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LICENSEE EVENT REPORT (LER)
Form Rsv. 2.0 Ficuity Name (2) doc.et Number (2)
Page (3)
Quad Cities Unit one 0l5l0l0l0l2l5l4 1 l of l 0 l 4 Title (4) i Control Roorn Emergency Filtration System inoperable due to operator knowledge weakness.
Event Date (5)
LER Number (6)
Report Date (7)
Other Facihties involvmi (8)
Month Day Year Year Sequential Revision Month Day Year Facility Docket Numberts)
Number Number Names Ol5l0l0l0l2l6l5 0l9 0l7 9l6 9l6 0l2l0 0l0 1l0 0
7 9
6 0l5l0l0l0]
l l
4 OPERATING THIS REPORT IS SUBMFITED PU LSUANT TO TIE REQU REh' ENTS OF 10CFR MODE (9)
(Check one or more of the following) (11) 4 1
20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b) j POWER 20.405(a)(1)(i) 50.36(c)(1)
T50.73(a)(2)(v) 73.7i(c)
LEVEL 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii)
Other (Specify (10) 0 l2l 3
20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) in Abstract i
20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) below and in 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
Text) d LICENSEE CON TACT FOR THIS LER (12)
NAME TELEPHONE NUMBER AREA CODE Charlas Peterson, Regulatory Affairs Manager, ext. 3602 3
0l9 6l5l4l-l2l2l4l1 j
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPON ENT MANUFACTU RER R
LE
CAUSE
SYSTEM COMPONENT MANUFACTURER LE a
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I SUPPLEMENTAL REPORT EXPECTED (14)
Expected Monih Day Yeas Submmion lYES (If yes. complete EXPECTED SUBMISSION DATE)
'"Y"]NO Date (15) l l
l AB5 TRACT (lanut la 1400 spacca, i.e., approumately fiticen umgle-space typewnnen haca) (16)
ABSTRACT:
On 9/7/96 at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />, Unit One was in Power Operation Mode at 23% power and Unit Two l
was in Power Operation Mode at 85% power. The Control Room ventilation system was in the i
isolated recirculation mode with the Toxic Gas Analyzer (TGA) de-energized. The operators were unable to start the Air Filtration Unit (AFU) booster fans during the performance of l
the monthly surveillance. When the operators were unable to determine the cause they declared the Control Room Emergency Filtration System inoperable, entered a 14 day 1
Limiting Condition for Operation (LCO), and made an Emergency Notification System (ENS) call at 0556 hours0.00644 days <br />0.154 hours <br />9.193122e-4 weeks <br />2.11558e-4 months <br />.
l The root cause of this event was operator knowledge weakness.
When the AFU booster fans failed to start, the operators failed to recognize the relationship between the AFU l
booster fans and the toxic gas analyzer.
Corrective actions include incorporating this event in the operator required reading, including this LER in Modifications and Lessons j
Learned training, and changing the surveillance procedure.
The safety significance of this event is minimal because in the event of a Loss of Coolant Accident (LOCA), the ventilation system would have remained in recirculation for a sufficient time to identify and correct the problem.
4 LER254\\M020.WPF 9610160182 961007 PDR ADOCK 05000254 g
PDR
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i-LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Fonn Rev. 2.0 j
FACIprY NAbtE (1)
DOurt NUMBER (2)
LER NUMBER (6)
PAGE (3)
Year Sequential Revision
' Nuniber Nuadier Quad Cities Unit One 0l5 0l0l0l2l5l4 9l6 0l2l0 0l0 2 lOFl 0 l 4
]
TEXT Energy Ir.d.;ry law.Gcation System (EIIS) codes are ik.6;md in the text as [XX]
4 3
PLANT AND SYSTEM IDENTIFICATION
General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
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j EVENT IDENTIFICATION: Control Room Emergency Filtration Systems inoperable due to operator knowledge weakness.
i L
A.
CONDITIONS PRIOR TO EVENT
i Event Date: September 7, 1996 Event Time: 0530 Unit: One j
Reactor Mode:
1 Mode Name:
Power Operation Power Level:
23 i
Unit: Two Reactor Mode:
1 Mode Name:. Power Operation Power Level:
85 1
j This report was initiated by Licensee Event Report LER254\\96-020.
Power Operation (1) - Mode switch in the RUN position with average reactor coolant-temperature at any temperature.
B.
DESCRIPTION OF EVENT
On 9/6/96 Q0S 5750-04, " Control Room Ventilation Toxic Gas Analyzer Inoperable Outage f
Report" was initiated to perform preventive maintenance on the Control Room Toxic Gas Analyzer [45]. Step 7 of QOS 5750-04 states in part, "If desired,-due to analyzer being in the tripped condition, place the toxic gas analyzer in the untripped condition by lifting wire...".
This step' allows the Air Filtration Unit (AFU) [VI]
to be run with the Toxic Gas Analyzer deenergized.
The Operations entered "NA" for this step as the operators did not need to operate the AFU. At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> the Toxic i
Gas Analyzer was de-energized to perform the prevantive maintenance.
