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| | Title = Forwards LER 96-017-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items | | | Title = Forwards LER 96-017-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items |
| | Plant = | | | Plant = |
| | Reporting criterion = | | | Reporting criterion = 10 CFR 50.73(a)(2)(iv) |
| | Power level = | | | Power level = |
| | Mode = | | | Mode = |
| | Docket = 05000254 | | | Docket = 05000254 |
| | LER year = 2096 | | | LER year = 1996 |
| | LER number = 17 | | | LER number = 17 |
| | LER revision = | | | LER revision = 0 |
| | Event date = | | | Event date = |
| | Report date = | | | Report date = |
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| o.mnion.caith tar.on o,mpan3 Quad Otics Generating stanon 2l'io 2tu,th Asenue %>rth - | | o.mnion.caith tar.on o,mpan3 Quad Otics Generating stanon 2l'io 2tu,th Asenue %>rth o,raosa.n.<,u a n su 1,ci 3ow>s. 22 o LWP-96-068 September 13, 1996 U.S. Nuclear Regulatory Commission i |
| o,raosa.n.<,u a n su | | Washington, DC 20555 Attention: Document Control Desk |
| , 1,ci 3ow>s . 22 o l
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| LWP-96-068 ! | |
| l September 13, 1996 U.S. Nuclear Regulatory Commission ;
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| i Washington, DC 20555 I Attention: Document Control Desk
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| ==Reference:== | | ==Reference:== |
| Quad Cities Nuclear Power Station Docket Number 50-254, DPR-29, Unit One Enclosed is Licensee Event Report (LER) 96-017, Revision 00, for Quad ! | | Quad Cities Nuclear Power Station Docket Number 50-254, DPR-29, Unit One Enclosed is Licensee Event Report (LER) 96-017, Revision 00, for Quad Cities Nuclear Power Station. |
| Cities Nuclear Power Station. ' | | This report is submitted in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73(a)(2)(iv). The licensee shall report any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature. |
| This report is submitted in accordance with the requirements of the 1 l | | The following commitments are being made by this letter: |
| Code of Federal Regulations, Title 10, Part 50.73(a)(2)(iv). The ! | | 1. |
| licensee shall report any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature. ! | | Licensed Operator lesson plans will be revised to ensure the details of the 8/25/96 event and pressure transducer calibration data affecting the EHC system are presented in initial training i |
| l The following commitments are being made by this letter:
| |
| : 1. Licensed Operator lesson plans will be revised to ensure the details of the 8/25/96 event and pressure transducer calibration data affecting the EHC system are presented in initial training i
| |
| by 12/31/96. | | by 12/31/96. |
| : 2. The 0/25/96 event will be presented to Operators and Engineers in retraining by 12/31/96.
| | 2. |
| : 3. QCGF 1-1, Normal Unit Startup, will be revised to ensure the condenser backpressure bypass permissive is satisfied prior to lowering the EHC setpoint into a control range. This revision will be completed by 11/01/96.
| | The 0/25/96 event will be presented to Operators and Engineers in retraining by 12/31/96. |
| : 4. The 8/25/96 event will be tailgated with the Training Department by 12/31/96 emphasizing the instructor's responsibility to communicate such discovered information in training materials to ensure thorough and consistent training.
| | 3. |
| [ | | QCGF 1-1, Normal Unit Startup, will be revised to ensure the condenser backpressure bypass permissive is satisfied prior to lowering the EHC setpoint into a control range. This revision will be completed by 11/01/96. |
| pO STMGRW68% LWP 9610010155 960913 PDR ADOCK 05000254 S PDR s i owom ( ompan3 | | 4. |
| | The 8/25/96 event will be tailgated with the Training Department by 12/31/96 emphasizing the instructor's responsibility to communicate such discovered information in training materials to ensure thorough and consistent training. |
| | [pO STMGRW68% LWP 9610010155 960913 PDR ADOCK 05000254 S |
| | PDR s i owom ( ompan3 |
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| :l . ... | | :l LWP-96-068 t |
| LWP-96-068 t | | September 13, 1996 j |
| : September 13, 1996 j .page 2 j.
