LER-1981-173, Forwards LER 81-173/03L-0.Detailed Event Analysis Encl |
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su.. e. m c,0, Mr. J. P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: McGuire Nuclear Station Unit 1 Docket No. 50-369
Dear Mr. O'Reilly:
Please find attached Reportable Occurrence Report R0-369/81-173. This report concerns T.S.3.6.3, "The Containment Isolation Valves Specified in Table 3.6-2 Shall be Operable.
This incident was considered to be of no signifi-cance with respect to the health and safety of the public.
Very truly yours, 9a/
l/N x th. A,/y William O. Parker, Jr.
PBN/sch Attachment i
cc: Director Records Center Office of Managment and Program Analysis Institute of Nuclear Power Operations U. S. Nuclear Regulatory Commission 1820 Water Place l
Washington, D. C.
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Mr. P. R. Bemis N
Sr. Resident Inspector-NRC
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r-r DUKE POWER COMPANY McGUIRE NUCLEAR STATION REPORTABLE OCCURRENCE REPORT NO.81-173 REPORT DATE: November 30, 1981 FACILITY: McGuire Unit 1, Cornelius, NC IDENTIFICATION:
The Inadvertant Opening of Steam Generator 1B Main Feedwater to Auxiliary Feedwater Nozzle Isolation Valve.
INTRODUCTION
On October 30, control room personnel tried to open S/G 1B main feed-water nozzle isolation valve but the valve failed to open and a ground fault indica-tion was received. A check of the motor winding readings at the motor control center determined that the motor was burned-up.
Since the actuator for this valve is a Ro-tork, the actuator had to be removed from the valve to replace the burned-up motor.
The valve was in its safety position, closed, when Technicians began removing the ac-tuator from the valve. A gag was placed on the stem of the valve to prevent the valve from opening when the actuator was removed. The bolts on the actuator were loosened, and the Technicians began to screw the actuator off the stem using the handwheel. When the handwheel was first turned, it was turned in the wrong direction and lifted the
. disc off the seat enough to allow system pressure, approximately 1140 psig, to com-pletely open the valve.
The gag failed to prevent the valve from opening. Control room personnel were notified that the valve had opened at 0246 on October 31.
Prior to the incident, Unit 1 was in mode 3, Hot Standby. Pursuant to Technical Specifica-tion 3.6.3, the plant entered into an action statement; therefore, this is a reportable incident. According to the action statement, plant personnel had four hours to close the valve. Mechanical maintenance personnel were notified to jack the valve closed.
At 0431, maintenance personnel had successfully gagged the valve closed.
The actuator was repaired, and the valve was returned to service on November 1, 1981.
EVALUATION: Af ter the reactor trip on October 30, attempts to open the valve to obtain normal feedwater alignment failed.
It was determined that the motor was burned-up, and thus the actuator (Rotork, Model 30 NAX1) would have to be removed from the valve.
Since the valve was in its safety position, closed, it was necessary to keep the valve in this position when its actuator was removed, and thus a gag was placed on the stem.
This gag consisted of a modified C-Clamp (pieces of angle iron are welded to the jaws of the clamp).
When Technicians attempted to screw the actuator off the valve stem using the handwheel, they turned the wheel in the wrong direction which allowed the disc to lift off its seat.
The system pressure of approximately 1140 psig easily caused the valve to open.
Initially turning the valve the wrong way could have also caused i
the gag to loosen its hold on the stem.
Once the valve began to open, the gag could not hold it in place.
It is possible that the gag failed to hold due to being instal-led incorrectly or due to being disturbed while removing the actuator. When the hand-wheel is turned in the closed direction after the valve reaches its closed position, the actuator will come off the stem.
It is possible that the gag may not have held the valve closed under this condition, but doubtful. Therefore it was the initial wrong directional turn of handwheel that caused the valve to open.
CORRECTIVE ACTION
In accordance with the action statement of Technical Specification 3.6.3, the valve had to be closed within four hours. After several unsuccessful at-tempts were made to close the valve by hand, the valve was jacked closed and gagged.
While the valve was gagged in the closed position, the actuator was repaired and rein-stalled.
Report No.81-173 Page 2 VERIFICATION: The position of the gagged valve could be verified by the valve stem's position. After the actuator was repaired and returned to the valve, it was verified that the valve worked properly in accordance with Technical Specifications by the re-test program using the appropriate procedure.
SAFETY ANALYSIS
The plant was in hot standby at the time of the occurrence and the valve was returned to the closed position in one hour and forty-five minutes. During the time of this incident, nothing happened which required the closing of this valve.
Station personnel acted quickly to return the valve to its safety position.
The health and safety of the public were unaffected by this incident.
