05000255/LER-1996-006-01, Forwards LER 96-006-01.Determined Limits of Design Analysis Had Not Been Exceeded.Info Reclassified as Voluntary Rept

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Forwards LER 96-006-01.Determined Limits of Design Analysis Had Not Been Exceeded.Info Reclassified as Voluntary Rept
Person / Time
ML18065A858
Site:	Palisades
Issue date:	08/02/1996
From:	Smedley R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18065A859	List: 05000255/LER-1996-006, On 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit 05000255/LER-1996-006-01, Forwards LER 96-006-01.Determined Limits of Design Analysis Had Not Been Exceeded.Info Reclassified as Voluntary Rept
References
NUDOCS 9608140237
Download: ML18065A858 (2)
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LER-1996-006, Forwards LER 96-006-01.Determined Limits of Design Analysis Had Not Been Exceeded.Info Reclassified as Voluntary Rept

Event date:
Report date:
2551996006R01 - NRC Website
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consumel'S Power POWERINli lllllCHlliAN'S PROGRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 August2, 1996 U S Nuclear Regulatory Commission-Document Control Desk

Washington,* DC 20555

.. DOCKET 50~255 - LICENSE DPR~20 - PALISADES PLANT

LICENSE EVENT REPORT 96-006 REACTOR POWER LICENSE LIMIT -

VOLUNTARY SUPPLEMENTAL REPORT.

. A supplement to Licensee Event Report (LER)96-006 is attached. This event had**

been reported in accord~ncewith the Palisades Facility Operating License DPR-20, Section 2.F as a noncompliance with Section 2.C.(1) of the license. As a result of the initial evaluation, it had been determined that the li!'Dits of our design analyses could:

have been violated.* "fherefore this event had also been reported in accordance with 10 CFR Part 50. 72(b)(1 )(ii)(B).

. * * *.. Th~ invl3stigatioh which followed the original LER 96-00G resulted in the. determination

~hat the reactor power limit permitted by Section 2.C.(1) of the Palisades Facility Operating License DPR-20 had not been exceeded. It also resulted.in *the.

determination that the I Im its of the design analysis also had not been exceeded.

Therefore, this information is being reclassified as a voluntary r~port.

9608140237 960802 PDR ADOCK 05000255 S

PDR A GMS' ENERGY COMPANY

SUMMARY OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.

The commitment made in the March 11, 1996 submittal has now been completed.

Richard W Smedley Manager, Licensing CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades 2

.Ii

Licensee Event Report

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		Reporting criterion
05000255/LER-1996-001, :on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS	on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000255/LER-1996-002-01, :on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Root Cause of Failure Under Investigation.Const Cable Installation Spec Will Be Revised & Testing of Faulted Cable Will Be Performed	on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Root Cause of Failure Under Investigation.Const Cable Installation Spec Will Be Revised & Testing of Faulted Cable Will Be Performed	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
05000255/LER-1996-003, :on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board	on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board	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)
05000255/LER-1996-004, :on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts	on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts
05000255/LER-1996-005-01, Forwards LER 96-005-01 Re DC Panels Breaker/Fuse Coordinate Issue.Ltr Contains No New Commitments	Forwards LER 96-005-01 Re DC Panels Breaker/Fuse Coordinate Issue.Ltr Contains No New Commitments
05000255/LER-1996-005, :on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced	on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii)
05000255/LER-1996-006-01, Forwards LER 96-006-01.Determined Limits of Design Analysis Had Not Been Exceeded.Info Reclassified as Voluntary Rept	Forwards LER 96-006-01.Determined Limits of Design Analysis Had Not Been Exceeded.Info Reclassified as Voluntary Rept
05000255/LER-1996-006, On 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit	On 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 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)(1)
05000255/LER-1996-007, :on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting Modified	on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting Modified	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1)
05000255/LER-1996-008, :on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test Procedures	on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test Procedures	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 50.73(a)(2)(1)
05000255/LER-1996-009, :on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis Document	on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis Document	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x)
05000255/LER-1996-010, :on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected	on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1)
05000255/LER-1996-011, :on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments	on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000255/LER-1996-012, :on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling Completed	on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling Completed	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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000255/LER-1996-013, :on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested	on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000255/LER-1996-014, :on 961124,Class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Inadequate Procedure.Splices Were Either Confirmed to Be Acceptable by Field Insp or Were Replaced W/Correctly Installed Splices	on 961124,Class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Inadequate Procedure.Splices Were Either Confirmed to Be Acceptable by Field Insp or Were Replaced W/Correctly Installed Splices	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)(i) 10 CFR 50.73(a)(2)(iii)

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