LER-1981-002, /03L-0:on 810111,auxiliary Feedwater Flow to Steam Generators Found Set Below Normal Limit.Caused by Feed Regulating Valve Stroke Limitation Implemented Under Mods Required by NUREG-0578.Restriction Removed on 810122 |
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' NRC FORM 366 U.S. NUCLEA2 REGULATORY COMMIS$10N (7 771 LICENSEE EVENT REPORT CONTROL SLOCK: l 1
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4 60 61 COCK ET NLMS E R 68 69 EVENT CATE 74 75 REPCRT DATE 40 EVENT DESCRIPTION AND PROSA8LE CONSECUENCES h
' l o_ : 21 i At 2100 on 01-11-81, it was detennined that Auxiliary Feedwater flow l
i i o,2 i I (AFW) to the steam generators was only 480 GPM. The AFW regulating l
valves were reset to obtain a flow of 750 GPM at 1610,1-12-Gl. The l
i o i., i i l io isi l AFW manual bypasses remained operable during the event. This is not I
io is i i a repetitive occurrence.
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liioil A 75% AFW feed regulating i ilve stroke limit was implemented under modi _ _
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l i 12 i I not fully verified by testing. This restriction has been removed as of I
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LER NO.
81-02 DOCKET NO.
50-317 LICENSE NO. DPR-53 EVENT DATE 01-11-81 REPORT DATE 02-10-81 ATTACHMENT EVENT DESCRIPTION AND PROBABLE CONSECUENCES (CONT'D)
At 2100 on 1-11-81, while feeding Steam Generators with the Auxiliary Feedwater System, the operator observed that he could only obtain a total flow of 480 GPM to the Steam Generators (130 GPM to ill, 350 GPM to f12) using the valve position controllers on the main control boards.
This total flow was less than the value of design flow referenced in the T.S. Bases (700 GPM total).
It was determined that the maximum valve stroke limit was too restrictive to allow design flow conditions to be reached utilizing the valve controllers alone.
These valves were limited to 757. of full stroke under an approved design modification re-lating to the " Control Grade" AFW auto-start system (as required by NUREG0578). The Shift Supervisor initiated maintenance action to reset the maximum stroke limit so that a total flow rate of 750 GPM could be achieved. This corrective action was completed at 1610 on 1-12-81.
It was subsequently detemined that the system flow capability had not been tested upon implementation of approved design modifications re-lating to the " Safety Grade" AFW auto-start system (also required by NUREG0578). However, the required flow rate with the restriction of valve opening was only required to be 460 GPM total, as per the approved design changes, which is sufficient to remove decay heat on a loss of feedwater accident. The basis for the Technical Specification refers to the AFW system design flow rate of 700 GPM which provides for decay heat removal and the capability to cooldown the plant to less than 3000F.
In con-sideration of other design features (Manual Bypasses) of the AFW system, flow rates of at least 700 GPM were attainable throughout the period l,
of valve restriction and thus public health and safety were not affected.
This is not a repetitive occurrence.
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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (CONT'D)
The cause of the reduced flow rates was determined to be the maximum open-ing setting of the AFW regulating valves. This restriction was implemented under special instructions relating to the " Control Grade" AFW auto-start system. The intent of this action was to limit the maximum flow rate of the APd system in order to prevent APA pump cav'itation on a loss of in-l strument air to the valves and to the AFW pump speed controller. The i
flow rate required to remove decay heat and maintain hot-standby con-ditions was determined to be 460 GPM. With the valve restrictions in effect, a total flow of 480 GPM was achieved. Under the specific condi-tions of this modification, no testing was required. Upon implementation of tne " Safety Grade" AFW auto-start modification, the special instructions for the " Control Grade" modification were continued in effeet.
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i The Technical Specification Bases refer to a flow requirement in excess of 700 GPM.
This number is based on the AFW system design capability to, not only remove decay heat in hot-standby, bug also additional flow capability to cooldown the plant to less than 300 F.
