| | | Reporting criterion |
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| 05000295/LER-1997-001-01, Forwards LER 97-001-01,which Clarifies Info on Root Cause,Safety Analysis & Event Description.Corrective Actions Updated to Show Status of Items | Forwards LER 97-001-01,which Clarifies Info on Root Cause,Safety Analysis & Event Description.Corrective Actions Updated to Show Status of Items | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000295/LER-1997-001, Forwards LER 97-001-00 Which Involved Discovery of Lack of Sump Cover Plate Holes Contrary to Plant Structural Drawing Details,Per 10CFR50.73(a)(2)(ii)(B) | Forwards LER 97-001-00 Which Involved Discovery of Lack of Sump Cover Plate Holes Contrary to Plant Structural Drawing Details,Per 10CFR50.73(a)(2)(ii)(B) | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
| 05000295/LER-1997-001-14, :on 970110,recirculation Sump Cover Plate Holes Were Not Installed at Original Construction.Caused by Construction Error.Holes Installed IAW Emergency Exempt Change Prepared Prior to Ramp Down |
- on 970110,recirculation Sump Cover Plate Holes Were Not Installed at Original Construction.Caused by Construction Error.Holes Installed IAW Emergency Exempt Change Prepared Prior to Ramp Down
| 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)(iv), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1)
10 CFR 50.73(e)(2) |
| 05000295/LER-1997-001-03, :on 970110,recirculation Sump Covers Were Not Installed at Original Construction.Cause Is Unknown & Impact on Plant Operation Is Unknown.Sump Cover Was Removed,Holes Were Drilled & Cover Replaced Prior to Expiration of LCO |
- on 970110,recirculation Sump Covers Were Not Installed at Original Construction.Cause Is Unknown & Impact on Plant Operation Is Unknown.Sump Cover Was Removed,Holes Were Drilled & Cover Replaced Prior to Expiration of LCO
| 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)
10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-001-11, :on 970902,Unit 2 Instrument Bus Perturbation Occurred.Caused by Insufficient Policy/Guidelines. Development of Policy for Proper Use of Protective Gear, Equipment & Tools |
- on 970902,Unit 2 Instrument Bus Perturbation Occurred.Caused by Insufficient Policy/Guidelines. Development of Policy for Proper Use of Protective Gear, Equipment & Tools
| 10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-001, Forwards LER 97-001-00 Per 10CFR50.73(a)(2)(iv) Which Requires Written Rept Using NRC Form 366, License Event Rept, within 90 Days of Discovery of Event.Attachment a Contains Commitments Associated W/Ltr | Forwards LER 97-001-00 Per 10CFR50.73(a)(2)(iv) Which Requires Written Rept Using NRC Form 366, License Event Rept, within 90 Days of Discovery of Event.Attachment a Contains Commitments Associated W/Ltr | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000295/LER-1997-002, Forwards LER 97-002-00.Commitments Made by Util Listed | Forwards LER 97-002-00.Commitments Made by Util Listed | 10 CFR 50.73(a)(2)(1) |
| 05000295/LER-1997-002-01, :on 970117,containment Isolation Valves Were Not Tested Prior to Leaving Cold Shutdown.Caused by Mgt Deficiencies in TS Implementation Process.Containment Isolation Valves Will Be Verified Tested Prior to Mode 4 |
- on 970117,containment Isolation Valves Were Not Tested Prior to Leaving Cold Shutdown.Caused by Mgt Deficiencies in TS Implementation Process.Containment Isolation Valves Will Be Verified Tested Prior to Mode 4
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-002-09, :on 971012,inadvertent Isolation of Svc Water Cooling to 2B DG During Sys Alignment,Occurred.Caused by Shift Mgt Not Ensuring All Operability Requirements Met. Valve 2MOV-SW0023 Opened to Restore Flow to 2B EDG |
- on 971012,inadvertent Isolation of Svc Water Cooling to 2B DG During Sys Alignment,Occurred.Caused by Shift Mgt Not Ensuring All Operability Requirements Met. Valve 2MOV-SW0023 Opened to Restore Flow to 2B EDG
| 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)
10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-002, Forwards LER 97-002-00,per 10CFR50.73(a)(2)(v)(B),which Requires 30 Day Written Rept.Commitments Associated W/Correspondence,Encl | Forwards LER 97-002-00,per 10CFR50.73(a)(2)(v)(B),which Requires 30 Day Written Rept.Commitments Associated W/Correspondence,Encl | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
