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p o, Box 270
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HARTFORD. CONNECTIOUT 00414-0270 L
Nvineast tuew rne gv mpany (2031665-5000 Re: 10CFR50.73(a)(2)(i)
March 18, 1991 MP-91-237 U.S. Nuclear Reculatory Commission Document Contr'ol Desk Washington, D.C. 20555
Reference:
Facility Operatine License No. NPF-49 Docket No. 50-423 Licensee Event Report 90-001-0:
Gentlemen:
This letter forwards Licensee Event Report 90-001-01, which is being submitted to revise corrective action information. Licensee Event Report 90~001-00 was submitted pursuant to 10CFR50.73(a)(2)(1), any operation or condition prohibited by the plant's Technical Specification.
I Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: Stephen E. Scace Director, Millstone Station f
/
BY:
arl
. Clemen Millstone Unit 3 Director SES/PAF:mo I
Attachment: LER 90-001-01 cc:
T. T. Martin, Recion 1 Administrator W. J. Raymond,' Senior Resident inspector, Millstone Unit Nos.1, 2 and 3 D. H. Jaffe, NRC Project Manager, Millstone Unit Nos. I and 3 kc'c) 3XI 91 OcA.* A m sM e Mp2{gggg Q, TA
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o., aeorocai,,y im., img... es:. iyo.orm.s un.i3 ne, On January 6,1990 at approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, with the plant at 100G power (Mode 1), 2 50 psia and 556 degrees Fahrenhen, it was discovered that a fire hose rack located in the Fuel Buildmg had insufficient lengths of fire hose to fulfill Plant Technical Specification hose station operabihty requirements. In accordance 'with the appheable Technical Specification, hose station operabihty was restored within one hour of discovery by installation of additional hose lengths. In response to the discovery of the deficient Fuel Building hose rack all other Technical Specification hose racks outside the Containment Building were inspected. Seven additional racks m the Auxihary Buildmg were found wnh insufficient hose lengths. Each deficient rack was restored to operable status wnhin one hour of discovery.
The cause of the hose rack found deficient in trie Fuel Building is undetermined. The cause of seven hose racks found deficient in the Auxihary Buildmg is procedural inadequac) in that the surveillance procedure did not accurately reflect minimum fire hose length requirements.
As action to prevent recurrence, the surveillance procedure was changed to accurately reflect the mintmum fire hose lengths requtred. On February 14, 1991, during a scheduled refueling outage, the hose racks inside the Contamment Buildmg were inspected to the requirements of the updated procedure. Five hose racks were found to be deficient and were restored to operable status.
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TEXT CONTINUATION
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?lN W~nM$'l.%s?c'WoSci E u.m.m.m am em t w. wem oc moa F AO(fry N AM& (1) oocMI NUM6fb di LFU MlWrE 8F' N'3' Mp MN YEAR Millstone Nuclear Power Station Umt 3 0 6l 0l 0l 0l4 l2 l3 9l0 0l 0l1 0l1 0l 0 OF 0l3 TE n m mo,e im. <ew.c use wemow Nec Form m ) on 1.
De-Mn of Event On January 8,1990 at approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, with the plant at 100r power (Mode 1), 0250 psia c
and $16 degrees Fahrenheit, it was discovered that a fire hose rack located on the elesen foot elevation of the Fuel Buildmg had insufficient lengths of fire hose to fulfill Plant Design Basis hose station operabihty requirements. This deficiency was drcosered during the performance of the Technical Specification suncillance of Unit 3 fire hose racks by site Engineering and Maintenance department personnel. The suneillance procedure required a minimum of 75 feet of hose, but only one 50 foot section was on the rack. Additionally, further invesugation revealed that the procedure was not m agreement with the series 14 Piping and Instrumentation Diagrams (P&lDs) shown in the fire protection l
cvaluauon, which required 125 feet of hose. These P&lDs are the diagrams used to defme minimum required hose lengths at hose stauons to mamtain Technical Specificauon operabihty. In accordance with the appheable Technical Specification Limiting Condition for Operation (LCO 3.7.12.5 " Fire Hose Stations"), hose stauon operabihty was restored wnhin one hour of discovery by addmon of enough hose lengths to meet the requirements of the P& ids.