| | .page 2 j. |
| i | | i If there are any questions or comments concerning this letter, please i |
| (
| | i refer them'to Charles Peterson, Regulatory Affairs Manager at l |
| If there are any questions or comments concerning this letter, please i i | | 309-654-2241, ext. 3602. |
| refer them'to Charles Peterson, Regulatory Affairs Manager at l 4 | | 4 i |
| 309-654-2241, ext. 3602. ' | | } |
| i ! | | Respectfully, q |
| } Respectfully, i q COMMONWEALTH EDISON 3 ! | | i COMMONWEALTH EDISON 3 |
| QU ITIES LEAR POWER STATION l | | QU ITIES LEAR POWER STATION l |
| K Lf W. Pearce | | K Lf W. Pearce Station Manager i |
| * Station Manager i
| |
| LWP/NC/as t | | LWP/NC/as t |
| . Enclosure '
| | Enclosure A. B. Beach,-Regional Administrator, Region ~III l |
| cc: A. B. Beach,-Regional Administrator, Region ~III l R. M. Pulsifer, Project Manager, NRR '
| | cc: |
| ! C. Miller, Senior Resident Inspector, Quad Cities
| | R. M. Pulsifer, Project Manager, NRR C. Miller, Senior Resident Inspector, Quad Cities R. J. Singer, Mid American Energy Company s |
| ! R. J. Singer, Mid American Energy Company s i D. C. Tubbs, Mid American Energy Company l P. Piet, Licensing,-Comed 4
| | i D. C. Tubbs, Mid American Energy Company l |
| ' F. Spangenberg, Regulatory Affairs Manager, Dresden l INPO Records Center !
| | P. Piet, Licensing,-Comed F. Spangenberg, Regulatory Affairs Manager, Dresden l |
| i ; | | 4 INPO Records Center i |
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LER-1996-017, Forwards LER 96-017-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items |
| Event date: |
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| Report date: |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(iv), System Actuation |
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| 2541996017R00 - NRC Website |
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text
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o.mnion.caith tar.on o,mpan3 Quad Otics Generating stanon 2l'io 2tu,th Asenue %>rth o,raosa.n.<,u a n su 1,ci 3ow>s. 22 o LWP-96-068 September 13, 1996 U.S. Nuclear Regulatory Commission i
Washington, DC 20555 Attention: Document Control Desk
]
Reference:
Quad Cities Nuclear Power Station Docket Number 50-254, DPR-29, Unit One Enclosed is Licensee Event Report (LER)96-017, Revision 00, for Quad Cities Nuclear Power Station.
This report is submitted in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73(a)(2)(iv). The licensee shall report any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature.
The following commitments are being made by this letter:
1.
Licensed Operator lesson plans will be revised to ensure the details of the 8/25/96 event and pressure transducer calibration data affecting the EHC system are presented in initial training i
by 12/31/96.
2.
The 0/25/96 event will be presented to Operators and Engineers in retraining by 12/31/96.
3.
QCGF 1-1, Normal Unit Startup, will be revised to ensure the condenser backpressure bypass permissive is satisfied prior to lowering the EHC setpoint into a control range. This revision will be completed by 11/01/96.
4.
The 8/25/96 event will be tailgated with the Training Department by 12/31/96 emphasizing the instructor's responsibility to communicate such discovered information in training materials to ensure thorough and consistent training.
[pO STMGRW68% LWP 9610010155 960913 PDR ADOCK 05000254 S
PDR s i owom ( ompan3
t t
- l LWP-96-068 t
September 13, 1996 j
.page 2 j.
i If there are any questions or comments concerning this letter, please i
i refer them'to Charles Peterson, Regulatory Affairs Manager at l
309-654-2241, ext. 3602.
