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. November 13, 1990 W. T. cotue i
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'U.S. Nuclear Regulatory Commission Mail. Station P1-137 Washington, D.C.
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' Attention: Document Control Desk 3
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- - Gentlemen:
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SUBJECT: Grand Gulf Nuclear Station l
Unit 1 Docket No. 50-416 l
License No. NPF-29
' Containment Cooling System Isolation On High Radiation Level LER 90-020 I
AECM-90/0193 s
Attached is. Licensee Event Report (LER)90-020 which is a final report.
Yours truly, w f~~~C*w WTC/JS:cg Attachment
- cc: Mr. D'.-C. Hintz (w/a)
Mr. R. B. McGehee (w/a))
Mr. N. S. Reynolds. (w/a
. Mr. H.. L. Thomas (w/o)
' Mr. H. 0. Christensen (w/a)
Mr. Stewart D. Ebneter (w/a)
Regional Administrator U.S. Nuclear Regulatory Commission Region 11 101.Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. L. L. Kintner, Project Manager (w/a)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 11D21 Washington, D.C.
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Attachment to AECM-90/0193 U 5. NUCLE AR REGULATORY COMMIS$lON NXC Fors,386.,
APPROVED OMS NO 3160 0104 LICENSEE EVENT REPORT (LER)
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REPORT DATE 17)
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On October 16, 1990, two containment vent isolation dampers isolated on a high radiation level signal received when the steam separator was being lifted from the reactor vessel.
Radiation Monitor (EIIS Code: IL) D17-K609 tria circuits actuated, causing the containment vent exhaust inboard and outaoard isolation dampers to close.
Integrated Operating Instruction 03-1-01-5, Refueling, has been changed to anticipate isolation of the containment vent exhaust dampers as a preplanned evolution.
The Containment Cooling System and Subsystems functioned as designed when radiation levels reached the trip level setpoints, i
LER9020/SCMPFLR - 3 Ng 3
Attachment to AECM-90/0193 bdC Penn Egg U.S. feUCLEA17.BOULAfDmV Comewsmoose UCENSEE EVENT REPORT (LER) TEXT CONTINUATION
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Reportable Occurrence On.0ctober.16, 1990, two containment vent isolation dampers isolated on a high radiation level signal received when the steam saparator was being lifted from the reactor vessel. This event is considered an Engineered Safety Feature (ESF) automatic actuation and is
- reportedpursuantto50.73(a)(2)(iv).
B.
Initial Condition The plant was in Mode 5, Refueling, at the time of the event.
C.
Description of Occurrc-3 On_ October 16,'1990, during the steam separator lift from the reactor vessel to the storage area, Radiation Monitor (EIIS Code: IL)
D17-K609. trip circuits actuated, causing the Containment Cooling System (EIIS Code: VG) vent exhaust inboard-and outboard isolation dampers.M41-F034 and M41-F035 to close on a high radiation level signal. 'The radiation emitted during the lift of the separator was a
" controlled source" being monitored by Health Physicists on the refueling floor, and not an effluent release.
Operators in the Control Room verified that dampers M41-F034 and M41-F035 had, in fact, isolated and recorded the actuation in the Control Room Log Book. They immediately notid ed the refueling floor of the isolation and confirmed that Health physics personnel were present during this evolution to take the' required radiological readings.
The separator was placed into the storage pric alarms cleared, and the system restored to normal.
.D.
Apparent Cause The Containment Cooling System is equipped with redundant isolation dampers (M41-F034 and M41-F035) that prevent airborne contaminants from escaping to the environment following a Loss of Coolant Accident (LOCA).
The radiation monitoring portion of the system is designed to detect, measure, indicate, and record levels of radiation to ensure that the release of radioactivity to unrestricted areas is within permissible limits.
Four radiation detector units for the containment and drywell vent exhaust plenum are located in the duct upstream of the isolation dampers to detect and measure radiation level outputs.
