to Ssd Analysis to Credit Alternate Power Feeds,Will Be Performed |
- on 970729,cable for Unit 2 in Same Fire Area as Fire of Concern Due to Ineffective Implementation of Original Safe Shutdown Analysis.Rev to Ssd Analysis to Credit Alternate Power Feeds,Will Be Performed
| | | 05000254/LER-1997-007-03, :on 970331,unit One Emergency DG Inadvertently Started Due to Error by RSO While Operating Control Switch. Nso Removed from All Licensed Duties Until Completion of Remediation Plan |
- on 970331,unit One Emergency DG Inadvertently Started Due to Error by RSO While Operating Control Switch. Nso Removed from All Licensed Duties Until Completion of Remediation Plan
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000254/LER-1997-008, Forwards LER 97-008,Rev 00 & Submits Commitments.Revised Qcop 2300-13 Is to Include Steps to Fully Disengage Turning Gear If Necessary for Testing Purposes | Forwards LER 97-008,Rev 00 & Submits Commitments.Revised Qcop 2300-13 Is to Include Steps to Fully Disengage Turning Gear If Necessary for Testing Purposes | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1997-008-01, :on 970402,high Pressure Coolant Injection Was Inoperable Due to Turning Gear Failure.Turbine Turning Gear Was Manually Engaged |
- on 970402,high Pressure Coolant Injection Was Inoperable Due to Turning Gear Failure.Turbine Turning Gear Was Manually Engaged
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000265/LER-1997-008, Forwards LER 97-008-00 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed | Forwards LER 97-008-00 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(1) | | 05000265/LER-1997-008-05, :on 970629,five Control Rod Drives Did Not Receive Required Scram Insertion Time Testing Prior to 40% Power.Caused by Ineffective Operations.Rods Associated with Nwr Were Scram Timed & Declared Operable |
- on 970629,five Control Rod Drives Did Not Receive Required Scram Insertion Time Testing Prior to 40% Power.Caused by Ineffective Operations.Rods Associated with Nwr Were Scram Timed & Declared Operable
| 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)(iii)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1997-009, Forwards LER 97-009-00 Per 10CFR50.73(a)(2)(v)(D).Commitment Included in Ltr | Forwards LER 97-009-00 Per 10CFR50.73(a)(2)(v)(D).Commitment Included in Ltr | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1997-009-03, :on 970504,both Trains of Standby Gas Treatment Sys Were Inoperable.Caused by Cognitive Peersonnel Error. Blown Fuse Replaced,A Train of SBGTS Was Tested & Declared Operable & SRO Test Director Counseled |
- on 970504,both Trains of Standby Gas Treatment Sys Were Inoperable.Caused by Cognitive Peersonnel Error. Blown Fuse Replaced,A Train of SBGTS Was Tested & Declared Operable & SRO Test Director Counseled
| | | 05000265/LER-1997-009-05, :on 970713,control Room Personnel Misread Indication Delaying Discovery of Abnormal Offgas Radiation Readings Was Discovered.Caused by Personnel Error.Chemistry Sampled off-gas |
- on 970713,control Room Personnel Misread Indication Delaying Discovery of Abnormal Offgas Radiation Readings Was Discovered.Caused by Personnel Error.Chemistry Sampled off-gas
| 10 CFR 50.73(a)(2)(x)
10 CFR 50.73(s)(2)(v) | | 05000254/LER-1997-010-02, :on 970407,train B of Control Room HVAC Sys Was Inoperable Due to Loss of Refrigerant.Caused by Failed Fitting.Replaced Fitting & Sys Tested Satisfactorily |
- on 970407,train B of Control Room HVAC Sys Was Inoperable Due to Loss of Refrigerant.Caused by Failed Fitting.Replaced Fitting & Sys Tested Satisfactorily
| | | 05000265/LER-1997-010-05, :on 970819,2B Offgas Hydrogen Analyzer Declared Inoperable.Caused by Communication Error.Offgas Hydrogen Sample Immediately Taken & Analyzed & Technicians Involved Counseled |
- on 970819,2B Offgas Hydrogen Analyzer Declared Inoperable.Caused by Communication Error.Offgas Hydrogen Sample Immediately Taken & Analyzed & Technicians Involved Counseled
| | | 05000265/LER-1997-010, Forwards LER 97-010-00 IAW Requirements of 10CFR50.73(a)(2)(i)(B).No Commitments Made | Forwards LER 97-010-00 IAW Requirements of 10CFR50.73(a)(2)(i)(B).No Commitments Made | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1997-010, Forwards LER 97-010-00 Which Repts Event That Occurred at Quad Cities Nuclear Station,Per 10CFR50.73(a)(2)(v)(D). Commitment Made by Ltr,Submitted | Forwards LER 97-010-00 Which Repts Event That Occurred at Quad Cities Nuclear Station,Per 10CFR50.73(a)(2)(v)(D). Commitment Made by Ltr,Submitted | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1997-011-01, :on 970409,RHRSW Sys Was Made Inoperable Due to Uncertainties Related to 4 Kv Air magne-blast Horizontal Gas Circuit Breakers.Caused by Improper Manufacturers Switch Mounting Design.Pif 97-1276 Written to Investigate Cause |
- on 970409,RHRSW Sys Was Made Inoperable Due to Uncertainties Related to 4 Kv Air magne-blast Horizontal Gas Circuit Breakers.Caused by Improper Manufacturers Switch Mounting Design.Pif 97-1276 Written to Investigate Cause