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| 05000369/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000369/LER-1981-001-03, /03L-0:on 810129-0212,several Fire Detection Instruments Were Inoperable for Periods Exceeding 1-h. Caused by Const in Area.Fire Watches & Patrols Established | /03L-0:on 810129-0212,several Fire Detection Instruments Were Inoperable for Periods Exceeding 1-h. Caused by Const in Area.Fire Watches & Patrols Established | | | 05000369/LER-1981-002-01, /01T-0:on 810130,during Test,Vent Valve VX-41 & Containment Isolation Valve XV-40 Found Open to Atmosphere, in Violation of Tech Spec 4.9.4.1.Caused by Lack of Valve Checklist & Lack of Periodic Test.Valves Closed | /01T-0:on 810130,during Test,Vent Valve VX-41 & Containment Isolation Valve XV-40 Found Open to Atmosphere, in Violation of Tech Spec 4.9.4.1.Caused by Lack of Valve Checklist & Lack of Periodic Test.Valves Closed | | | 05000369/LER-1981-002, Forwards LER 81-002/01T-0 | Forwards LER 81-002/01T-0 | | | 05000369/LER-1981-003-03, /03L-0:on 810129,conventional Waste Plant Discharge Flow Monitor Found Inoperable.Caused by Inaccurate Flow Readings Due to Inability of Instrument to Measure Continuous Discharge Flow.New Equipment Ordered | /03L-0:on 810129,conventional Waste Plant Discharge Flow Monitor Found Inoperable.Caused by Inaccurate Flow Readings Due to Inability of Instrument to Measure Continuous Discharge Flow.New Equipment Ordered | | | 05000369/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000369/LER-1981-004-03, /03L-0:on 810129-0212,various Firestops & Fire Doors Found Inoperable for Periods Exceeding 1-h.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrols Established | /03L-0:on 810129-0212,various Firestops & Fire Doors Found Inoperable for Periods Exceeding 1-h.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrols Established | | | 05000369/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000369/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000369/LER-1981-005-03, /03L-0:on 810202,power Supply to Both Excore Range Monitors Was Interrupted.Caused by Maint Personnel Cutting Off Power to Investigate Steam Generator Status Lights & lo-lo Level Alarms.Personnel Instructed | /03L-0:on 810202,power Supply to Both Excore Range Monitors Was Interrupted.Caused by Maint Personnel Cutting Off Power to Investigate Steam Generator Status Lights & lo-lo Level Alarms.Personnel Instructed | | | 05000369/LER-1981-006-03, /03L-0:on 810202,leaking Seal Discovered on RHR Pump.Caused by Improperly Loaded Spring Which Holds Seal Faces Together.Seal Replaced | /03L-0:on 810202,leaking Seal Discovered on RHR Pump.Caused by Improperly Loaded Spring Which Holds Seal Faces Together.Seal Replaced | | | 05000369/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000369/LER-1981-007-03, /03L-0:on 810203,RHR Sys Train a Was Declared Inoperable.Caused by Draining Essential Header to Repair Leaking Valves in Nuclear Svc Water Sys.Valves Repaired & Train a Returned to Svc | /03L-0:on 810203,RHR Sys Train a Was Declared Inoperable.Caused by Draining Essential Header to Repair Leaking Valves in Nuclear Svc Water Sys.Valves Repaired & Train a Returned to Svc | | | 05000369/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000369/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000369/LER-1981-008-03, /03L-0:on 810203,control Area Ventilation Sys Train a Declared Inoperable.Caused by Draining Essential Header to Repair Leaking Valves in Nuclear Svc Water Sys. Valves Repaired & Train a Returned to Svc | /03L-0:on 810203,control Area Ventilation Sys Train a Declared Inoperable.Caused by Draining Essential Header to Repair Leaking Valves in Nuclear Svc Water Sys. Valves Repaired & Train a Returned to Svc | | | 05000369/LER-1981-009-03, /03L-0:on 810205,flow to Reactor Coolant Loops Was Momentarily Lost.Caused by Failure of Throttle Valve to Close Due to Loosening of Nut Holding Linkage to Valve Stem. Linkage Repositioned & Nut Tightened | /03L-0:on 810205,flow to Reactor Coolant Loops Was Momentarily Lost.Caused by Failure of Throttle Valve to Close Due to Loosening of Nut Holding Linkage to Valve Stem. Linkage Repositioned & Nut Tightened | | | 05000369/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Encl | Forwards LER 81-009/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000369/LER-1981-010-03, /03L-0:on 810207,total RHR Flow Exceeded Tech Specs.Caused by Air Line Supplying Actuator on RHR Valve Breaking,Allowing Valve to Fail Open.Rhr Flow Reset.Rigid Air Supply Lines to Be Replaced W/Flexible Lines | /03L-0:on 810207,total RHR Flow Exceeded Tech Specs.Caused by Air Line Supplying Actuator on RHR Valve Breaking,Allowing Valve to Fail Open.Rhr Flow Reset.Rigid Air Supply Lines to Be Replaced W/Flexible Lines | | | 05000369/LER-1981-011-03, /03T-0:on 810210,both Pressure Seals on Inner Door of Lower Personnel Air Lock Failed.Caused by Hole in One Seal & Bubble in Other Seal.Seals Replaced & Returned to Manufacturer | /03T-0:on 810210,both Pressure Seals on Inner Door of Lower Personnel Air Lock Failed.Caused by Hole in One Seal & Bubble in Other Seal.Seals Replaced & Returned to Manufacturer | | | 05000369/LER-1981-011, Forwards LER 81-011/03T-0 | Forwards LER 81-011/03T-0 | | | 05000369/LER-1981-012-03, /03T-0:on 801211,isolation Valve NV-250 Found Not Verified Closed Under Administrative Control Per Tech Spec. Caused by Lack of Signoff Step in Daily Surveillance Items. Procedure Change Incorporated | /03T-0:on 801211,isolation Valve NV-250 Found Not Verified Closed Under Administrative Control Per Tech Spec. Caused by Lack of Signoff Step in Daily Surveillance Items. Procedure Change Incorporated | | | 05000369/LER-1981-012, Forwards LER 81-012/03T-0 | Forwards LER 81-012/03T-0 | | | 05000369/LER-1981-013-03, /03L-0:on 810212,radiation Detectors EMF 33,35,36, 37,38,39 & 40 Were Declared Inoperable Due to Loss of Sample Flows.Caused by Individual Nonrelated Failures of Each Emf. Repairs Performed & EMFs Declared Operable | /03L-0:on 810212,radiation Detectors EMF 33,35,36, 37,38,39 & 40 Were Declared Inoperable Due to Loss of Sample Flows.Caused by Individual Nonrelated Failures of Each Emf. Repairs Performed & EMFs Declared Operable | | | 05000369/LER-1981-013, Forwards LER 81-013/03L-0.Detailed Event Analysis Encl | Forwards LER 81-013/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-014, Forwards LER 81-014/03L-0 | Forwards LER 81-014/03L-0 | | | 05000369/LER-1981-014-03, /03L-0:on 810212,while in Mode 6,control Room Received High Groundwater Alarm.Caused by Localized Temporary High Groundwater Level.Proper Surveillance Conducted & Alarm Was Cleared within 2 Days | /03L-0:on 810212,while in Mode 6,control Room Received High Groundwater Alarm.Caused by Localized Temporary High Groundwater Level.Proper Surveillance Conducted & Alarm Was Cleared within 2 Days | | | 05000369/LER-1981-015-03, /03L-0:on 810213,various Firestops & Fire Doors Rendered Inoperable for Periods Exceeding 1-h from 810213-27.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrols Established as Required | /03L-0:on 810213,various Firestops & Fire Doors Rendered Inoperable for Periods Exceeding 1-h from 810213-27.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrols Established as Required | | | 05000369/LER-1981-015, Forwards LER 81-015/03L-0 | Forwards LER 81-015/03L-0 | | | 05000369/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000369/LER-1981-016-03, /03L-0:on 810216,several Firestops Inadvertently Left Open W/O Fire Watches Being Posted.Caused by Omission of Stops from Maint List of Those Requiring Seals.Stops Sealed.Seals Will Be Verified Every 18 Months | /03L-0:on 810216,several Firestops Inadvertently Left Open W/O Fire Watches Being Posted.Caused by Omission of Stops from Maint List of Those Requiring Seals.Stops Sealed.Seals Will Be Verified Every 18 Months | | | 05000369/LER-1981-018, Forwards LER 81-018/03L-0.Detailed Event Analysis Encl | Forwards LER 81-018/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-018-03, /03L-0:on 810219,annunciator Alarm Indicated Loss of Sample Flow on Radiation Monitor 1-EMF-33.Monitor Vacuum Pump Internally Damaged Due to Water Inside Pump.Pump Vanes & Bearings Replaced & Water Removed | /03L-0:on 810219,annunciator Alarm Indicated Loss of Sample Flow on Radiation Monitor 1-EMF-33.Monitor Vacuum Pump Internally Damaged Due to Water Inside Pump.Pump Vanes & Bearings Replaced & Water Removed | | | 05000369/LER-1981-019-01, /01T-0:on 810306,during ESF