| 05000295/LER-1997-003, :on 970117,determined That EDG Tests Completed in Previous Refueling Outages Failed to Meet TS Requirement. Caused by Programmatic Deficiencies.Corrected Deficient Procedures & Completed Tests on Operating Unit |
- on 970117,determined That EDG Tests Completed in Previous Refueling Outages Failed to Meet TS Requirement. Caused by Programmatic Deficiencies.Corrected Deficient Procedures & Completed Tests on Operating Unit
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-003, Forwards LER 97-003-00 Re Unit 2 RHR Sys Declared Inoperable,Per 10CFR50.73(a)(2)(v)(B) | Forwards LER 97-003-00 Re Unit 2 RHR Sys Declared Inoperable,Per 10CFR50.73(a)(2)(v)(B) | 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2) |
| 05000304/LER-1997-003-10, :on 971014,unit 2 RHR Sys Declared Inoperable. Caused by Oil Leak from Oil Bulb.Leak Coming from Oil Bulb on Ob CC Pump Stopped by Removing Bulb & Inspected |
- on 971014,unit 2 RHR Sys Declared Inoperable. Caused by Oil Leak from Oil Bulb.Leak Coming from Oil Bulb on Ob CC Pump Stopped by Removing Bulb & Inspected
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) |
| 05000304/LER-1997-004-08, :on 971015,small Bore Containment Penetration Line Inadequately Supported Since Plant Construction Was Noted.Cause Cannot Be determined.Non-destructive Exams Performed to Determine Condition & Integrity of Pipe |
- on 971015,small Bore Containment Penetration Line Inadequately Supported Since Plant Construction Was Noted.Cause Cannot Be determined.Non-destructive Exams Performed to Determine Condition & Integrity of Pipe
| 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) |
| 05000304/LER-1997-004, Forwards LER 97-004-00,per 10CFR50.73(a)(2)(i).Commitments Associated W/Correspondence,Encl | Forwards LER 97-004-00,per 10CFR50.73(a)(2)(i).Commitments Associated W/Correspondence,Encl | 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
| 05000295/LER-1997-004, Forwards LER 97-004-00 Re Failure to Start Pump in Required Time & Led to Declaring 1C Containment Spray Pump Inoperable | Forwards LER 97-004-00 Re Failure to Start Pump in Required Time & Led to Declaring 1C Containment Spray Pump Inoperable | |
| 05000295/LER-1997-004-04, :on 970221,identified Failure to Start Pump in Required Time & Led to Declaring 1C Containment Spray Inoperable.Caused by Clogged Fuel Filter & Defective components.1C Containment Spray Pump Fuel Drained & Flushed |
- on 970221,identified Failure to Start Pump in Required Time & Led to Declaring 1C Containment Spray Inoperable.Caused by Clogged Fuel Filter & Defective components.1C Containment Spray Pump Fuel Drained & Flushed
| 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)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1) |
| 05000295/LER-1997-004-01, :on 970221,reactor Was Shutdown,Per LCO 3.6.1 Due to One Inoperable Containment Spray pump.1C CS Pump Day Tank Was Drained,Flushed,Refilled w/biocide-added Fuel from Different Source |
- on 970221,reactor Was Shutdown,Per LCO 3.6.1 Due to One Inoperable Containment Spray pump.1C CS Pump Day Tank Was Drained,Flushed,Refilled w/biocide-added Fuel from Different Source
| 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
| 05000295/LER-1997-005, Forwards LER 97-005-00 IAW 10CFR50.73(a)(2)(i)(B).Actions Listed | Forwards LER 97-005-00 IAW 10CFR50.73(a)(2)(i)(B).Actions Listed | 10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-005, Forwards LER 97-005-00 Which Documents Event That Occurred at Zion Nuclear Power Station,Unit 2.Commitment Made within Ltr,Encl | Forwards LER 97-005-00 Which Documents Event That Occurred at Zion Nuclear Power Station,Unit 2.Commitment Made within Ltr,Encl | 10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-005-07, :on 971021,failed to Test 2A SI Pump Suction Valve in Prescribed Periodicity.Caused by Inadequate Program to Ensure That TS IST Requirements for Each Component Are Met.Ist Group Will Include Second Check in Review |
- on 971021,failed to Test 2A SI Pump Suction Valve in Prescribed Periodicity.Caused by Inadequate Program to Ensure That TS IST Requirements for Each Component Are Met.Ist Group Will Include Second Check in Review
| 10 CFR 50.73(a)(1), Submit an LER
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2) |