Only the capa-bility to remove decay heat is analyzed in the FSAR Safety Analysis.
The operators, believing the requirement to be 700 GPM, initiated cor-rect maintenance action to restore capability to greater than 700 GPM.
This action was not necessary since the actual requirement was 460 GPM l
and a flow rate of 480 GPM could be achieved. Also, the design of the AFW system includes manual bypass capabilities which could be used on cooldewn to attain the higher flow rates if required.
Calvert Cliffs Instructions refer to a requirement for verification test-ing of all safety-related modifications. Testing for non-safety related modifications is at the discretion of the responsible engineer or super-visor, and is accomplished on a as necessary basis. Since the flow restriction requirement was implemented as non-safety related, testing was not required at that time. However, on the subsequent upgrade to safety related, verification testing should have been performed, con-trary to existing instructions, the requirement was omitted and no veri-fication test was performed.
On subsequent review of this situation, it was decided to remove the 75%
restriction on AFW regulating valve stroke. This was based upon the l
installation of a safety related air supply to the subject valves which cbviates concern over loss of the normal air supply.
This corrective action has been implemented.
In addition, a memo was sent to the Engineering Department requesting that future modifications contain all special instructions necessary for implementation and that the use of cross referencing these instructions between different jobs be elimi-nated. This action provides increased assurances that a similar ccror will not occur again.
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| 05000317/LER-1981-001-01, /01T-0:on 810114,feedwater Transmitter Out of Calibr,Resulting in Erroneous Adjustments to ex-core Nuclear Instrument Channels.Transmitter Failed to Maintain Calibr. Transmitter Replaced.Cause of Shift in Calibr Not Stated | /01T-0:on 810114,feedwater Transmitter Out of Calibr,Resulting in Erroneous Adjustments to ex-core Nuclear Instrument Channels.Transmitter Failed to Maintain Calibr. Transmitter Replaced.Cause of Shift in Calibr Not Stated | | | 05000317/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000318/LER-1981-001-03, /03L-0:on 810107,Channel B Reactor Protective Sys Trip Units for High Power,Thermal Margin/Low Pressure & Axial Flux Offset Bypassed for Troubleshooting Linear Power Range Instrument.Detector Output Faulty | /03L-0:on 810107,Channel B Reactor Protective Sys Trip Units for High Power,Thermal Margin/Low Pressure & Axial Flux Offset Bypassed for Troubleshooting Linear Power Range Instrument.Detector Output Faulty | | | 05000318/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000318/LER-1981-002-03, /03L-0:on 810108,diesel Generator 12 Started Automatically.Possibly Caused by Control Relays in Abnormal State.Generator Reset & Tested | /03L-0:on 810108,diesel Generator 12 Started Automatically.Possibly Caused by Control Relays in Abnormal State.Generator Reset & Tested | | | 05000318/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000317/LER-1981-002-03, /03L-0:on 810111,auxiliary Feedwater Flow to Steam Generators Found Set Below Normal Limit.Caused by Feed Regulating Valve Stroke Limitation Implemented Under Mods Required by NUREG-0578.Restriction Removed on 810122 | /03L-0:on 810111,auxiliary Feedwater Flow to Steam Generators Found Set Below Normal Limit.Caused by Feed Regulating Valve Stroke Limitation Implemented Under Mods Required by NUREG-0578.Restriction Removed on 810122 | | | 05000317/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000317/LER-1981-003-03, /03L-0:on 810217,engineered Safety Features Actuation Sys Channel 2D 12 Steam Generator Pressure Isolator Found Out of Spec.Caused by Transmation Isolator w/non-liner Output.Isolator