4 i
}
Respectfully, q
i COMMONWEALTH EDISON 3
QU ITIES LEAR POWER STATION l
K Lf W. Pearce Station Manager i
LWP/NC/as t
Enclosure A. B. Beach,-Regional Administrator, Region ~III l
cc:
R. M. Pulsifer, Project Manager, NRR C. Miller, Senior Resident Inspector, Quad Cities R. J. Singer, Mid American Energy Company s
i D. C. Tubbs, Mid American Energy Company l
P. Piet, Licensing,-Comed F. Spangenberg, Regulatory Affairs Manager, Dresden l
4 INPO Records Center i
i i
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i I
l i
h STMGRWM96.LWP t
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| | | Reporting criterion |
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| 05000254/LER-1996-001-07, :on 960303,B CR HVAC Sys Inoperable Due to Malfunctioning Relay Which Prevented Isolation of Air Handling Unit Fan.Ems Replaced Relay & Forwarded Damaged Relay to Engineering for Evaluation |
- on 960303,B CR HVAC Sys Inoperable Due to Malfunctioning Relay Which Prevented Isolation of Air Handling Unit Fan.Ems Replaced Relay & Forwarded Damaged Relay to Engineering for Evaluation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000265/LER-1996-001, Forwards LER 96-001-00.Listed Commitments Made,Including Event Will Be Included as Part of Continuing Training for Both Licensed Operators & Engineering Dept | Forwards LER 96-001-00.Listed Commitments Made,Including Event Will Be Included as Part of Continuing Training for Both Licensed Operators & Engineering Dept | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000265/LER-1996-001-10, :on 960417,HPCIS Was Declared Inoperable Due to Procedural Deficiency Which Allowed Isolation of Turbine Exhaust Vacuum.Licensed Operators Have Been Trained on Procedure Changes |
- on 960417,HPCIS Was Declared Inoperable Due to Procedural Deficiency Which Allowed Isolation of Turbine Exhaust Vacuum.Licensed Operators Have Been Trained on Procedure Changes
| 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000265/LER-1996-002, Forwards LER 96-002-00.Licensee Revised Qcop 2300-1 to Ensure That Piping Downstream of Sys Isolation Valve Is Filled & Vented After Maint | Forwards LER 96-002-00.Licensee Revised Qcop 2300-1 to Ensure That Piping Downstream of Sys Isolation Valve Is Filled & Vented After Maint | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000265/LER-1996-002-10, :on 961009,HPCI Sys Declared Inoperable.Caused by Improper Filling & Venting After Aug 1996 Maint.Air Purged from Sys & line-up Procedure Revised to Ensure Filling & Venting of Piping |
- on 961009,HPCI Sys Declared Inoperable.Caused by Improper Filling & Venting After Aug 1996 Maint.Air Purged from Sys & line-up Procedure Revised to Ensure Filling & Venting of Piping
| | | 05000254/LER-1996-002-04, :on 960220,CR HVAC Sys Inoperable.Caused by Design Oversight Involving Toxic Gas Anlayzer.On 960223 Procedure Change to Qcop 5750-09, CR Ventilation Sys, Made to Allow for Operation of Booster Fans |
- on 960220,CR HVAC Sys Inoperable.Caused by Design Oversight Involving Toxic Gas Anlayzer.On 960223 Procedure Change to Qcop 5750-09, CR Ventilation Sys, Made to Allow for Operation of Booster Fans
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | | 05000265/LER-1996-003-01, :on 961112,Unit 2 LPCI Was Declared Inoperable. Caused by Failure of 2D RHR Pump Discharge Check Valve.Lpci Kf Pressure Was re-established within One Hour |
- on 961112,Unit 2 LPCI Was Declared Inoperable. Caused by Failure of 2D RHR Pump Discharge Check Valve.Lpci Kf Pressure Was re-established within One Hour
| | | 05000265/LER-1996-003-13, :on 961112,Unit 2 LPCI Was Declared Inoperable to 2D RHR Pump Discharge Check Valve Failure.Lpci Kf Was re-established within 1 Hour & Operability Determination Was Completed for PIF 96-3196 |
- on 961112,Unit 2 LPCI Was Declared Inoperable to 2D RHR Pump Discharge Check Valve Failure.Lpci Kf Was re-established within 1 Hour & Operability Determination Was Completed for PIF 96-3196
| | | 05000265/LER-1996-003, Forwards LER 96-003-00 Submitted IAW Requirements of 10CFR50.73(a)(2)(v)(D).Commitments Made by Ltr,Submitted | Forwards LER 96-003-00 Submitted IAW Requirements of 10CFR50.73(a)(2)(v)(D).Commitments Made by Ltr,Submitted | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1996-003-02, :on 960222,unanticipated Start Occurred on Unit 1 Edg.Caused by Inadequate Guidance within Procedure Qcmms 6600-03.Procedure Qcmms 6600-03 Will Be Revised to Clarify Switch Settings |