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,nn, During previous outages, the separator was successfully lifted and set into the storage area, without causing an isolation. The plant directive controlling the removal of the separator alerted operators of
. the possibility of receiving radiation' alarms; however, it did not warn operators that an isolation could occur if radiation levels reached the trip circuit setpoints. Operators did not antici) ate that the Containment Cooling System would isolate.during tie separator lift, since it had not isolated during other previous outages.
E.
Supplemental Corrective Actions Integrated Operating Instruction 03-1-01-5, Refueling, has been changed to anticipate. isolation of the containment vent exhaust dampers as.part of a preplanned evolution during future separator lifts.
F.
Safety Assessment
The Containment Cooling System's instrumentation and control logics functioned as required when radiation levels approached the design trip setpoints, Q,"" '" '
LER9020/SCMPFLR - 5
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| | | Reporting criterion |
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| 05000416/LER-1990-001, :on 900112,determined That Tech Spec Reactor Coolant Cooldown Rate Limit of 100 Degrees F Exceeded in Reactor Bottom Head Drain Pipe.Caused by Programmatic Deficiencies.Incident Rept Form Improved |
- on 900112,determined That Tech Spec Reactor Coolant Cooldown Rate Limit of 100 Degrees F Exceeded in Reactor Bottom Head Drain Pipe.Caused by Programmatic Deficiencies.Incident Rept Form Improved
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1990-002, :on 900124,discovered That Div II Solenoid Associated W/Secondary Containment Isolation Valve Did Not Operate During Quarterly Valve Stroke Time Tests.Caused by Procedure Inadequacy.Procedures Changed |
- on 900124,discovered That Div II Solenoid Associated W/Secondary Containment Isolation Valve Did Not Operate During Quarterly Valve Stroke Time Tests.Caused by Procedure Inadequacy.Procedures Changed
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1990-003, :on 900215,identified Potential Single Failure Scenario That Could Result in Unavailability of Both Core Spray Sys for Long Term post-LOCA Core Cooling.Detailed Heatup Evaluation Performed for Power Bundle |
- on 900215,identified Potential Single Failure Scenario That Could Result in Unavailability of Both Core Spray Sys for Long Term post-LOCA Core Cooling.Detailed Heatup Evaluation Performed for Power Bundle
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000416/LER-1990-003-01, Corrected LER 90-003-01:on 900215,potential Single Failure Scenario Identified That Could Result in Unavailability of Both Core Spray Sys for post-LOCA Core Cooling.Detailed Heatup Evaluation Performed | Corrected LER 90-003-01:on 900215,potential Single Failure Scenario Identified That Could Result in Unavailability of Both Core Spray Sys for post-LOCA Core Cooling.Detailed Heatup Evaluation Performed | | | 05000416/LER-1990-004, :on 900406,discovered That Surveillance Procedure for Verifying Air Pressure in Containment Airlock Seal Flasks Did Not Fully Implement Tech Spec 4.6.1.3.d.2. Caused by Deficient Procedures |
- on 900406,discovered That Surveillance Procedure for Verifying Air Pressure in Containment Airlock Seal Flasks Did Not Fully Implement Tech Spec 4.6.1.3.d.2. Caused by Deficient Procedures
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1990-005, :on 900406,discovered That Current Surveillance Practices for Stroke Testing Fresh Air Makeup Intake Valves Could Have Resulted in Unfiltered Pathway.Administrative Controls Placed on Valves |
- on 900406,discovered That Current Surveillance Practices for Stroke Testing Fresh Air Makeup Intake Valves Could Have Resulted in Unfiltered Pathway.Administrative Controls Placed on Valves
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000416/LER-1990-006, :on 900502,review of Effluent Sample Analysis Revealed That Turbine Bldg Ventilation Exhaust Had Not Been Analyzed Exceeding Time Limit.Caused by Personnel Error. Training & Counseling Conducted |