In response to the discovery of the aforementioned deficient hose rack, all other Techmcal Specificanon hose racks. outside the Containment Building, were inspected on January 6,1990. The hose racks -
mside the Containment Buildmg were excluded from this inspection because of inaccessibihty due to personnel safety / radiation exposure considerations. Seven additional racks m the Auxihary Buildmg were found with insufficient hose lengths and were declared inoperable. In these cases however, the number of hose lengths did meet the requirements of the surveillance procedure, but the procedure was not in comphance with the P&lDs. Each deficient tack was restored to operable status ulthin one hour of discovery in accordance with LCO 3.7.12.5 by addmg the required hose lengths.
11.
Cause of Es ern The cause of the hose rack tound deficient in the Fuel Buildmg can not be positively determined. A resnew of the previous month's surveillance data indicates the correct amount of hose lengths were in place. However, there appears to have been some confusion by persons performing the surveillance in determmmg hose length by visual inspecuon. They were not aware that all fire hose utilized at Unit 3 (ulth the exception of one case) are in 50 foot length. During the visual surveillance inspection, it was most likely assumed the one length hanging on the rack was 75 feet in length.'
The root cause of seven hose racks found deficient in the Auxiliary Building is procedural inadequacy.
The appbcable surveillance procedure did not accuratel) reflect fire hose length requirements as shown on the P&lDs. It is uncertain how the incorreci fire hose lengths were incorporated into the procedure.
During the ume penod when the procedure was revised to include Unit 3 fire hose stations, continuing fire hose length evaluations and modifications were being performed to fulfill regulatory requirements.
Ill.
Analveic of Event 4
This event is reportable pursuant to 10CFR$0.73(a)(2)(i), as a condition prohibited by Plant Technical Specibcations.
Fire suppression for the affected areas consists of the unit fire brigade. Conservatism was estabbshed when the initial fire hose length evaluations were performed. Field testing has verified that, in each case invohang the Fuel and Auxihary Buildmgs, there was adequate hose lengths at the Technical Specification Hose Stations to fulfill fire fighting requirements pertinent to each fire zone. The Containment building is classified as one fire area as discussed in the Unit 3 Fire Protection Evaluation Report. While fire fightmg capabihues were degraded with the reduction of fire hose inventory, combined fire hose lengths allowed for fire fighting coverage of the Containment Building. Therefore, the health and safety of the pubhc was not jeopardned and the event posed no significant safety consequences, j
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TEXT CONTINUATION a,e Aeoorts uanagemoni e..ner. n-633t v s N.,eier Aegstatory Com%ssion Washington oc 20sf s anc tc the Pape won 8<ecoctior Prc e:1(3150-0 9 ) otoce of Manageme*" av tsuccet Wa shington DO 20s03 F A01UTY NAME (),
DOCKET NUMBF O i p gam r r, st i FAGE 13 4 YEAR Ng jg Millstone Nuclear Power ctation Unn3
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Corrective Action
immediate corrective action was to restore all fire hose stations, outside the Containment Buildmp, to l
operable status withm one hour of discosery. This was accomphshed by ensuring all fire hose stations were in comphance with the series 116 P&lDs.
The action to present recurrence is two part. First, the appheable surveillance procedure was changed to reflect fire hose lengths as listed on the P&lDs. Also, the procedure has been revised to require a senior heensed operator review pnor to presentation to the Site Operations Review Comtr'ttee for approval.
incorporatian of this requirement was completed on May 1,1990.