- on 960222,unanticipated Start Occurred on Unit 1 Edg.Caused by Inadequate Guidance within Procedure Qcmms 6600-03.Procedure Qcmms 6600-03 Will Be Revised to Clarify Switch Settings
| 10 CFR 50.73(a)(2) | | 05000254/LER-1996-003, Forwards LER 96-003-00 Re Unit 1 Start of Egd Due to Inadequate Procedure | Forwards LER 96-003-00 Re Unit 1 Start of Egd Due to Inadequate Procedure | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000254/LER-1996-004-01, :on 960130,HPCI Sys Declared Inoperable Due to Gland Exhauster Breaker Trip.Hpci Gland Exhauster Breaker Replaced & Tested for Proper Operation & AOP Time Delay Bypass Switches in Starting Circuit Replaced |
- on 960130,HPCI Sys Declared Inoperable Due to Gland Exhauster Breaker Trip.Hpci Gland Exhauster Breaker Replaced & Tested for Proper Operation & AOP Time Delay Bypass Switches in Starting Circuit Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | | 05000254/LER-1996-005-07, :on 960203,B CR HVAC Sys Declared Inoperable Due to Outside Air Temp.Submitted TS Change Requesting That Heater Power Be Measured Instead of Differential Temp Across Heater to Determine Operability |
- on 960203,B CR HVAC Sys Declared Inoperable Due to Outside Air Temp.Submitted TS Change Requesting That Heater Power Be Measured Instead of Differential Temp Across Heater to Determine Operability
| | | 05000254/LER-1996-006, :on 960210,TS 3.0.A Incorrectly Invoked Due to Procedural & Operator Knowledge Deficiencies.Policy Statement Developed & Presented to Licensed Operator Re Expectations for Use & Entry Into TS 3.0.A |
- on 960210,TS 3.0.A Incorrectly Invoked Due to Procedural & Operator Knowledge Deficiencies.Policy Statement Developed & Presented to Licensed Operator Re Expectations for Use & Entry Into TS 3.0.A
| 10 CFR 50.73(a)(2)(i) | | 05000254/LER-1996-007-02, :on 960510,secondary Containment Damaged.Caused by Tornado.Initiated Shutdown,Ac Power Restored to Prompt Notification Sys & Station Blackout Bldg Cables Spliced Per Er 9603099 |
- on 960510,secondary Containment Damaged.Caused by Tornado.Initiated Shutdown,Ac Power Restored to Prompt Notification Sys & Station Blackout Bldg Cables Spliced Per Er 9603099
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(e)(2)(vii) | | 05000254/LER-1996-008-02, :on 960607,TS Required Pressure Not Met During Local Leak Rate Testing.Caused by Procedural Deficiency. Procedure Changes Submitted & Check Valves Retested Using Appropriate Vent Paths |
- on 960607,TS Required Pressure Not Met During Local Leak Rate Testing.Caused by Procedural Deficiency. Procedure Changes Submitted & Check Valves Retested Using Appropriate Vent Paths
| 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-008, Forwards LER 96-008,Rev 00 & Makes Following Commitment: Procedure Qcts 0600-34 Will Be Revised to Ensure Appropriate Vent Path Exists When Leak Rate Testing 2251(2)-81A/B Panels | Forwards LER 96-008,Rev 00 & Makes Following Commitment: Procedure Qcts 0600-34 Will Be Revised to Ensure Appropriate Vent Path Exists When Leak Rate Testing 2251(2)-81A/B Panels | 10 CFR 50.73(a)(2)(1) | | 05000254/LER-1996-009-01, :on 960523,noted Discrepancy in Cable Length Modeled in Existing Degraded Voltage Calculations.Caused by Design Analysis Deficiency.Performed Design Changes to Correct Voltage Problems |
- on 960523,noted Discrepancy in Cable Length Modeled in Existing Degraded Voltage Calculations.Caused by Design Analysis Deficiency.Performed Design Changes to Correct Voltage Problems
| 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) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-010-02, :on 960611,discovered Installed Gallery Steel Configuration Lacked Required Cross Bracing.Caused by Deficiency in Original Design Configuration Control Process. Installed Gallery Cross Bracing |
- on 960611,discovered Installed Gallery Steel Configuration Lacked Required Cross Bracing.Caused by Deficiency in Original Design Configuration Control Process. Installed Gallery Cross Bracing
| 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | | 05000254/LER-1996-011, Forwards LER 96-011-00.Circuit Mods & Procedure Changes Will Be Implemented Prior to Startup & Review of Sample of Assumptions from Safe Shutdown Repts & Calculations Investigated | Forwards LER 96-011-00.Circuit Mods & Procedure Changes Will Be Implemented Prior to Startup & Review of Sample of Assumptions from Safe Shutdown Repts & Calculations Investigated | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000254/LER-1996-011-02, :on 960708,determined Postulated Fire Could Have Caused Disabling Damage to Selected Motor Operated Valves.Caused by Inadequate Design Analysis Review.Movs Analyzed for Susceptibility to Single Failure |