Testing,Loss of Ac Power Was Experienced on Half of Station Security Sys.Caused by Blown Security Sys Power Inverter Fuse.Security Procedures Changed to Indicate Info Concerning Power Sys | /01T-0:on 810306,during ESF Testing,Loss of Ac Power Was Experienced on Half of Station Security Sys.Caused by Blown Security Sys Power Inverter Fuse.Security Procedures Changed to Indicate Info Concerning Power Sys | | | 05000369/LER-1981-019, Forwards LER 81-019/01T-0 | Forwards LER 81-019/01T-0 | | | 05000369/LER-1981-020, Forwards LER 81-020/03L-0.Detailed Event Analysis Encl | Forwards LER 81-020/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-020-03, /03L-0:on 810219,spurious High Radiation Alarm & Loss of Flow Alarm Sounded in Control Room on EMF-49. Personnel Cleared Radiation Alarm But Overlooked Closed Valve,Causing Loss of Flow Alarm.Monitor Repaired | /03L-0:on 810219,spurious High Radiation Alarm & Loss of Flow Alarm Sounded in Control Room on EMF-49. Personnel Cleared Radiation Alarm But Overlooked Closed Valve,Causing Loss of Flow Alarm.Monitor Repaired | | | 05000369/LER-1981-021, Forwards LER 81-021/03L-0.Detailed Event Analysis Encl | Forwards LER 81-021/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-021-03, /03L-0:on 810226,noble Gas Activity Monitor for Condenser Evacuation Sys EMF-33 Not Functioning.Caused by Excessive Amounts of Condensation in Sample Lines.Moisture Removed.Different Type of Moisture Separator to Be Used | /03L-0:on 810226,noble Gas Activity Monitor for Condenser Evacuation Sys EMF-33 Not Functioning.Caused by Excessive Amounts of Condensation in Sample Lines.Moisture Removed.Different Type of Moisture Separator to Be Used | | | 05000369/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000369/LER-1981-022-03, /03L-0:on 810301-16,various Portions of Fire Detection Sys Inoperable for Periods Exceeding 1-h.Caused by Const in Area.Fire Watches & Patrols Established as Required | /03L-0:on 810301-16,various Portions of Fire Detection Sys Inoperable for Periods Exceeding 1-h.Caused by Const in Area.Fire Watches & Patrols Established as Required | | | 05000369/LER-1981-023-03, /03L-0:on 810227-0313,various Firestops & Fire Doors Inoperable for Periods Exceeding 1-h.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrol Established as Required | /03L-0:on 810227-0313,various Firestops & Fire Doors Inoperable for Periods Exceeding 1-h.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrol Established as Required | | | 05000369/LER-1981-023, Forwards LER 81-023/03L-0 | Forwards LER 81-023/03L-0 | | | 05000369/LER-1981-024, Forwards LER 81-024/01T-0 | Forwards LER 81-024/01T-0 | | | 05000369/LER-1981-024-01, /01T-0:on 810316,Unit 1 Wedge Plates Discovered to Be Smaller than Required Size.Cause Not Stated.Calculations Reviewed to Determine Acceptance.Corrective Action Deemed Necessary.Bar Along Length of Washer Plate Added | /01T-0:on 810316,Unit 1 Wedge Plates Discovered to Be Smaller than Required Size.Cause Not Stated.Calculations Reviewed to Determine Acceptance.Corrective Action Deemed Necessary.Bar Along Length of Washer Plate Added | | | 05000369/LER-1981-025-01, /01T-0:on 810319,no Seismic Bracing or Calculations Found for 12 Reactor Bldg safety-related Electrical Cable Tray Hanger Stds.Cause Not Stated.Seismic Calculations Performed on Affected Hangers | /01T-0:on 810319,no Seismic Bracing or Calculations Found for 12 Reactor Bldg safety-related Electrical Cable Tray Hanger Stds.Cause Not Stated.Seismic Calculations Performed on Affected Hangers | | | 05000369/LER-1981-025, Forwards LER 81-025/01T-0 | Forwards LER 81-025/01T-0 | | | 05000369/LER-1981-026-03, /03L-0:on 810305,EMF Sys Panel Alarm in Control Room Indicated Malfunction of EMF-43A.Alarm Could Not Be Cleared & Control Room Outside Air Intake Gaseous Activity Monitor Inoperable.Caused by Broken Bnc Jack | /03L-0:on 810305,EMF Sys Panel Alarm in Control Room Indicated Malfunction of EMF-43A.Alarm Could Not Be Cleared & Control Room Outside Air Intake Gaseous Activity Monitor Inoperable.Caused by Broken Bnc Jack | | | 05000369/LER-1981-026, Forwards LER 81-026/03L-0.Detailed Event Analysis Encl | Forwards LER 81-026/03L-0.Detailed Event Analysis Encl | |
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