Personnel performing the hose station surveillances have received departmental trammg to increase familiarization with the Unit's fire fighting apparatus. They base also received formal trainmg by attendmp the stations Nuclear Trammg Department's course for fire exunguisher/ hose inspecuon and maintenance. In addition, a recent department reorganization has placed the group responsible for performance of the applicable hose station surveillance within a site engmeermg group to ensure adequate techrucal guidance.
Addiuonally, signs were posted on all Technical Specification Hose Stations requiring that the Unit Shift Supemsor be notif ed when removmp any equipment from the stat on. All signs were mstalled at stations outside of the Containment Buildmg by February 7,1990.
Followmg the scheduled plant shutdown for the refuehng outage (which began on February 2,1991),
signs were posted on the Technical Specification hose station by February 6,1991.
On February 14, 1991. during the refuelmg outage, the hose stations inside the Containment Building were inspected to the requirements of the revised surveillance procedure. Five hose racks were found to be deficient and were restored to operable status.
Y.
AddnionM Information i
There has been one previous similar event to date. Licensee Event Report (LER) 89-023-00 reported i
that insufficient hose lengths were discovered at outdoor hydrant hose houses resulting in inoperability of j
the hydrant hose houses. In LER 89-023, the root causes were personnel error and procedural inadequacy. The corrective action was: to verify all suffic ent hydrant hose house inventory, to post t
caution signs at the hydrant hose houses, and to require a senior heensed operator review of procedural revisions. In retrospect, these correcuve actions were limited in scope. Had the corrective actions been applied to all Technical Specification hose stations, the events discussed in this LER could have been prevented.
I Ells Cc, des System Comnonents e
Fire Protection (water) - KP Hose Houses Hoses i
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| 05000245/LER-1990-001-02, :on 900126,determined That 1 H Roving Fire Patrol Established on 900125 for Two Nonfunctional Fire Barriers Penetrations Not Consistent W/Requirements of Tech Spec 3.12.F.2.Caused by Personnel Error |
- on 900126,determined That 1 H Roving Fire Patrol Established on 900125 for Two Nonfunctional Fire Barriers Penetrations Not Consistent W/Requirements of Tech Spec 3.12.F.2.Caused by Personnel Error
| 10 CFR 50.73(a)(2)(i) | | 05000423/LER-1990-001, :on 910108,inoperable Fire Hose Stations Due to Insufficient Fire Hose Inventory.Cause Unknown for Fuel Bldg Fire Hose Rack & Procedural Inadequacy for Auxiliary Bldg Fuel Racks.Station Restored to Operable Status |
- on 910108,inoperable Fire Hose Stations Due to Insufficient Fire Hose Inventory.Cause Unknown for Fuel Bldg Fire Hose Rack & Procedural Inadequacy for Auxiliary Bldg Fuel Racks.Station Restored to Operable Status
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000336/LER-1990-001, :on 900110,discovered That Surveillances in Tech Specs for New Smoke Detectors & Suppression Sys Not Performed.Caused by Personnel Error.Fire Protection Sections of Tech Specs Updated |
- on 900110,discovered That Surveillances in Tech Specs for New Smoke Detectors & Suppression Sys Not Performed.Caused by Personnel Error.Fire Protection Sections of Tech Specs Updated
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000423/LER-1990-001-01, :on 900108,discovered That Fire Hose Racks in Fuel & Auxiliary Blgs Had Insufficient Fire Lengths to Fulfill Tech Spec Operability Requirements.Caused by Procedural Inadequacy.Caution Signs Posted |
- on 900108,discovered That Fire Hose Racks in Fuel & Auxiliary Blgs Had Insufficient Fire Lengths to Fulfill Tech Spec Operability Requirements.Caused by Procedural Inadequacy.Caution Signs Posted