- on 960708,determined Postulated Fire Could Have Caused Disabling Damage to Selected Motor Operated Valves.Caused by Inadequate Design Analysis Review.Movs Analyzed for Susceptibility to Single Failure
| | | 05000254/LER-1996-012-02, :on 960620,diesel Fuel Oil Transfer Piping Noted in Unanalysed Condition Due to an Incomplete Safety Classification Upgrade.Minor Mod Has Been Completed Which Removes Autofill Capability for Fire Pump Day Tanks |
- on 960620,diesel Fuel Oil Transfer Piping Noted in Unanalysed Condition Due to an Incomplete Safety Classification Upgrade.Minor Mod Has Been Completed Which Removes Autofill Capability for Fire Pump Day Tanks
| | | 05000254/LER-1996-012, Forwards LER 96-012-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items within Component Classification Program & Ensure Resolution of Items.Plan Will Be Completed by 970301 | Forwards LER 96-012-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items within Component Classification Program & Ensure Resolution of Items.Plan Will Be Completed by 970301 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1996-013-01, :on 960808,zebra Mussels Were Discovered on Fire Pump Suction Strainers.Caused by Inadequate Insp Frequency of Fire Pump Suction Strainers.Divers Removed & Cleaned Zebra Mussels from Fire Pump Suction Strainers |
- on 960808,zebra Mussels Were Discovered on Fire Pump Suction Strainers.Caused by Inadequate Insp Frequency of Fire Pump Suction Strainers.Divers Removed & Cleaned Zebra Mussels from Fire Pump Suction Strainers
| 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)(B) | | 05000254/LER-1996-013, Forwards LER 96-013,Rev 0 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed | Forwards LER 96-013,Rev 0 IAW Requirements of 10CFR50.73(a)(2)(i)(B).Commitments Made by Ltr,Listed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1996-014, Forwards LER 96-014-00.All Personnel Will Be Briefed in Event by 961215,reinforcing Expectations to Initiate Procedure Changes When Needed | Forwards LER 96-014-00.All Personnel Will Be Briefed in Event by 961215,reinforcing Expectations to Initiate Procedure Changes When Needed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1996-014-03, :on 960927,electrical Distribution Weekly Surveillance Did Not Document Voltage Verification Due to an Inadequate Procedure.Qcos 0005-06 Has Been Revised to Ensure Verification of Proper Voltages |
- on 960927,electrical Distribution Weekly Surveillance Did Not Document Voltage Verification Due to an Inadequate Procedure.Qcos 0005-06 Has Been Revised to Ensure Verification of Proper Voltages
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-015-01, :on 960816,HPCI Sys Jet Impingement Support Baseplate/Concrete Expansion Anchors Were Improperly Installed,Due to Ineffective Work Practices & QA Program. Review Will Be Completed |
- on 960816,HPCI Sys Jet Impingement Support Baseplate/Concrete Expansion Anchors Were Improperly Installed,Due to Ineffective Work Practices & QA Program. Review Will Be Completed
| 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) | | 05000254/LER-1996-015, Forwards LER 96-015-00.Commits to Completion Review of All Pipe Whip & Vibration Restraint Configuations by 961231 | Forwards LER 96-015-00.Commits to Completion Review of All Pipe Whip & Vibration Restraint Configuations by 961231 | 10 CFR 50.73(a)(2)(1) | | 05000254/LER-1996-016-01, :on 960823,secondary Containment Would Not Have Satisfied All UFSAR Requirements,Due to Siding Explosion Bolts Which Were Damaged by Either High Winds or Ineffective Work Pratices.Damaged Bolts Replaced |
- on 960823,secondary Containment Would Not Have Satisfied All UFSAR Requirements,Due to Siding Explosion Bolts Which Were Damaged by Either High Winds or Ineffective Work Pratices.Damaged Bolts Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-017, Forwards LER 96-017-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items | Forwards LER 96-017-00,for Quad Cities Nuclear Power Station.Review Plan Will Be Prepared to Identify Open Items | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000254/LER-1996-017-01, :on 960825,manual Scram Taken During Reactor Startup When Reactor Water Level Increased Following Unplanned Opening of All Main Turbine Bypass Valves Occurred,Due to Inadequate Procedures.Procedures Revised |
