: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| ML20129H556 |
| Person / Time |
|---|
| Site: |
Quad Cities  |
|---|
| Issue date: |
10/24/1996 |
|---|
| From: |
Peterson C COMMONWEALTH EDISON CO. |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20129H553 |
List: |
|---|
| References |
|---|
| LER-96-014-03, LER-96-14-3, NUDOCS 9611010200 |
| Download: ML20129H556 (4) |
|
text
.
LICENSEE EVENT REPORT (LER)
Form Rsv. 2.0 Facdary N;me (1)
Dockes Number Q)
Page (3)
Quad Cities Unit One 0l5l0l0l0l2l5l4 1 l of l 0 l 4 Tide (4)
Electrical distribution weekly surveillance did not document voltage verification in accordance with Technical Specification 4.9.E. due to an inadequate procedure.
Event Date (5)
LER Numt.er (6)
Report Date (7)
Other Facdities involved (8)
Month Day Year Year Sequential Revision Month Day Year Facility Docket Number (s)
Number Number Names 0l5l0l0l0l2l6l5 0l9 2l7 9l6 9l6 0l1l4 0l0 1l0 2l4 9l6 0l5l0l0l0l l
l OPERATING THis REPORT !$ $UBM TIED PUR5UANT TO THE REQUIREMENTS OF 10CFR MODE (9)
(Check one or more of the following) (11) 1 20.402(b) 20.405(c) 50.73(a)(2)0v) 73.71(b)
POWER 20.405(s)(I)G) 50.36(c)(I)
- - 50.73(a)G)(v) 73.7I(c)
LEVEL 20.405(a)(1)0i)
- - 50.36(c)(2) 50.73(a)(2)(vii)
Other (Specify (10) 1 l0l 0
- - 20.405(a)(1)0ii)
T50.73(a)(2)0) 50.73(a)(2)(viii)(A) in Abstract 20.405(a)(1)0v)
- - 50.73(a)(2)0i)
- - 50.73(a)(2)(viii)(B) below and in 20.405(a)(1)(v)
- - 50.73(a)(2)0ii) 50.73(a)(2)(x)
Tert)
LICENSEE CON TACT FOR THIS LER (la)
NAME TELEPHONE NUMBER AREA CODE Charles Peterson. Regulatory Affairs Manager, ext. 3602 3l0l9 6l5l4l-l2l2l4l1 COMPLETE ONE LINE FOR EACH COMPONENT F AILURE Dl3CRIBED IN THIS REM >RT (13)
CAU5E 5Y5 TEM COMPONENT MANUFACTURLR REPORTABLE CAU5E 5YSTEM COMPONENT MANUFACnJRER REPORTABM TO NPRDS TO NPRDS I
I I
I I
l l
1 I
I I
I I
I I
I I
I I
i l
l I
I I
I SUP *EMENTAL REPORT EXPECILD 04)
Expected Month Day Year Submunen lYES Of yes, complete EXPECTED SUBMIS$10N DATE) yo Date 05) l l
l AB5 TRACT tlamn to 3400 spaces, s_e.. appronunately fdteen omgle-specs typewnnen imes) 0 6)
ABSTRACT:
On 9/27/96 at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, Unit I and Unit 2 were in Power Operation mode at 100 percent power when a Technical Specification (TS) required surveillance became overdue for both Units. QCOS 0005-06, Weekly Electrical Distribution Breaker and Voltage Verification, is required to be performed weekly in accordance with TS 4.9.E and had last been performed on 9/19/96 for both Units. On 9/26/96, Nuclear Station Operators performed QCOS 0005-06 for both Units, but the surveillance procedure did not have operators document verification of proper voltages in accordance with TS 4.9.E, a requirement implemented with the Upgraded TS on 9/23/96. On 10/02/96 at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, a Unit Supervisor reviewing the 9/26/96 copies of QCOS 0005-06 identified there was no documentation that proper voltages had been verified. A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Limiting Condition for Operation (LCO) for completion of the surveillance was entered for both Units in accordance with TS 4.0.C.