| 10 CFR 50.73(a)(2)(i) | | 05000245/LER-1990-002-01, :on 900305,main Steam Line High Flow Setpoint Determined to Be Incorrect & Nonconservative.Caused by Use of Incorrect Assumptions Based on Original Plant Design Conditions.Setpoint Corrected |
- on 900305,main Steam Line High Flow Setpoint Determined to Be Incorrect & Nonconservative.Caused by Use of Incorrect Assumptions Based on Original Plant Design Conditions.Setpoint Corrected
| 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1990-002-02, :on 900322,Tech Spec Action Statement 3.3.3.10 Not Entered for Out of Svc Stack Gas & Particulate Radiation Monitor.No Particulate Radiation Increases Detected.Caused by Personnel Error |
- on 900322,Tech Spec Action Statement 3.3.3.10 Not Entered for Out of Svc Stack Gas & Particulate Radiation Monitor.No Particulate Radiation Increases Detected.Caused by Personnel Error
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000423/LER-1990-002, :on 900109,partial Train a Containment Depressurization Actuation Signal Generated.Caused by Personnel Error.Warnings Added to Production Maint Mgt Sys for Recirculation Spray Sys Pump Breakers |
- on 900109,partial Train a Containment Depressurization Actuation Signal Generated.Caused by Personnel Error.Warnings Added to Production Maint Mgt Sys for Recirculation Spray Sys Pump Breakers
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000245/LER-1990-003, :on 900302,determined That 4-day Limiting Condition for Operation for One Emergency Power Sources, Gas Turbine Generator Exceeded.Caused by Lack of Verification of Load Requirement |
- on 900302,determined That 4-day Limiting Condition for Operation for One Emergency Power Sources, Gas Turbine Generator Exceeded.Caused by Lack of Verification of Load Requirement
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(0)(i) | | 05000423/LER-1990-003, :on 900115,discovered That Fire Watches Not Established Prior to Removing Deluge Sys for Trains a & B Reserve Station Svc Transformers from Svc.Caused by Personnel Error.Personnel Counseled |
- on 900115,discovered That Fire Watches Not Established Prior to Removing Deluge Sys for Trains a & B Reserve Station Svc Transformers from Svc.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1990-004-01, :on 900228,control Room Ventilation Sys Operated Outside Tech Specs.Caused by Inconsistency in Tech Specs.Proposed Tech Spec Change Request Submitted Re Emergency Diesel Generator Operability |
- on 900228,control Room Ventilation Sys Operated Outside Tech Specs.Caused by Inconsistency in Tech Specs.Proposed Tech Spec Change Request Submitted Re Emergency Diesel Generator Operability
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000423/LER-1990-004, :on 900115,nuclear Instrument Power Range Channel N43 Became Inoperable Due to Power Supply Failure. Caused by Computer Program 3R5 Design Inadequacy.Night Order Issued to Enter Tech Spec 4.2.1.1.1.b |
- on 900115,nuclear Instrument Power Range Channel N43 Became Inoperable Due to Power Supply Failure. Caused by Computer Program 3R5 Design Inadequacy.Night Order Issued to Enter Tech Spec 4.2.1.1.1.b
| 10 CFR 50.73(a)(2)(i) | | 05000245/LER-1990-004-02, :on 900406,calculation Which Was Performed to Verify Reactor High Pressure Scram Setpoint Demonstrated That Existing Head Correction Nonconservative.Caused by Lack of Independent Verification of Setpoint |
- on 900406,calculation Which Was Performed to Verify Reactor High Pressure Scram Setpoint Demonstrated That Existing Head Correction Nonconservative.Caused by Lack of Independent Verification of Setpoint
| 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1990-004, :on 900228,Unit Operated Outside of Tech Specs for Control Room Air Conditioning Sys.Caused by Inconsistency in Tech Specs.Tech Spec Change Request Approved |
- on 900228,Unit Operated Outside of Tech Specs for Control Room Air Conditioning Sys.Caused by Inconsistency in Tech Specs.Tech Spec Change Request Approved
