05000455/LER-1990-001, Ro:On 900118,Unit 2 Experienced Unanticipated ECCS Actuation During Testing Activities.Caused by 2 of 3 Channel Coincidence of Low Steam Line Pressure Due to One Channel in Test & Second Channel Spiking Low.W/O Stated LER 90-00

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Ro:On 900118,Unit 2 Experienced Unanticipated ECCS Actuation During Testing Activities.Caused by 2 of 3 Channel Coincidence of Low Steam Line Pressure Due to One Channel in Test & Second Channel Spiking Low.W/O Stated LER 90-001
Person / Time
ML20012E915
Site:	Byron
Issue date:	03/15/1990
From:	Pleniewicz R COMMONWEALTH EDISON CO.
To:	Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
BYRON-90-0282, BYRON-90-282, NUDOCS 9004090084
Download: ML20012E915 (1)
v • d • e

LER-1990-001, Ro:On 900118,Unit 2 Experienced Unanticipated ECCS Actuation During Testing Activities.Caused by 2 of 3 Channel Coincidence of Low Steam Line Pressure Due to One Channel in Test & Second Channel Spiking Low.W/O Stated LER 90-001

Event date:
Report date:
4551990001R00 - NRC Website
v • d • e

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j March 15, 1990-L 1

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LTR BYRON 90-0282 j

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FILE:

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1 Mr. A. Bert Davis U. S. Nuclear Regulatory Commission

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3, Regional Administrator l

I' Region III

(

799 Roosevelt Road i

Glen Ellyn, IL 60137 SUBJECT Dyron Unit 2, ECCS Actuation Report i.

Dear Mr. Davist L

This letter is submitted to document the circumstances of a recent Emergency Core. Cooling System (ECCS) actuation at Byron Station Unit 2.

r On January 10, 1990,'Dyron Unit 2 experienced an unanticipated ECCS actuation during testing' activities. The actuation was initiated by a 2 of 3 channel I

L coincidence of low steam line pressure due to one channel in test and a second

{

channel spiking low.

At no time did conditions in the plant exist.which would t

require mitigation by the ECCS. At the time of the event, the unit was in Mode 1, Power Operation, at 99% reactor power. The attached report, LER

[

90-001,' describes the circumstances of the ECCS actuation in detail.

l To dat.e, Byron Unit 2 has experienced four (4) unplenned injections by the ECCS.

..In this occurrence, it is estimated that 3150 gallons of borated water were injected into the. Reactor Coolant System through the cold leg injection flowpath of the Charging / Safety injection Pumps. Given a design parameter of 110 actuation cycles for life-of-plant, Dyron Unit 2 is well below the y

report.able nozzle usage factor of 0.70.

This report is submitted in accordance with Technical Specifications 6.9.2 and j

3.5.2.

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f(xA.- --v

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R. Plenlewics p

Station Manager

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Byron Nuclear Power Station HP/SM/bf' ces W. Kropp, NRC Senior Resident Inspector

((f INPO Record Center Ceco Distribution List 3

'9004090084[6$hs3 PDR ADOCK PDC Np' l

(2429z/47z)