- on 900502,review of Effluent Sample Analysis Revealed That Turbine Bldg Ventilation Exhaust Had Not Been Analyzed Exceeding Time Limit.Caused by Personnel Error. Training & Counseling Conducted
| | | 05000416/LER-1990-007, :on 900516,discovered That Actions Taken for Inoperable Reactor Water Level Transmitter Not Adequate to Comply W/Requirements for Tech Spec 3.3.2.Caused by Personnel Error.Meetings Held W/Personnel |
- on 900516,discovered That Actions Taken for Inoperable Reactor Water Level Transmitter Not Adequate to Comply W/Requirements for Tech Spec 3.3.2.Caused by Personnel Error.Meetings Held W/Personnel
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1990-008, :on 900521,discovered That Fire Rated Door Required by Tech Spec 3/4.7.7 Not Designated as Tech Spec Door in Ssurveillance Procedures.Caused by Incorrect Interpretation of Tech Spec Requirements |
- on 900521,discovered That Fire Rated Door Required by Tech Spec 3/4.7.7 Not Designated as Tech Spec Door in Ssurveillance Procedures.Caused by Incorrect Interpretation of Tech Spec Requirements
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1990-009, :on 900526,nonlicensed Personnel Performed Step Out of Sequence During Breaker rack-out & Caused LPCS Pump Breaker to Close.Operator Involved Counseled on Failure to Adhere to Breaker Operation Procedure |
- on 900526,nonlicensed Personnel Performed Step Out of Sequence During Breaker rack-out & Caused LPCS Pump Breaker to Close.Operator Involved Counseled on Failure to Adhere to Breaker Operation Procedure
| | | 05000416/LER-1990-010-01, :on 900706,error Discovered in Evaluation Used to Demonstrate Adequacy of Svc Water Flow to HPCS Pump Room Cooler.Matls Nonconformance Rept Generated to Document Discrepancy |
- on 900706,error Discovered in Evaluation Used to Demonstrate Adequacy of Svc Water Flow to HPCS Pump Room Cooler.Matls Nonconformance Rept Generated to Document Discrepancy
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000416/LER-1990-011-01, :on 900724,reactor Tripped on High Reactor Water Level W/Reactor Power in Process of Being Reduced in Attempt to Control Turbine Pump B Oscillations.Caused by Malfunction of Controller.Controller Calibr |
- on 900724,reactor Tripped on High Reactor Water Level W/Reactor Power in Process of Being Reduced in Attempt to Control Turbine Pump B Oscillations.Caused by Malfunction of Controller.Controller Calibr
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1990-013, :on 900725,instrument Cable from B Detector Disconnected Rather than C Detector While Performing Maint on Monitoring Sys.Caused by Personnel Error.Personnel Counseled on Methods for Self Verification |
- on 900725,instrument Cable from B Detector Disconnected Rather than C Detector While Performing Maint on Monitoring Sys.Caused by Personnel Error.Personnel Counseled on Methods for Self Verification
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1990-014, :on 900810,retest Not Performed Prior to Returning Secondary Containment Isolation Valve to Operable Status.Caused by Programmatic Weaknesses in Administrative Controls.Plant Procedures Changed |
- on 900810,retest Not Performed Prior to Returning Secondary Containment Isolation Valve to Operable Status.Caused by Programmatic Weaknesses in Administrative Controls.Plant Procedures Changed
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1990-015, :on 900823,discovered That Fire Rated Assembly Penetration Not Properly Sealed.Cause Not Determined. Nonconformance Rept Written & Work Order Initiated to Seal Penetration |
- on 900823,discovered That Fire Rated Assembly Penetration Not Properly Sealed.Cause Not Determined. Nonconformance Rept Written & Work Order Initiated to Seal Penetration
| | | 05000416/LER-1990-016-01, :on 900912,cooling Water Outlet Valve Failed to Stroke to Full Open Position & Div II Purge Sys Declared Inoperable |
- on 900912,cooling Water Outlet Valve Failed to Stroke to Full Open Position & Div II Purge Sys Declared Inoperable
