LER-1981-105, Forwards LER 81-105/01T-0.Detailed Event Analysis Encl |
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Dear Mr. O'Reilly:
Please find attached Reportable Occurrence Report R0.v1/81-105. This report concerns Technical Specification 3.4.7.2; " Reactor coolant system leakage shall be limited to...". This incident was considered to be of no significane with respect to the health and safety of the public.
Ve truly yours,
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William O. Parker, Jr.
PBN/pw Attachment cc: Director Mr. Bill Lavallee Office of Management & Program Analysis Nuclear Safety Analysis Center U. S. Nuclear Regulatory Commission Post Office Box 10412 Washington, D. C.
20555 Palo Alto, CA 94303 Ms. M. J. Graham Resident Inspector - NRC McGuire Nuclear Station i
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0108040349 810724 PDR ADOCK 05000369 S
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McGUIRE NUCLEAR STATION I
REPORTABLE OCCURRENCE Report Number:
81-105 l
Report Date: July 24, 1981 i
i Occurrence Date:
July 10, 1981 i
Facility: McGuire Unit 1, Cornelius, N. C.
I Identification of Occurrence: A reactor coolant leak.was caused when technicians
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were placing the resistance temperature detector bypass manifold in service.
Conditions Prior to Occurrence: Mode 3, prior to initial criticality.
I Description of Occurrence: On July 9, 1981 Operations isolated and drained the cold leg portion of the "A" loop resistance temperature detector (RTD) manifold.
1 The inlet and outlet valves were closed and red tagged. The vent and drain valves were opened but not tagged. An R&R (removal and restoration) form was filled out i
by the operator detailing the isolation process and the required sequence of i
restoration. This work was done in preparation for the replacement of a defective RTD.
Instrument and Electrical (IAE) technicians completed the installation of the RTD on the same d.ay except that the wiring was temporarily connected for l
testing.
i The following day, another IAE technician was assigned to complete the wiring.
l After he had finished, his supervisor instructed him to "get the red tags cleared."
l The supervisor meant for the technician to take the red tag stubs to Operations l
for clearance.
The technician interpreted the instruction to mean that he'per-sonally should remove the tags and cut in the man Hold.
He entered containment, removed the tags from the inlet and outlet valves and attempted to open the inlet valve. The valve was difficult to move, so the technician requested assistance j
from his supervisor who assigned a second technician to assist him. Neither i
technician noticed the open vent and drain valves. When the inlet valve was cracked otan, steam blew out through the open vent and drain valves, burning the l
second technician's leg.
The technicians lef t ths area inanediately and another technician in the area called the control room and reported a leak on the "A" l
loop RTD manifold.
Since the operators could not assess the amount of the leak, they started cooling down per Technical Specification 3.4.7.2 (1615, July 10, 1981). At 1713 hours0.0198 days <br />0.476 hours <br />0.00283 weeks <br />6.517965e-4 months <br />, an Operations Engineer wearing a heat protection suit and an air pack managed to isolate the leak by closing the vent and drain valves on the manifold..
Apparent Cause of Occurrence:
The IAE technicians misunderstood the instructions of the IAE supervisor and attempted to do work for which.they were neither trained or qualified by station policy.
They did not realize that a process pipe such as the cold leg RTD bypass manifold would have vent and drain valves that must be closed.
Analysis of Occurrence:
IAE technicians are allowed to cycle only instrument valves and root valves.
Process valves are controlled by Operations or Chemistry.
Similarly, IAE technicians are allowed to tag and clear tags on instrument and i
root valves only, while Operations and Chemistry tag all other equipment. A more i
1 Report Number 81-105 Page 2 l
experienced technician would have realized that IAE was not allowed to operate l
I the RTD bypass manifold valves. He would also have recognized the red tags as belonging to Operations.
Since instrument lines do not usually use valves on vents and drains, the technicians did not look for vent and drain valves on the manifold.
l An operator, assigned to cut in the RTD bypass manifold, would have been guided by the R&R form.
He would also have been familiar with the vents and drains used on process piping.
The IAE supervisor should have realized when the first technician called for assistance in opening the valves that a serious error was being made.
Safety Analysis
Although the amount of the leak could not be determined, the l
capacity of the positive displacement pump was never seriously challenged even during the cool down.. All of the safety injection pumps were available to main-tain pressure and volume of the reactor coolact system had they been needed.
In addition, only new fuel was in the core at the time of the incident.
For these reasons the incident had no effect on the health and safety of the public.
Corrective Action
The immediate corrective action was to isolate the leaks j
by closing the manifold vent and drain valves.
IAE technicians will receive special ia.structions on which valves they are allowed to operate and the entire tagging procedure.
IAE supervisors will be counseled to be more careful in giving instructions to less experienced technicians.
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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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