| | | 05000254/LER-1997-011, Forwards LER 97-011-00 Re an Event or Condition That Alone Could Have Prevented Fulfillment of Safety Function of Structures or Sys That Are Needed to Remove Residual Heat. Commitments Made by Ltr,Submitted | Forwards LER 97-011-00 Re an Event or Condition That Alone Could Have Prevented Fulfillment of Safety Function of Structures or Sys That Are Needed to Remove Residual Heat. Commitments Made by Ltr,Submitted | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(1) | | 05000265/LER-1997-011-05, :on 970904,determined That Offgas H Sampling Frequency Was Less than That Required by Ts.Caused by Inadequate Tracking of LCO Actions Re Recombiner Temp.Began Sampling at Four H Intervals |
- on 970904,determined That Offgas H Sampling Frequency Was Less than That Required by Ts.Caused by Inadequate Tracking of LCO Actions Re Recombiner Temp.Began Sampling at Four H Intervals
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000265/LER-1997-012-06, :on 971121,loss of Shutdown Cooling Due to Loss of Power to Reactor Protection Bus 2B.Caused by Undervoltage Condition at RPS 2B Bus When Bus Was Loaded.Voltage Regulating Transformer Cleaned & Adjusted |
- on 971121,loss of Shutdown Cooling Due to Loss of Power to Reactor Protection Bus 2B.Caused by Undervoltage Condition at RPS 2B Bus When Bus Was Loaded.Voltage Regulating Transformer Cleaned & Adjusted
| | | 05000254/LER-1997-013, Forwards LER 97-013-00 Re Any Single Cause of Inoperable Independent Train or Channel in Single Sys Designed to Remove Residual Heat.Commitments Made by Ltr,Listed | Forwards LER 97-013-00 Re Any Single Cause of Inoperable Independent Train or Channel in Single Sys Designed to Remove Residual Heat.Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000254/LER-1997-013-01, :on 970416,RCIC Area High Temperature Switch Would Not Actuate Due to Excess Sealing Varnish Applied by Technician.Caused by Personnel Error.Removed Excess Varnish from Switch,Calibrated & Functionally Tested Switch |
- on 970416,RCIC Area High Temperature Switch Would Not Actuate Due to Excess Sealing Varnish Applied by Technician.Caused by Personnel Error.Removed Excess Varnish from Switch,Calibrated & Functionally Tested Switch
| | | 05000254/LER-1997-014, Forwards LER 97-014-00 Per 10CFR50.73(a)(2)(i)(B).Listed Commitment Made by Ltr | Forwards LER 97-014-00 Per 10CFR50.73(a)(2)(i)(B).Listed Commitment Made by Ltr | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1997-014-01, :on 970416,target Rock Safety Relief Valve Removed from Unit 2 During Q2R13 & Unit 1 During Q1R14 Were Not Tested within 12 Months.Caused by Defective Procedure. Revised Maintenance Procedure |
- on 970416,target Rock Safety Relief Valve Removed from Unit 2 During Q2R13 & Unit 1 During Q1R14 Were Not Tested within 12 Months.Caused by Defective Procedure. Revised Maintenance Procedure
| | | 05000265/LER-1997-015-05, :on 970622,TS Required Surveillance Was Not Properly Performed Due to Apparent Unfamiliarity w/10CFR50 Appendix G Which Resulted in Insufficient Tp.Cause Is Under Investigation.No Action Taken at Present Time |
- on 970622,TS Required Surveillance Was Not Properly Performed Due to Apparent Unfamiliarity w/10CFR50 Appendix G Which Resulted in Insufficient Tp.Cause Is Under Investigation.No Action Taken at Present Time
| | | 05000254/LER-1997-015, Informs NRC of Change of Committed Due Date Contained in LER 97-015,dtd 970812.Station Changing Due Date of Commitment to 990528 | Informs NRC of Change of Committed Due Date Contained in LER 97-015,dtd 970812.Station Changing Due Date of Commitment to 990528 | | | 05000254/LER-1997-015-02, :on 970622,discovered That 10CFRE50,App G Pressure Testing Requirements Were Not Met.Caused by Failure of Station Personnel to Recognize All Organizational Challenges Which Could Occur in Controlling.Performed Test |
- on 970622,discovered That 10CFRE50,App G Pressure Testing Requirements Were Not Met.Caused by Failure of Station Personnel to Recognize All Organizational Challenges Which Could Occur in Controlling.Performed Test
| | | 05000254/LER-1997-016-01, :on 970509,DG CW IST Requirements Were Not Completed When Inaccurate Predefined Work Request Used for Scheduling Was Implemented.Caused by Inappropriately Titled Work Request.Qcos 6600-08 Was Completed for Unit 1 |
- on 970509,DG CW IST Requirements Were Not Completed When Inaccurate Predefined Work Request Used for Scheduling Was Implemented.Caused by Inappropriately Titled Work Request.Qcos 6600-08 Was Completed for Unit 1
| | | 05000254/LER-1997-016, Forwards LER 97-016-00 Re DG CW IST Requirements Not Being Completed When Inaccurate Predefined Work Request Was Implemented | Forwards LER 97-016-00 Re DG CW IST Requirements Not Being Completed When Inaccurate Predefined Work Request Was Implemented | 10 CFR 50.73(a)(2)(1) |
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