| 05000295/LER-1997-005-03, :on 970221,supplement to Unapproved Mode Change W/Ts Required Equipment Inoperable Were Noted.Caused by Inadequate Planning & Briefing.Both Units Have Been Placed in Cold Shutdown W/Rcs at Atmospheric Pressure |
- on 970221,supplement to Unapproved Mode Change W/Ts Required Equipment Inoperable Were Noted.Caused by Inadequate Planning & Briefing.Both Units Have Been Placed in Cold Shutdown W/Rcs at Atmospheric Pressure
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(viii)(B) |
| 05000304/LER-1997-006-07, :on 971028,informed of Potential to Exceed 10CFR50.46 ECCS Acceptance Criteria.Caused by Fuel Clad Gap re-opening & 17% Maximum Cladding Oxidation Limit.Performed Conservative Corrosion Calculations |
- on 971028,informed of Potential to Exceed 10CFR50.46 ECCS Acceptance Criteria.Caused by Fuel Clad Gap re-opening & 17% Maximum Cladding Oxidation Limit.Performed Conservative Corrosion Calculations
| 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)(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) |
| 05000304/LER-1997-006, Forwards LER 97-006-00 Per 10CFR50.73(a)92)(ii)(B) Which Requires 30 Day Written Rept When Any Event or Condition Occurs That Resulted in Condition of Nuclear Power Plant. Regulatory Commitments Encl | Forwards LER 97-006-00 Per 10CFR50.73(a)92)(ii)(B) Which Requires 30 Day Written Rept When Any Event or Condition Occurs That Resulted in Condition of Nuclear Power Plant. Regulatory Commitments Encl | 10 CFR 50.73(a)(2) |
| 05000295/LER-1997-006, :on 970222,Zion Station Exceeded Limiting Condition for Operation Due to Inadequate Procedure Controls.Standing Order to Require Review of TS During OOS Procedure Implementation,Was Issued |
- on 970222,Zion Station Exceeded Limiting Condition for Operation Due to Inadequate Procedure Controls.Standing Order to Require Review of TS During OOS Procedure Implementation,Was Issued
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-007-06, :on 971030,failure to Maintain Required Number of Svc Water Pumps Operable Was Identified.Caused by Failure of Mgt Personnel to Adhere to Requirements for Reviewers to Use Applicable Drawings.Procedure Rev to Provide Guidanc |
- on 971030,failure to Maintain Required Number of Svc Water Pumps Operable Was Identified.Caused by Failure of Mgt Personnel to Adhere to Requirements for Reviewers to Use Applicable Drawings.Procedure Rev to Provide Guidance
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1) |
| 05000295/LER-1997-007-02, :on 970311,operator Opened Local Sys Auxiliary Transformer Panel.Cause of Sys Auxiliary Transformer Trip Could Not Be Conclusively Determined.Unit 2 Sys Auxiliary Transformer Tested for Damage |
- on 970311,operator Opened Local Sys Auxiliary Transformer Panel.Cause of Sys Auxiliary Transformer Trip Could Not Be Conclusively Determined.Unit 2 Sys Auxiliary Transformer Tested for Damage
| 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 50.73(a)(2)
10 CFR 50.73(a)(2)(1)
10 CFR 50.73(a)(7)(ii) |
| 05000295/LER-1997-007, Forwards LER 97-007-00 Re Automatic Actuation of Esf. Submitted Table Identifies Actions Committed to by Util | Forwards LER 97-007-00 Re Automatic Actuation of Esf. Submitted Table Identifies Actions Committed to by Util | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000304/LER-1997-007, Forwards LER 97-007-00 Per 10CFR50.73(a)(2)(v)(B) Which Requires Written Rept for Any Event or Condition That Could Prevent Fulfillment of Safety Function of Structures or Sys Needed to Remove Residual Heat.W/Commitments Attach | Forwards LER 97-007-00 Per 10CFR50.73(a)(2)(v)(B) Which Requires Written Rept for Any Event or Condition That Could Prevent Fulfillment of Safety Function of Structures or Sys Needed to Remove Residual Heat.W/Commitments Attached | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
| 05000295/LER-1997-008, :on 970321,air Filters Containing Al Were Inadvertently Installed in Containment Due to Faulty Parts Selection Process.Hepa Filters Containing Al Will Be Removed or Replaced w/non-Al Containing Filters |
- on 970321,air Filters Containing Al Were Inadvertently Installed in Containment Due to Faulty Parts Selection Process.Hepa Filters Containing Al Will Be Removed or Replaced w/non-Al Containing Filters
| 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)(vii), Common Cause Inoperability
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)