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) | | 05000336/LER-1990-005, :on 900503,notified of Potential High Energy Line Break Via as Sys in Safety Related Areas.Caused by Inaccurate Conclusions Drawn from 1973 Rept.As Sys Removed from Svc & Plant Mods Initiated |
- on 900503,notified of Potential High Energy Line Break Via as Sys in Safety Related Areas.Caused by Inaccurate Conclusions Drawn from 1973 Rept.As Sys Removed from Svc & Plant Mods Initiated
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000336/LER-1990-005-02, :on 900503,identified Potential for High Energy Line Break in Auxiliary Steam Sys That Could Degrade Plant Areas Determined as Mild Environs.Probably Caused by Incorrect Conclusions from Analysis in 1973 |
- on 900503,identified Potential for High Energy Line Break in Auxiliary Steam Sys That Could Degrade Plant Areas Determined as Mild Environs.Probably Caused by Incorrect Conclusions from Analysis in 1973
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vi) | | 05000423/LER-1990-005, :on 900118,manual Plant Trip Initiated in Anticipation of Automatic Trip on lo-lo Level in All Four Steam Generators.Caused by Loss of Preload on Coupling Blocks from Personnel Error.Procedure Revised |
- on 900118,manual Plant Trip Initiated in Anticipation of Automatic Trip on lo-lo Level in All Four Steam Generators.Caused by Loss of Preload on Coupling Blocks from Personnel Error.Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000245/LER-1990-005-01, :on 900411,determined That Daily Surveillance Greater than 6 H from Previous Days Surveillance.Caused by Combination of Factors Including Administrative Deficiency. Operations Dept Logs Revised |
- on 900411,determined That Daily Surveillance Greater than 6 H from Previous Days Surveillance.Caused by Combination of Factors Including Administrative Deficiency. Operations Dept Logs Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000245/LER-1990-006-01, :on 900424,determined That Gas Turbine Encl Not Included in Monthly Surveillance for Nonsupervised Circuits. Caused by Personnel Error.Gas Turbine Fire Detection Surveillance Changed to Monthly |
- on 900424,determined That Gas Turbine Encl Not Included in Monthly Surveillance for Nonsupervised Circuits. Caused by Personnel Error.Gas Turbine Fire Detection Surveillance Changed to Monthly
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000423/LER-1990-006, :on 900118,chemistry Dept Determined 6-month Interval Tech Spec for Average Disintegration Energy Determination Not Met.Caused by Inappropriate Appliance of Surveillance Interval.Addl Controls Placed |
- on 900118,chemistry Dept Determined 6-month Interval Tech Spec for Average Disintegration Energy Determination Not Met.Caused by Inappropriate Appliance of Surveillance Interval.Addl Controls Placed
| 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1990-006-02, :on 900508,reactor Manually Tripped When Decreasing Levels Noted in Steam Generator 1 & Feedwater Regulating Valve Indicated Full Open.Caused by Valve Stem Separating from Plug.Feedwater Flow Restored |
- on 900508,reactor Manually Tripped When Decreasing Levels Noted in Steam Generator 1 & Feedwater Regulating Valve Indicated Full Open.Caused by Valve Stem Separating from Plug.Feedwater Flow Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | | 05000245/LER-1990-007-01, :on 900512,determined That One Emergency Power Source Did Not Have Sufficient Capacity for Accident Loading Conditions.Gas Turbine Generator Declared Inoperable & Orderly Reactor Shutdown Initiated |
- on 900512,determined That One Emergency Power Source Did Not Have Sufficient Capacity for Accident Loading Conditions.Gas Turbine Generator Declared Inoperable & Orderly Reactor Shutdown Initiated
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) | | 05000336/LER-1990-007, :on 900611,discovered Missed Surveillance Prior to Entering Mode 4 |
- on 900611,discovered Missed Surveillance Prior to Entering Mode 4