A revision to QCOS 0005-06 was expedited, and on 10/03/96 at 1923 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.317015e-4 months <br />, the revised QCOS 0005-06 was successfully performed and TS 4.0.C LC0 was exited for both Units.
The root cause of this event is an inadequate procedure.
Corrective actions include procedure revision, counselling of personnel involved with the review and approval of the procedure, and briefing all Operations personnel on the event.
The safety significance of this event is minimal as the affected busses and motor control centers were verified as energized and an abnormal voltage would have been identified by operators during rounds or through Control Room alarms.
9611010200 961024 PDR-ADOCK 05000254 S
PDR
LICENSEE EVENT REPCbT (LER) TEXT CONTINUATION Form Rev. 2.0 FACILTTY N AME (1)
DOCKET NUMBER C)
LER NUMBER (6)
PAGE (3)
=
Year sequential Revimon Number Number Quad Cities Unit one 0l5lOj*l0l2 5l4 9l6 0l1l4 0l0 2 lOFl 0 l 4 TEXT Energy Industry Ident 6 cation System (Ells) codes are ident:6e in the text as (XX)
PLANT AND SYSTEM IDENTIFICATION
General Electric - Boiling Water Reactor - 2511 MWt rated core thermal power.
EVENT IDENTIFICATION:
Electrical distribution weekly surveillance did not document voltage verification in accorJance with Technical Specification 4.9.E due to an inadequate procedure.
A.
CONDITIONS PRIOR TO EVENT
Unit: One Event Date:
September 27, 1996 Event Time: 0000 Reactor Mode:
1 Mode Name:
POWER OPERATION Power Level:
100%
Unit: Two Event Date:
September 27, 1996 Event Time: 0000 Reactor Mode:
1 Mode Name:
POWER OPERATION Power Level:
100%
This report was initiated by Licensee Event Report LER254\\96-014.
Power Operation (1) - Mode switch in the RUN position with average reactor coolant temperature at any temperature.
B.
DESCRIPTION OF EVENT
On 4/25/96, a new procedure, QCOS 0005-06, Weekly Electrical Distribution Breaker and Voltage Verification was developed by a Senior Reactor Operator in preparation for implementing the Upgraded Technical Specifications (TSUP).
This procedure was reviewed for technical accuracy by a Shift Engineer and the Operations TSUP Coordinator prior to approval by the Administrative Operating Engineer. On 9/17/96, revision 0 of QCOS 0005-06 was issued prior to implementing the TS. The purpose of this procedure was in part "to verify the onsite distribution system [EB, ED, EJ) is in the correct breaker [BKR] alignment with proper voltages on essential busses [BU]
and motor control centers [MCC], as required by Technical Specifications (TS)." A typical step from revision 0 of this surveillance was to " verify Bus 13-1 (23-1) energized from Bus 13 (23)" without specifying adequate voltage to be checked. TS section 4.9.E states: "Each of the required power distribution system divisions shall be determined energized at least once per 7 days by verifying correct breaker alignment and voltage on the busses /MCCs/ panels."
LER254\\96\\014. WPF
. _.. - - - - - ~. -
l LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rav. 2.0 FACILITY NAME 0)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3) s Year Sequential Revision
=
Number Number j
Quad Cities Unit One ol5lo'olol2l5l4 9l6 ol1l4 olo 3 lOFl o l 4 i
TEXT Energy Industry identification System (Ells) codes are identifie< in the text as [XX)
On 9/19/96, QCOS 0005-06 was being performed for the first time on both Units. A j
Nuclear Station Operator (NS0) contacted the Operations TS Coordinator and questioned if the surveillance adequately addressed TSUP 4.9.E if the proper
~
voltages were not verified and documented. The Operations TSUP Coordinator i
recommended that the NSO could verify that there were no undervoltage alarms present on the 901-8 and 902-8 Control Room electrical distribution panels and document the verification in the comments section of QC05 0005-06 if he was concerned with the i
adequacy of the procedure. The Operations TSUP Coordinator stated he would ensure that the procedure concern would be resolved prior to performing the surveillances again (the following week). QCOS 0005-06 was completed for both Units and included i
comments that no alarms were present. The Operations TSUP Coordinator failed to follow through to ensure the procedure concern was resolved as requested.