10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-008-07, :on 971122,safety Related Snubber Not in Snubber Program & Subsequently Was Not Inspected Per Ts. Cause Unknown.Procedure TSS 15.6.48 Revised to Incorporate Unit 2 Snubber |
- on 971122,safety Related Snubber Not in Snubber Program & Subsequently Was Not Inspected Per Ts. Cause Unknown.Procedure TSS 15.6.48 Revised to Incorporate Unit 2 Snubber
| 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)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-008, Forwards LER 97-008-00 Per 10CFR50.73(a)(2)(i)(B),which Requires 30 Day Written Rept.Attachment a Provides Commitments Associated W/Correspondence | Forwards LER 97-008-00 Per 10CFR50.73(a)(2)(i)(B),which Requires 30 Day Written Rept.Attachment a Provides Commitments Associated W/Correspondence | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000295/LER-1997-009-01, :on 970114,1FCV-CS0002 Was Inoperable Between 970115 & 0208.Caused by Failure to Verify That Acceptance Criteria for Return to Service Was Met.Disciplined Unit Supervisor & Will Cover Event in Licensed Operator Training |
- on 970114,1FCV-CS0002 Was Inoperable Between 970115 & 0208.Caused by Failure to Verify That Acceptance Criteria for Return to Service Was Met.Disciplined Unit Supervisor & Will Cover Event in Licensed Operator Training
| 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 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(1) |
| 05000295/LER-1997-009, Forwards LER 97-009-00 IAW 10CFR50.73(A)(2)(i)(B) Which Requires Listed Corrective Actions | Forwards LER 97-009-00 IAW 10CFR50.73(A)(2)(i)(B) Which Requires Listed Corrective Actions | |
| 05000304/LER-1997-009-08, :on 971202,test Relay SIX1-AX Did Not Unlatch as Required During Restoration of PT 10-3.Caused by Failure to Follow Procedures.Rewired Test Relay SIX1-AX |
- on 971202,test Relay SIX1-AX Did Not Unlatch as Required During Restoration of PT 10-3.Caused by Failure to Follow Procedures.Rewired Test Relay SIX1-AX
| 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)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1) |
| 05000304/LER-1997-009, Forwards LER 97-009-00,re Event Which Occurred at Zion Nuclear Power Station,Unit 2.Commitments Made within Ltr Also Encl | Forwards LER 97-009-00,re Event Which Occurred at Zion Nuclear Power Station,Unit 2.Commitments Made within Ltr Also Encl | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000295/LER-1997-010, :on 960316,reactor Trip Due to Equipment Failure Occurred.Caused by New But Defective Pneumatic Vol Booster on Valve.Pneumatic Vol Booster for 1C Main FW Regulating Valve Replaced |
- on 960316,reactor Trip Due to Equipment Failure Occurred.Caused by New But Defective Pneumatic Vol Booster on Valve.Pneumatic Vol Booster for 1C Main FW Regulating Valve Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000295/LER-1997-010-01, :on 970404,radiation Area Surveys Were Missed. Caused by Inadequate TS Review.Nso,Unit Supervisor & Shift Engineer,Counseled |
- on 970404,radiation Area Surveys Were Missed. Caused by Inadequate TS Review.Nso,Unit Supervisor & Shift Engineer,Counseled
| 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)(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)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) |
| 05000295/LER-1997-012-02, :on 970423,determined That Test Criteria for H Recombiner Was Inappropriate.Caused by Low Std for for Documentation of Changes to Vendor Recommendations. Will Review Results of 1995 TS Compliance Self Assessment |
- on 970423,determined That Test Criteria for H Recombiner Was Inappropriate.Caused by Low Std for for Documentation of Changes to Vendor Recommendations. Will Review Results of 1995 TS Compliance Self Assessment
| 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 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(1) |
| 05000295/LER-1997-012, Forwards LER 97-012-00,which Documents 970423 Event That Occurred at Zion Generating Station.Commitments Made by Util,Listed | Forwards LER 97-012-00,which Documents 970423 Event That Occurred at Zion Generating Station.Commitments Made by Util,Listed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000295/LER-1997-013-02, :on 970412,VT-3 Insp Requirements of Relief Request CR-13 for Reactor Head Bolting Were Not Performed. Caused by Failure to Revise ISI Database After SER Received from Nrc.Procedure Revised |