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000336/LER-1990-007-02, :on 900611,discovered That Surveillance Procedure 2609E Re Encl Bldg Filtration Sys Testing - Refueling Not Performed Prior to Entering Mode 4.Caused by Personnel Error.Missed Surveillance Performed |
- on 900611,discovered That Surveillance Procedure 2609E Re Encl Bldg Filtration Sys Testing - Refueling Not Performed Prior to Entering Mode 4.Caused by Personnel Error.Missed Surveillance Performed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000423/LER-1990-007, :on 900125,discovered That Tech Spec Surveillance Did Not Verify Load Shedding of Five Compressors.Caused by Procedural Inadequacy & Personnel Error.Surveillance Procedure Revised |
- on 900125,discovered That Tech Spec Surveillance Did Not Verify Load Shedding of Five Compressors.Caused by Procedural Inadequacy & Personnel Error.Surveillance Procedure Revised
| 10 CFR 50.73(a)(2)(i) | | 05000245/LER-1990-008-01, :on 900531,determined That Fuel Thermal Limit Exceeded Tech Spec Limit.Caused by Underestimation of Xenon Transient That Resulted from Power Reduction.Refresher Course Planned for Personnel |
- on 900531,determined That Fuel Thermal Limit Exceeded Tech Spec Limit.Caused by Underestimation of Xenon Transient That Resulted from Power Reduction.Refresher Course Planned for Personnel
| 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1990-008-02, :on 900620,determined That Grab Sample of Unit Stack Gas Not Taken.Caused by Lack of Communication Between Personnel.Grab Sample Obtained & Analyzed |
- on 900620,determined That Grab Sample of Unit Stack Gas Not Taken.Caused by Lack of Communication Between Personnel.Grab Sample Obtained & Analyzed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000245/LER-1990-009-01, :on 900511,determined That House Heating Steam Sys Could Potentially Degrade Environ Classified, Eeq Mild Environs. Caused by Incorrect Conclusion Drawn from 1973 Study.Plant Mods Implemented |
- on 900511,determined That House Heating Steam Sys Could Potentially Degrade Environ Classified, Eeq Mild Environs. Caused by Incorrect Conclusion Drawn from 1973 Study.Plant Mods Implemented
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000336/LER-1990-009-02, :on 900617,inadvertent Partial Actuation of Train B of Enclosure Bldg Filtration Sys Occurred.Root Cause Not Determined.No Corrective Actions Recommended Until Further Testing & Troubleshooting Performed |
- on 900617,inadvertent Partial Actuation of Train B of Enclosure Bldg Filtration Sys Occurred.Root Cause Not Determined.No Corrective Actions Recommended Until Further Testing & Troubleshooting Performed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000336/LER-1990-009-01, :on 900617,facility Experienced Inadvertent Partial Actuation of Train B of Auxiliary Exhaust Actuation Sys.Cause Undetermined.Two Addl Actuations Occurred on 900711 |
- on 900617,facility Experienced Inadvertent Partial Actuation of Train B of Auxiliary Exhaust Actuation Sys.Cause Undetermined.Two Addl Actuations Occurred on 900711
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000423/LER-1990-009, :on 900309,automatic Turbine Trip W/Subsequent Reactor Trip Occurred Due to High Stator Cooling Water Temp. Caused by Failure of Mechanical Linkage on Fisher & Portor Controller.Controller Replaced W/Spare |
- on 900309,automatic Turbine Trip W/Subsequent Reactor Trip Occurred Due to High Stator Cooling Water Temp. Caused by Failure of Mechanical Linkage on Fisher & Portor Controller.Controller Replaced W/Spare
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(viii)(B) | | 05000245/LER-1990-010-01, :on 891223,EEQ Barriers Violated W/Switchgear Area & Heating & Ventilation Room Mild Environ & Turbine Deck Had Potential Harsh Environ.Caused by Lack of Formal guidance.Long-term Program Developed |
- on 891223,EEQ Barriers Violated W/Switchgear Area & Heating & Ventilation Room Mild Environ & Turbine Deck Had Potential Harsh Environ.Caused by Lack of Formal guidance.Long-term Program Developed
