05000295/LER-1997-021-01, Forwards LER 97-021-01,per 10CFR50.73(a)(2)(i)(B). Commitments Associated W/Correspondence,Encl

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Forwards LER 97-021-01,per 10CFR50.73(a)(2)(i)(B). Commitments Associated W/Correspondence,Encl
Person / Time
ML20197G147
Site:	Zion File:ZionSolutions icon.png
Issue date:	12/23/1997
From:	Starkey R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20197G153	List: 05000295/LER-1997-021-01, Forwards LER 97-021-01,per 10CFR50.73(a)(2)(i)(B). Commitments Associated W/Correspondence,Encl
References
NUDOCS 9712300387
Download: ML20197G147 (1)
v • d • e

LER-1997-021, Forwards LER 97-021-01,per 10CFR50.73(a)(2)(i)(B). Commitments Associated W/Correspondence,Encl

Event date:
Report date:
2951997021R01 - NRC Website
v • d • e

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ifil %hiloll ibniin.itd fung. ll turn iv 1,w e~u,vms December 23,1997 U.S. Nuelcar llegulatory Commission Document Control Desk Washington, DC 20555 IInclosed is Supplemental 1.icensee IIvent Iteport (Llilt) number 1 97-021 Itevision 01, Docket No. 50 000295 that is being submitted pursuant to 10CFitS0.73 (a)(2)(i)(II),

which requires a 30 day written report when any operation occurs that is prohibited by the plant's Technical Specifications.

Attachment A provides commitments associated with this correspondence.

Very truly yours.

p-+1J%

It. Starkey Station Manager Zion Generating Station RS/jb linclosures:

Licensee livent Iteport itegulatory Commitment List

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NRC llegion 111 Administrator NitC Zion Resident inspector lilinois Department of Nuclear Safety [8 ] 7-IDNS. Resident inspector d'

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9712300307 971223 PDR ADOCK 05000295 8

PDR 30C350 ll!.l.lll.1 Ill.!.II k l 'o k.',l81) ('41ol{1.%fl) j

Licensee Event Report

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
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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