- on 970412,VT-3 Insp Requirements of Relief Request CR-13 for Reactor Head Bolting Were Not Performed. Caused by Failure to Revise ISI Database After SER Received from Nrc.Procedure Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1) |
| 05000295/LER-1997-014-02, :on 970502,TS Surveillances on Radiation Monitors Were Missed Because Technical Interpretation That Kept 1(2)RT-PR15 Operable Was Inoperable.Revised Station Procedures |
- on 970502,TS Surveillances on Radiation Monitors Were Missed Because Technical Interpretation That Kept 1(2)RT-PR15 Operable Was Inoperable.Revised Station Procedures
| 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)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(1) |
| 05000295/LER-1997-015-01, :on 970724,Unit 1 EDGs & Unit 2 RHR Sys Was Declared Inoperable Which Resulted in Inadvertent ESF While Performing TS Related Surveillance.Caused by Unclear Expectations.Declared EDG Operable on 970729 |
- on 970724,Unit 1 EDGs & Unit 2 RHR Sys Was Declared Inoperable Which Resulted in Inadvertent ESF While Performing TS Related Surveillance.Caused by Unclear Expectations.Declared EDG Operable on 970729
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
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 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) |
| 05000295/LER-1997-015-02, :on 970724,Unit 1 EDGs & Unit 2 RHR Sys Were Declared Inoperable & Inadvertent Esg Actuation Was Noted While Performing TS Related Surveillances.Cause Is Under Investigation.Restored ESF Equipment |
- on 970724,Unit 1 EDGs & Unit 2 RHR Sys Were Declared Inoperable & Inadvertent Esg Actuation Was Noted While Performing TS Related Surveillances.Cause Is Under Investigation.Restored ESF Equipment
| 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) |
| 05000295/LER-1997-016-01, Forwards LER 97-016-01,which Clarifies Info on Event Description,Root Causes & Safety Analysis.Cas Have Been Updated.Attachment a Provides Commitments Associated W/ Correspondence | Forwards LER 97-016-01,which Clarifies Info on Event Description,Root Causes & Safety Analysis.Cas Have Been Updated.Attachment a Provides Commitments Associated W/ Correspondence | |
| 05000295/LER-1997-016, Forwards LER 97-016-00 Re Failure to Recognize That 125 Vdc Buses Were Inoperable During Inter Unit cross-tie.Event Investigation Is Ongoing & Corrective Actions Will Be Provided in Supplemental LER | Forwards LER 97-016-00 Re Failure to Recognize That 125 Vdc Buses Were Inoperable During Inter Unit cross-tie.Event Investigation Is Ongoing & Corrective Actions Will Be Provided in Supplemental LER | |
| 05000295/LER-1997-016-02, :on 970905,failed to Recognize That 125 Vdc Buses Were Inoperable During Inter Unit cross-tie.Cause Indeterminate.Corrective Actions Will Provided in Supplemental Response to LER |
- on 970905,failed to Recognize That 125 Vdc Buses Were Inoperable During Inter Unit cross-tie.Cause Indeterminate.Corrective Actions Will Provided in Supplemental Response to LER
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(1) |
| 05000295/LER-1997-017-02, :on 970806,TS Surveillance on Containment Isolation Valve Operability Was Missed After Maint.Cause Undetermined.Revised & Performed PT-306 for Affected Valves Prior to Units 1 & 2 Reaching Mode 4 |
- on 970806,TS Surveillance on Containment Isolation Valve Operability Was Missed After Maint.Cause Undetermined.Revised & Performed PT-306 for Affected Valves Prior to Units 1 & 2 Reaching Mode 4
| 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)
10 CFR 50.73(a)(2)(1) |
| 05000295/LER-1997-017, Forwards LER 97-017-00,informing That TS Surveillance Containment Isolation Valve Operability Was Missed After Maint.Commitments Made within Ltr,Encl | Forwards LER 97-017-00,informing That TS Surveillance Containment Isolation Valve Operability Was Missed After Maint.Commitments Made within Ltr,Encl | |
| 05000295/LER-1997-017-01, :on 970806,TS Surveillance on Containment Isolation Valve Operability After Maint Was Missed.Caused by Personnel Error.Procedure Writer Who Failed to Identify Remaining Procedures by 1993 UFSAR Rev Has Been Counseled |
- on 970806,TS Surveillance on Containment Isolation Valve Operability After Maint Was Missed.Caused by Personnel Error.Procedure Writer Who Failed to Identify Remaining Procedures by 1993 UFSAR Rev Has Been Counseled
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