| | | 05000423/LER-1990-010, :on 900319,both Trains of Auxiliary Bldg Filters Became Inoperable When Train B Circuit Breaker Motor Failed & Train a Filter Removed from Svc.Caused by Fatigue Failure in Breaker Spring.Filter Work Stopped |
- on 900319,both Trains of Auxiliary Bldg Filters Became Inoperable When Train B Circuit Breaker Motor Failed & Train a Filter Removed from Svc.Caused by Fatigue Failure in Breaker Spring.Filter Work Stopped
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000336/LER-1990-010-02, :on 900621,door Identified in Configuration Not Consistent W/Bechtel Design Drawings During High Energy Line Review.Caused by Lack of Knowledge of Requirements.Double Door Reinforced |
- on 900621,door Identified in Configuration Not Consistent W/Bechtel Design Drawings During High Energy Line Review.Caused by Lack of Knowledge of Requirements.Double Door Reinforced
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000336/LER-1990-010-01, :on 900621,door Identified as Being in Configuration Not Consistent W/Bechtel Design Drawings Due to Lack of Knowledge of HELB Requirements for Area |
- on 900621,door Identified as Being in Configuration Not Consistent W/Bechtel Design Drawings Due to Lack of Knowledge of HELB Requirements for Area
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000245/LER-1990-011-01, :on 900720,Tech Spec Fire Door Found Blocked Open & Unguarded by Fire Watch.Caused by Personnel Error. Personnel Cautioned to Be Aware of Potential for Impacting Tech Spec Barrier Requirements |
- on 900720,Tech Spec Fire Door Found Blocked Open & Unguarded by Fire Watch.Caused by Personnel Error. Personnel Cautioned to Be Aware of Potential for Impacting Tech Spec Barrier Requirements
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) | | 05000423/LER-1990-011, :on 900330,manual Reactor Trip Initiated Due to Anticipated Turbine Trip from Loss of Condenser Vacuum. Caused by Failure to Collect Debris from Manual Screen Washing.Elbow Replaced & Screen Wash Restored |
- on 900330,manual Reactor Trip Initiated Due to Anticipated Turbine Trip from Loss of Condenser Vacuum. Caused by Failure to Collect Debris from Manual Screen Washing.Elbow Replaced & Screen Wash Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000336/LER-1990-012-02, :on 900827,automatic Reactor Trip Occurred During Bypass Switch Operations.Caused by Operator Error. Procedure Sp 2601D Revised to Incorporate Separate Section on Performing Calibrs |
- on 900827,automatic Reactor Trip Occurred During Bypass Switch Operations.Caused by Operator Error. Procedure Sp 2601D Revised to Incorporate Separate Section on Performing Calibrs
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000245/LER-1990-012-01, :on 900813,determined That hi-hi Trip Settings on Both Offgas Instrument Drawers Set in Nonconservative Direction & Exceeded Tech Spec 3.8.B.1.Caused by Failure to Recognize Significance of Response Factor |
- on 900813,determined That hi-hi Trip Settings on Both Offgas Instrument Drawers Set in Nonconservative Direction & Exceeded Tech Spec 3.8.B.1.Caused by Failure to Recognize Significance of Response Factor
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) | | 05000423/LER-1990-012, :on 900406,review of Steam Generator Blowdown Monitor High Radiation Alarm Setpoint Revealed That Setpoint Was Nonconservative.Caused by Administrative Deficiency. Correct Setpoint Installed |
- on 900406,review of Steam Generator Blowdown Monitor High Radiation Alarm Setpoint Revealed That Setpoint Was Nonconservative.Caused by Administrative Deficiency. Correct Setpoint Installed
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000245/LER-1990-013, :on 900806,standby Gas Treatment Sys Initiation Occurred Due to Inadvertent de-energization of Power Supply to Channel 2 Process Radiation Monitoring Sys.Power Restored to Channel 2 & Initiation Trip Logic Reset |