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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
05000455/LER-1990-001-03, :on 900118,during Functional Surveillance on Steam Generator Pressure Channel 526,channel 525 Spiked Low, Causing Reactor Trip & Safety Injection.Caused by Failure of Pressure Transmitter.Transmitter Replaced	on 900118,during Functional Surveillance on Steam Generator Pressure Channel 526,channel 525 Spiked Low, Causing Reactor Trip & Safety Injection.Caused by Failure of Pressure Transmitter.Transmitter Replaced	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000454/LER-1990-001-07, :on 900118,determined That Containment Purge Isolation Sys Not Demonstrated Operable 100 H Prior to Start of Core Alterations.Caused by Cognitive Personnel Error. Task Force Formed to Review Tech Specs	on 900118,determined That Containment Purge Isolation Sys Not Demonstrated Operable 100 H Prior to Start of Core Alterations.Caused by Cognitive Personnel Error. Task Force Formed to Review Tech Specs	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 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)
05000455/LER-1990-001, Ro:On 900118,Unit 2 Experienced Unanticipated ECCS Actuation During Testing Activities.Caused by 2 of 3 Channel Coincidence of Low Steam Line Pressure Due to One Channel in Test & Second Channel Spiking Low.W/O Stated LER 90-00	Ro:On 900118,Unit 2 Experienced Unanticipated ECCS Actuation During Testing Activities.Caused by 2 of 3 Channel Coincidence of Low Steam Line Pressure Due to One Channel in Test & Second Channel Spiking Low.W/O Stated LER 90-001
05000455/LER-1990-002-02, :on 900714,feedwater Isolation Signal from Train B Reactor Trip Generated When Reactor Trip Closed. Caused by Cell Switch Which Houses 33a Contacts.Reactor Trip Breaker Replaced	on 900714,feedwater Isolation Signal from Train B Reactor Trip Generated When Reactor Trip Closed. Caused by Cell Switch Which Houses 33a Contacts.Reactor Trip Breaker Replaced	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)
05000454/LER-1990-002-09, :on 900301,reactor Trip Occurred.Caused by Failure of Resistance Temp Detector Card Coincident W/One Channel in Test.Failed Card Replaced.Reactivity Computer Reconnected to Power Range Channel	on 900301,reactor Trip Occurred.Caused by Failure of Resistance Temp Detector Card Coincident W/One Channel in Test.Failed Card Replaced.Reactivity Computer Reconnected to Power Range Channel	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000455/LER-1990-002-11, :on 900714,unexpected Feedwater Isolation Signal from Reactor Trip Breaker Generated.Specific Cause of Event Not Identified.Cell Switch Replaced & Breaker Reinstalled	on 900714,unexpected Feedwater Isolation Signal from Reactor Trip Breaker Generated.Specific Cause of Event Not Identified.Cell Switch Replaced & Breaker Reinstalled	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)(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)
05000454/LER-1990-003-07, :on 900307,individual Cell Voltage for Cell 53 Found to Be at 2.11 Volts,Contrary to Tech Spec Limit.Caused by Electrician Using Improper Acceptance Criteria Format & Inadequate Mgt Review of Surveillance	on 900307,individual Cell Voltage for Cell 53 Found to Be at 2.11 Volts,Contrary to Tech Spec Limit.Caused by Electrician Using Improper Acceptance Criteria Format & Inadequate Mgt Review of Surveillance	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 50.73(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)
05000455/LER-1990-003-11, :on 900717,feedwater Isolation Occurred Due to Inability to Control Level in D-5 Steam Generators at Low Power Levels.Caused by hi-hi Narrow Range Level on Steam Generator 2A.Signal Reset & Sys Realigned	on 900717,feedwater Isolation Occurred Due to Inability to Control Level in D-5 Steam Generators at Low Power Levels.Caused by hi-hi Narrow Range Level on Steam Generator 2A.Signal Reset & Sys Realigned	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)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000455/LER-1990-004-10, :on 900701,discovered That Process Sampling Containment Isolation Valve Not Placed on Increased Test Frequency.Caused by Personnel Error.Procedure Revised to Require Mgt Concurrence on Technical Changes	on 900701,discovered That Process Sampling Containment Isolation Valve Not Placed on Increased Test Frequency.Caused by Personnel Error.Procedure Revised to Require Mgt Concurrence on Technical Changes	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000455/LER-1990-005, :on 900817,pre-outage Mod Work Initiated W/O Proper Operability Review.Caused by Programmatic Deficiencies.Daily Const Work Authorization Sheet Formalized Specifying Scope of Work	on 900817,pre-outage Mod Work Initiated W/O Proper Operability Review.Caused by Programmatic Deficiencies.Daily Const Work Authorization Sheet Formalized Specifying Scope of Work	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)(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) 10 CFR 50.73(a)(2)(1)