On 9/23/96, the TSUP was implemented. On 9/26/96, QCOS 0005-06 was performed again for both Units. The NS0's verified the associated busses were energized in accordance with the procedure but no one recognized that the procedure did not meet i
the TS 4.9.E requirement to document the verification of proper voltage. The j
surveillances were completed and no comments were documented.
On 10/02/96 at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, an operator was reviewing documentation for the 9/26/96 i
performances of QCOS 0005-06 for both Units and noted there was no documentation of proper voltage verification as required by TS 4.9.E.
The Unit Supervisor verified no undervoltage annunciator alarms present on the 901-8 and 902-8 Control Room electrical distribution panels. A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Limiting Condition for Operation (LCO) for completion of the surveillance was entered effective at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> in accordance with TS 4.0.C.
The Operations TSUP Coordinator was contacted and a revision to QCOS 0005-06 was expedited to ensure the verification of proper voltages was documented.
On 10/03/96 at 1923 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.317015e-4 months <br />, the revised QCOS 0005-06 was successfully performed and TS 4.0.C LC0 was exited for both Units.
C.
APPARENT CAUSE OF EVENT:
i The root cause of this event was the inadequate review and approval of QCOS 0005-06 which did not recognize that TS 4.9.E required verifications were not documented by l
the procedure. The individuals involved with reviewing and approving the procedure considered the term " verify energized" to encompass and fully satisfy the Technical Specification. All other new or modified surveillances applicable to Power 2
i Operation have been performed and no other TSUP surveillance problems have been
]
identified.
A contributing cause of this event was ineffective tracking of an identified i
problem. The procedural discrepancy was recognized and addressed on 9/19/96 prior to the implementation of the TSUP requirement on 9/23/96, but the necessary changes were not tracked and completed as the Operations TSUP Coordinator perceived the change as a clarification rather than a correction.
i LER254 96\\014. WPF
i LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rav. 2.0 FACILrrY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
Year sequential Revision Number Number Qund Cities Unit One 0l5l0l0l0l2l5l4 9l6 0l1l4 0l0 4 lOFl 0 l 4 TEXT Energy ladustry identi6 cation System (Ells) codes are ident:6ed in the text as (XX)
D.
SAFETY ANALYSIS OF EVENT:
The safety significance of this event is minimal. The affected busses and motor control centers were verified as energized on 9/26/96 and although the proper voltages verifications were not documented, an abnormal voltage would have been identified by operators during rounds or through Control Room alarms.
E.
CORRECTIVE ACTIONS
Corrective Actions Completed:
1.
QCOS 0005-06 has been revised to ensure the verification of proper voltages is documented.
2.
The affected Operations personnel were counselled on the failure to identify the procedural inadequacy during the review for procedure approval.
Corrective Actions To Be Completed:
1.
All Operations personnel will be briefed on this event by 12/15/96, reinforcing the expectation to initiate procedure changes when needed.
)
(NTS# 2541809601401 - Operations).
F.
PREVIOUS EVENTS:
A search for LERs in the last 2 years involving missed Technical Specification surveillances revealed the following events 254/94-14, Fire system surveillance went past their critical due date without the j
systems being declared inoperable and compensatory actions put in place due to inadequate training and written communication.
254/95-06, The RPS EPA relays had not been tested prior to the mode switch being moved to Refuel due to an in adequate written communication.
254/96-19, Main steam line radiation monitor functional test not performed within frequency established for Technical Specifications when in Refueling mode due to I
incomplete documentation of a Technical Specification interpretation.
6.
COMPONENT FAILURE DATA
Not applicable.
LER254\\%014. WPF i
|
|---|
|
|
| | | Reporting criterion |
|---|
| 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) |
|