- on 960825,manual Scram Taken During Reactor Startup When Reactor Water Level Increased Following Unplanned Opening of All Main Turbine Bypass Valves Occurred,Due to Inadequate Procedures.Procedures 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) | | 05000254/LER-1996-018, Forwards Supplemental Info Re LER 96-018-00,correcting Editorial Error | Forwards Supplemental Info Re LER 96-018-00,correcting Editorial Error | | | 05000254/LER-1996-018-01, :on 960903,TS Surveillance Requirements Were Misinterpreted Due to Conservative Misunderstanding of Requirement.Memo Was Written to Explain Which Min TS Surveillances Must Be Performed Re Mode Switch |
- on 960903,TS Surveillance Requirements Were Misinterpreted Due to Conservative Misunderstanding of Requirement.Memo Was Written to Explain Which Min TS Surveillances Must Be Performed Re Mode Switch
| 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) | | 05000254/LER-1996-019, Forwards LER 96-019 IAW Requirements of 10CFR50.73(a)(2)(ii)(B) & Discusses Listed Commitments | Forwards LER 96-019 IAW Requirements of 10CFR50.73(a)(2)(ii)(B) & Discusses Listed Commitments | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000254/LER-1996-019-01, :on 960904,main Steam Line Radiation Monitor Functional Test Was Not Performed within Frequency Established for TS When in Refueling Mode Due to Incomplete Documentation of TS Interpretation.Qcap 2300-11 Was Changed |
- on 960904,main Steam Line Radiation Monitor Functional Test Was Not Performed within Frequency Established for TS When in Refueling Mode Due to Incomplete Documentation of TS Interpretation.Qcap 2300-11 Was Changed
| 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-020, Forwards LER 96-020-00.Commitments Included in LER & Submitted | Forwards LER 96-020-00.Commitments Included in LER & Submitted | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1996-020-01, :on 960907,CR Emergency Filtration Sys Declared Inoperable.Caused by Operator Knowledge Weakness.Operators Declared CR Emergency Filtration Sys Inoperable & Entered 14-day LCO |
- on 960907,CR Emergency Filtration Sys Declared Inoperable.Caused by Operator Knowledge Weakness.Operators Declared CR Emergency Filtration Sys Inoperable & Entered 14-day LCO
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000254/LER-1996-021-01, :on 961011,B CR HVAC Sys Was Declared Inoperable Due to Crankcase Heater Power Supply Design Deficiency.Design Change Notice 9600380 Issued,Which Replaced Crankcase Heater W/Safety Related Heater |
- on 961011,B CR HVAC Sys Was Declared Inoperable Due to Crankcase Heater Power Supply Design Deficiency.Design Change Notice 9600380 Issued,Which Replaced Crankcase Heater W/Safety Related Heater
| | | 05000254/LER-1996-021, Forwards LER 96-021-00,for Quad Cities Nuclear Power Station.No Commitments Being Made | Forwards LER 96-021-00,for Quad Cities Nuclear Power Station.No Commitments Being Made | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000254/LER-1996-022-01, Extends Commitment Date for Completing Rev to Plant CR Dose Analysis of Record,Per LER 96-022-01 | Extends Commitment Date for Completing Rev to Plant CR Dose Analysis of Record,Per LER 96-022-01 | | | 05000254/LER-1996-023-01, :on 961124,CR Emergency Filtration Sys Failed to Maintain Required Airflow Due to Cognitive Personnel Error.Instrument Loop for Gauge Fi 1/2-5795-307 Calibr |
- on 961124,CR Emergency Filtration Sys Failed to Maintain Required Airflow Due to Cognitive Personnel Error.Instrument Loop for Gauge Fi 1/2-5795-307 Calibr
| | | 05000254/LER-1996-023, Provides Commitments Re LER 96-023.Predefined Model Work Request Which Initiates Perodic Maint Procedure Initiated | Provides Commitments Re LER 96-023.Predefined Model Work Request Which Initiates Perodic Maint Procedure Initiated | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000254/LER-1996-025, Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values | Forwards LER 96-025-00 Re Operability Calculations Performed on ECCS Suction Strainers W/Incorrect Head Loss Values | | | 05000254/LER-1996-025-01, :on 961220,discovered Original Value for Strainers Head Loss Incorrect.Cause Could Not Be Determined. Training Provided for Operators to Recognize Pump Cavitation During Design Basis Accidents |
- on 961220,discovered Original Value for Strainers Head Loss Incorrect.Cause Could Not Be Determined. Training Provided for Operators to Recognize Pump Cavitation During Design Basis Accidents
| 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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