- on 900806,standby Gas Treatment Sys Initiation Occurred Due to Inadvertent de-energization of Power Supply to Channel 2 Process Radiation Monitoring Sys.Power Restored to Channel 2 & Initiation Trip Logic Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000423/LER-1990-013, :on 900416,manual Reactor Trip Occurred Due to Imminent Loss of Condenser Vacuum.Caused by Inadequate Administrative Guidance.Personnel Instructed to Closely Monitor Trash Rack Water Levels |
- on 900416,manual Reactor Trip Occurred Due to Imminent Loss of Condenser Vacuum.Caused by Inadequate Administrative Guidance.Personnel Instructed to Closely Monitor Trash Rack Water Levels
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000336/LER-1990-014-02, :on 901010,main Steam Safety Valve Setpoint Drift Discovered During as-found Simmer Test |
- on 901010,main Steam Safety Valve Setpoint Drift Discovered During as-found Simmer Test
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000245/LER-1990-014-01, :on 900907,inconsistency Between Procedural & Design Parameters Associated W/Lpci HX Flow Rates Identified.Caused by Inadequate Evaluation of Original Plant Design Documentation |
- on 900907,inconsistency Between Procedural & Design Parameters Associated W/Lpci HX Flow Rates Identified.Caused by Inadequate Evaluation of Original Plant Design Documentation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000423/LER-1990-014, :on 900519,manual Reactor Trip Initiated as Result of Anticipated Turbine Trip Due to Condenser Vacuum. Caused by Design Deficiency in That Traveling Screen Capacity Inadequate.Traveling Screen Modified |
- on 900519,manual Reactor Trip Initiated as Result of Anticipated Turbine Trip Due to Condenser Vacuum. Caused by Design Deficiency in That Traveling Screen Capacity Inadequate.Traveling Screen Modified
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000423/LER-1990-015, :on 900512,feedwater Isolation Occurred While Opening Msivs.Caused by MSIV 2 Opening Faster than Other Msivs,Resulting in Swell in Steam Generator 2.Steam Generator Level Restored to Normal |
- on 900512,feedwater Isolation Occurred While Opening Msivs.Caused by MSIV 2 Opening Faster than Other Msivs,Resulting in Swell in Steam Generator 2.Steam Generator Level Restored to Normal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000336/LER-1990-015, :on 900919,unit Experienced Inadvertent Isolation of Containment Purge Valves.On 900920,unit Experienced Actuation of SI Actuation Sys.Caused by Operator Error.Technician Counseled |
- on 900919,unit Experienced Inadvertent Isolation of Containment Purge Valves.On 900920,unit Experienced Actuation of SI Actuation Sys.Caused by Operator Error.Technician Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000336/LER-1990-015-02, :on 900919,containment Purge Valves 2-AC-4, 2-AC-5,2-AC-6 & 2-AC-7 Inadvertently Isolated |
- on 900919,containment Purge Valves 2-AC-4, 2-AC-5,2-AC-6 & 2-AC-7 Inadvertently Isolated
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | | 05000245/LER-1990-015-01, :on 900914,reactor Scram Occurred on Low Reactor Water Level After Feedwater Regulating Valves Began to Close |
- on 900914,reactor Scram Occurred on Low Reactor Water Level After Feedwater Regulating Valves Began to Close
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000336/LER-1990-016, :on 901009,inadvertent ESAS Actuation of Containment Purge Isolation Sys Occurred.Caused by Loose Ground Wire in Control Room Cabinet S14D.Ground Wire Termination Tightened |
- on 901009,inadvertent ESAS Actuation of Containment Purge Isolation Sys Occurred.Caused by Loose Ground Wire in Control Room Cabinet S14D.Ground Wire Termination Tightened
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000336/LER-1990-016-02, :on 901009,inadvertent ESAS Actuation Occurred in Violation of Tech Specs |
- on 901009,inadvertent ESAS Actuation Occurred in Violation of Tech Specs
| 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)(i) |
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