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1990-017, :on 900916,reactor Scram Occurred Due to Loss of Balance of Plant Busses |
- on 900916,reactor Scram Occurred Due to Loss of Balance of Plant Busses
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1990-018-01, :on 901008,secondary Containment Doors Found Open During Refueling Outage |
- on 901008,secondary Containment Doors Found Open During Refueling Outage
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1990-019-01, :on 901014,during Refueling Outage Four,Three Events Occurred in Which Same Power Supply Breaker Inadvertently Opened |
- on 901014,during Refueling Outage Four,Three Events Occurred in Which Same Power Supply Breaker Inadvertently Opened
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1990-020-01, :on 901016,containment Cooling Sys Found on High Radiation Level |
- on 901016,containment Cooling Sys Found on High Radiation Level
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1990-021-01, :on 901024,uncontrolled Lowering of Fuel Bundle Occurred |
- on 901024,uncontrolled Lowering of Fuel Bundle Occurred
| | | 05000416/LER-1990-022, :on 901026,loss of Shutdown Cooling Due to Inadequate Procedure |
- on 901026,loss of Shutdown Cooling Due to Inadequate Procedure
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000416/LER-1990-022-01, :on 901026,breaker 52-15309,which Supplies Power to Common Suction Isolation Valve E12-F008,closed, Tripping RHR Pump B & Isolating Shutdown Cooling Sys.Caused by Inadequate Procedure.Standing Order Issued |
- on 901026,breaker 52-15309,which Supplies Power to Common Suction Isolation Valve E12-F008,closed, Tripping RHR Pump B & Isolating Shutdown Cooling Sys.Caused by Inadequate Procedure.Standing Order Issued
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000416/LER-1990-023, :on 901105,shutdown Cooling Isolation Occurred Due to Blown Fuse |
- on 901105,shutdown Cooling Isolation Occurred Due to Blown Fuse
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000416/LER-1990-024, :on 901114,standby Fresh Air Unit Actuation Occurred Due to Inadequate Test Instruction |
- on 901114,standby Fresh Air Unit Actuation Occurred Due to Inadequate Test Instruction
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1990-025, :on 901122,actuation of Reactor Protection Sys Occurred During Surveillance of Reactor Mode Switch.Caused by Diminishing Power Supply of Test Equipment.Evaluation Will Be Conducted |
- on 901122,actuation of Reactor Protection Sys Occurred During Surveillance of Reactor Mode Switch.Caused by Diminishing Power Supply of Test Equipment.Evaluation Will Be Conducted
| | | 05000416/LER-1990-026, :on 901124,manual Scram Inserted Following Lockup of Rod Pattern Control Sys During Reactor Startup. Caused by Transient of Reactor Water Level Attributed to Open Drain Valves.Startup Procedure Amended |
- on 901124,manual Scram Inserted Following Lockup of Rod Pattern Control Sys During Reactor Startup. Caused by Transient of Reactor Water Level Attributed to Open Drain Valves.Startup Procedure Amended
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1990-028, :on 901210,ESF,RPS & ECCS Hpsc Actuated, Resulting in Reactor Scram from Full Power.Caused by Failed Solder Joint in Instrument Air Sys & Leaking Root Valve. Joint Reinspected & Procedures Revised |
- on 901210,ESF,RPS & ECCS Hpsc Actuated, Resulting in Reactor Scram from Full Power.Caused by Failed Solder Joint in Instrument Air Sys & Leaking Root Valve. Joint Reinspected & Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1990-029, :on 901218,reactor Protection Sys Actuation Occurred,Resulting in Automatic Plant Shutdown Due to Reactor Feedwater Pump Trip.Caused by Air Supply Valve Not Fully Open.Air Supply Valve Replaced |
- on 901218,reactor Protection Sys Actuation Occurred,Resulting in Automatic Plant Shutdown Due to Reactor Feedwater Pump Trip.Caused by Air Supply Valve Not Fully Open.Air Supply Valve Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation |
|