On o 7/96 at approximately 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> operators were preparing to perform QCOS 5750-02, " Control Room Emergency Filtration System Monthly Test". Step H.2 of this
[
procedure states to verify the toxic gas analyzer system is in service or initiate l
the QOS 5750-04 Outage Report. The Unit Supervisor verified that QOS 5750-04 had already been initiated but did not review the existing outage report as this was not -
considered necessary to complete step H.2.
Outage Reports do not normally contain conditional steps required for a surveillance procedure.
1 I
At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> the operator attempted to perform step H.8 of QCOS 5750-02 to start the AFU. At this time the "A"
and "B" Booster fans could not be started. The Toxic Gas 4
Analyzer was still deenergized under Outage Report QOS 5750-04 which prevented the I
Booster fans from starting.
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k IIR254\\96\\020,WPF
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LICENSEE EVENT REPORT (LER) *1XT COfGINUATION Form Rry. 2.0 F.ACIIJTY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (0)
PAGE (3)
Year Sequential Revision Number Number Qual Cities Unit Chie 0l5l0l0lol2l5l4 9l6 ol2l0 ol0 3 lOFl o j 4 TEXT Energy industry identification System (EIIS) codes are identif,ed in the text as (XX]
The Operators could not determine the reason why the booster fans would not start and declared the AFU inoperable and entered the 14 day Limiting Condition for Operation (LCO) in accordance with Technical Specification 3.8.H.1.a.
A 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Emergency Notification System (ENS) phone call was made at 0556 hours0.00644 days <br />0.154 hours <br />9.193122e-4 weeks <br />2.11558e-4 months <br />.
I C.
APPARENT CAUSE OF EVENT:
The root cause of this event was operator knowledge weakness.
When the AFU booster fans failed to start, the operators failed to recognize the relationship between the AFU booster fans and the toxic gas analyzer.
The contributing cause of this event is inadequate procedures. The procedural direction necessary to operate the AFU with an inoperable toxic gas analyzer was contained in QOS 5750-04, step 7.
However, QCOS 5750-02 did not contain a specific reference to tha applicable step of Q0S 5750-04 nor did it provide any specific information as to the intent of the outage report. As a result, the operators did not identify the need to lift the appropriate lead to bypass the AFU interlock.
D.
SAFETY ANALYSIS OF EVENT:
The safety significance of this event is considered minimal. The AFU is a manually initiated system and the steps to initiate the AFU with the toxic gas analyzer inoperable were included in QOS 5750-04. In a non-accident condition, or in a Loss Of Offsite Power (LOOP), the inability to start the AFU booster fans is insignificant, as no radioactive particles or vapors requiring filtration would be present. In the condition of a concurrent LOCA and LOOP, the toxic gas analyzer would be bypassed allowing the booster fa~ns to start. Therefore, the only condition of concern for the inability to start the AFU booster fans is a LOCA condition.
In accordance with Updated Final Safety Analysis Report (UFSAR) Table 15.6-7,Section III, the Control Room intake will immediately isolate on a loss of Coolant Accident (LOCA).
This will act to minimize the intake of outside air and potential contamination into the Control Room. The AFU start (manual start) is assumed to be 110 minutes following the LOCA.
It is reasonable to assume in the event of a LOCA continuous troubleshooting would have commenced and that the system would have been able to be started within the 110 minutes.
LER254\\M020.WPF
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev. 2.0 EACILTTY NAME (1)
DCrKET NUMBER (2)
LER NUMBER (6)
PAGE (3) i 1
Year Sequential Revision Nuahr Number Quad Cities Unit one 0l5 0l0l0l2l5l4 9l6 0l2l0 0l0 4 lOFl 0 l 4 TEXT Energy Industry identification System (Ells) codes are identif,ed in the text as [XX]
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E.
CORRECTIVE ACTIONS
Corrective Actions ComDleted 4
1 l-1.
The Operators declared the Control Room Emergency Filtration System inoperable and entered the.14-day LCO.
2.
This event has been incorporated in' operator required reading.
1 Corrective Actions to be Completed 1.
A description of this event will be presented to Licensed Operations personnel in retraining by 01/31/97. (Training - NTS#2541809602001) i 2.
QC05 5750-02, " Control Room Emergency Filtration System Monthly Test" will be j
revised by 10/27/96. (Operations - NTS#2541809602002) i
)
i F.
PREVIOUS OCCURRENCES
- - A search conducted for LER's over the last two years, which involved operator
]
knowledge weakness, identified the following previous events:
254\\96-006 Technical Specification 3.0.A was incorrectly invoked, due to procedural and operator knowledge deficiencies on technical specification requirements, when primary to secondary containment j
flowpaths were established during Local Leak Rate testing.
254;96-017 Manual scram taken during reactor startup when reactor water level increased following unplanned opening of all main turbine bypass valves due to an inadequate procedure.
G.
CONPONENT FAILURE DATA:
Not applicable.
LER254\\96W20.WPF
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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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