05000454/LER-1990-005-04, :on 900327,high Radiation Signal Caused Fuel Handling Bldg Charcoal Booster Fan to Start & Dampers Transferred to ESF Positions.Caused by Procedural Deficiency.Maint Procedures Revised	on 900327,high Radiation Signal Caused Fuel Handling Bldg Charcoal Booster Fan to Start & Dampers Transferred to ESF Positions.Caused by Procedural Deficiency.Maint Procedures Revised	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 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)
05000455/LER-1990-005-11, :on 900811,pre-outage Mod Work Initiated W/O Proper Operability Review Due to Personnel Error.Daily Const Work Authorization Sheet Formalized & Will Specify Scope of Work Step by Step During Nonoutage Periods	on 900811,pre-outage Mod Work Initiated W/O Proper Operability Review Due to Personnel Error.Daily Const Work Authorization Sheet Formalized & Will Specify Scope of Work Step by Step During Nonoutage Periods	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000455/LER-1990-006, :on 910930,reactor Containment Fan Cooler 2C Low Speed Breaker Did Not Close.Caused by Miscommunication & Procedural Deficiency.Procedure Revised to Include Emergency Exit Section	on 910930,reactor Containment Fan Cooler 2C Low Speed Breaker Did Not Close.Caused by Miscommunication & Procedural Deficiency.Procedure Revised to Include Emergency Exit Section	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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000455/LER-1990-006-11, :on 900903,reactor Containment Fan Cooler 2C, Low Speed Fan Breaker Did Not Close,Resulting in Train a Safety Injection Signal.Caused by Miscommunication & Procedure Deficiency.Procedure Revised	on 900903,reactor Containment Fan Cooler 2C, Low Speed Fan Breaker Did Not Close,Resulting in Train a Safety Injection Signal.Caused by Miscommunication & Procedure Deficiency.Procedure 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000454/LER-1990-006-05, :on 900503,as Surveillance Underway All Indication on Digital electro-hydraulic Computer Panel Was Lost.Caused by Failure of Ampere Fuse Due to Short Circuit in Pushbutton.Lighting Circuit Rewired	on 900503,as Surveillance Underway All Indication on Digital electro-hydraulic Computer Panel Was Lost.Caused by Failure of Ampere Fuse Due to Short Circuit in Pushbutton.Lighting Circuit Rewired	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)(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)(1)
05000455/LER-1990-007-10, :on 900928,ECCS Throttle Valve Found Closed Due to Procedural Deficiency	on 900928,ECCS Throttle Valve Found Closed Due to Procedural Deficiency	10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)
05000454/LER-1990-007-06, :on 900612,discovered That Steam Line Isolation Handswitch on Main Control Board Panel 1PM06J Not Tested During Past Refueling Outages.Caused by Deficient Procedure. All Similar Equipment Will Be Reviewed	on 900612,discovered That Steam Line Isolation Handswitch on Main Control Board Panel 1PM06J Not Tested During Past Refueling Outages.Caused by Deficient Procedure. All Similar Equipment Will Be Reviewed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1990-007-01, :on 900612,main Steam Line Isolation Sys Declared Inoperable Due to Failure to Test Manual Initiation Handswitch.Caused by Deficiency in Procedure.Procedures Reviewed	on 900612,main Steam Line Isolation Sys Declared Inoperable Due to Failure to Test Manual Initiation Handswitch.Caused by Deficiency in Procedure.Procedures Reviewed	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)
05000454/LER-1990-007, :on 900612,discovered That Steam Line Isolation Handswitch on Main Control Board Panel Not Tested During Past Refueling Outage.Caused by Use of Deficient Procedure.All Contacts on Switches Tested	on 900612,discovered That Steam Line Isolation Handswitch on Main Control Board Panel Not Tested During Past Refueling Outage.Caused by Use of Deficient Procedure.All Contacts on Switches 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)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(n)(2)
05000455/LER-1990-008-10, :on 900929,fuel Assembly Dropped During Reconstitution Due to Procedural Inadequacy	on 900929,fuel Assembly Dropped During Reconstitution Due to Procedural Inadequacy	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000455/LER-1990-008-02, :on 900929,dropped Fuel Assembly Occurred During Reconstitution.Caused by Procedural Inadequacy. Generic Westinghouse Fuel Repair Revised & Latching Components of Basket Replaced	on 900929,dropped Fuel Assembly Occurred During Reconstitution.Caused by Procedural Inadequacy. Generic Westinghouse Fuel Repair Revised & Latching Components of Basket Replaced	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000455/LER-1990-009-10, :on 901107,ESF Actuation Caused by low-2 Steam Generator Level Occurred Due to Procedural Deficiency.W/	on 901107,ESF Actuation Caused by low-2 Steam Generator Level Occurred Due to Procedural Deficiency.W/	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000454/LER-1990-010-05, :on 900818,1A Auxiliary Feedwater Pump Automatic Start Occurred Due to Module Failure.Caused by Relay K1AA Energizing W/O Necessary 3 of 4 Low Steam Generator Signals.Driver Module Panel Replaced	on 900818,1A Auxiliary Feedwater Pump Automatic Start Occurred Due to Module Failure.Caused by Relay K1AA Energizing W/O Necessary 3 of 4 Low Steam Generator Signals.Driver Module Panel Replaced	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)
05000454/LER-1990-010, :on 900818,1A Auxiliary Feedwater Pump Auto Start Due to Module Failure	on 900818,1A Auxiliary Feedwater Pump Auto Start Due to Module Failure	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)
05000455/LER-1990-010-11, :on 901220,severe Steam Leak Reported in Main Steam Tunnel.Caused by Improper Installation of Sample Probe During Initial Const.One Inch Nozzle Capped & Weld in Place by Temporary Alteration 90-2-66	on 901220,severe Steam Leak Reported in Main Steam Tunnel.Caused by Improper Installation of Sample Probe During Initial Const.One Inch Nozzle Capped & Weld in Place by Temporary Alteration 90-2-66	10 CFR 50.73(a)(2)
05000455/LER-1990-010-02, :on 901220,severe Steam Leak Reported in Main Steam Tunnel & Main Steam Sample Probe 2C Found Lying on Floor.Caused by Incorrect Installation of Sample Probe. Nozzle Capped & Welded in Place	on 901220,severe Steam Leak Reported in Main Steam Tunnel & Main Steam Sample Probe 2C Found Lying on Floor.Caused by Incorrect Installation of Sample Probe. Nozzle Capped & Welded in Place	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)
05000454/LER-1990-011-04, :on 900819,high Negative Flux Rate Reactor Trip Occurred Due to Loss of CRD Power Supplies During Lightning Strike.Ground Cables & Lightning Rods Verified Intact	on 900819,high Negative Flux Rate Reactor Trip Occurred Due to Loss of CRD Power Supplies During Lightning Strike.Ground Cables & Lightning Rods Verified Intact	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000454/LER-1990-011-01, :on 900819,reactor Trip Occurred Due to Power Surge.Caused by Lightning Strike.Rod Drive Sys Will Be Modified W/New Model of Power Supply Less Likely to Cause Reactor Trip	on 900819,reactor Trip Occurred Due to Power Surge.Caused by Lightning Strike.Rod Drive Sys Will Be Modified W/New Model of Power Supply Less Likely to Cause Reactor Trip	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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000454/LER-1990-012-02, :on 900906,determined That Auxiliary Feedwater Discharge Isolation Valves Could Not Be Relied Upon.Caused by Inadequate Emergency Procedures.Revs to Emergency Procedures in Progress	on 900906,determined That Auxiliary Feedwater Discharge Isolation Valves Could Not Be Relied Upon.Caused by Inadequate Emergency Procedures.Revs to Emergency Procedures in Progress	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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000454/LER-1990-013-03, :on 901031,loss of Oa & Ob Essential Svc Water Makeup Pumps Occurred Due to Personnel Error	on 901031,loss of Oa & Ob Essential Svc Water Makeup Pumps Occurred Due to Personnel Error	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1990-014-04, :on 901203,actual Feedwater Isolation Signal Generated During Performance of Slave Relay Surveillance 1BOS 3.2.1-980,causing Loss of Feedwater.Caused by Personnel Error.Switch S817 Replaced	on 901203,actual Feedwater Isolation Signal Generated During Performance of Slave Relay Surveillance 1BOS 3.2.1-980,causing Loss of Feedwater.Caused by Personnel Error.Switch S817 Replaced	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)

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