Replaced | /03L-0:on 810217,engineered Safety Features Actuation Sys Channel 2D 12 Steam Generator Pressure Isolator Found Out of Spec.Caused by Transmation Isolator w/non-liner Output.Isolator Replaced | | | 05000317/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000318/LER-1981-003-03, /03L-0:on 810123,shutdown Cooling Return Header Isolation valve,MOV-652,lost Valve Position Indication & Flow Was Stopped.Caused by Motor Control Center Power Transfer.Transfer Completed,Indication & Flow Restored | /03L-0:on 810123,shutdown Cooling Return Header Isolation valve,MOV-652,lost Valve Position Indication & Flow Was Stopped.Caused by Motor Control Center Power Transfer.Transfer Completed,Indication & Flow Restored | | | 05000318/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000317/LER-1981-004-03, /03L-0:on 810119,containment Cooler 8-inch SRW Discharge valve,1-CV-1593,failed to Open.Caused by Solenoid valve,1-SV-1593,not Allowing 1-CV-1593 to Open.Solenoid Valve Replaced W/Spare & Parts Kit Installed | /03L-0:on 810119,containment Cooler 8-inch SRW Discharge valve,1-CV-1593,failed to Open.Caused by Solenoid valve,1-SV-1593,not Allowing 1-CV-1593 to Open.Solenoid Valve Replaced W/Spare & Parts Kit Installed | | | 05000317/LER-1981-004-01, Containment Cooler 8-inch SRW Discharge Valve Failed to Open.Apparently Caused by Low Differential Pressure Rating of Solenoid Valve That Would Not Vent to Allow Discharge Valve to Open | Containment Cooler 8-inch SRW Discharge Valve Failed to Open.Apparently Caused by Low Differential Pressure Rating of Solenoid Valve That Would Not Vent to Allow Discharge Valve to Open | | | 05000318/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000318/LER-1981-004-03, /03L-0:on 810204, While Conducting Preventive Maint,Shutdown Cooling Flow Lost.Caused by Procedure Not Containing Sufficient Info.Flow Lost Due to de-energized Vital Ac Bus Causing Valve to Shut.Procedure Revised | /03L-0:on 810204, While Conducting Preventive Maint,Shutdown Cooling Flow Lost.Caused by Procedure Not Containing Sufficient Info.Flow Lost Due to de-energized Vital Ac Bus Causing Valve to Shut.Procedure Revised | | | 05000317/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000318/LER-1981-005, Forwards LER 81-005/01T-0 | Forwards LER 81-005/01T-0 | | | 05000318/LER-1981-005-01, /01T-0:on 810118,w/reactor Coolant Sys at 220 F & 230 Psia,Presssure Transmitter Failed High,Causing Power Relief Valve RC-404-ERV to Open.Caused by Loose Oscillator/ Amplifier Assembly within Transmitter 2-PT-103-1 | /01T-0:on 810118,w/reactor Coolant Sys at 220 F & 230 Psia,Presssure Transmitter Failed High,Causing Power Relief Valve RC-404-ERV to Open.Caused by Loose Oscillator/ Amplifier Assembly within Transmitter 2-PT-103-1 | | | 05000317/LER-1981-005-03, /03L-0:on 810119,during Surveillance Testing, Containment Cooler 14 Would Not Start in Slow Speed.Caused by Contacts Not Closing on Slow Speed Motor Starter Interlock Contact Assembly Due to Cracked Case | /03L-0:on 810119,during Surveillance Testing, Containment Cooler 14 Would Not Start in Slow Speed.Caused by Contacts Not Closing on Slow Speed Motor Starter Interlock Contact Assembly Due to Cracked Case | | | 05000317/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000317/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000317/LER-1981-006-03, /03L-0:on 810113,steam Generator 11,level Channel D Placed Out of Svc Per Tech Specs to Correct Problem W/Ref Leg.Caused by Indication Deviation Among Redundant Safety Channels Due to Level Transmitter Valve leak-through | /03L-0:on 810113,steam Generator 11,level Channel D Placed Out of Svc Per Tech Specs to Correct Problem W/Ref Leg.Caused by Indication Deviation Among Redundant Safety Channels Due to Level Transmitter Valve leak-through | | | 05000318/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000318/LER-1981-006-03, /03L-0:on 810113 Diesel Generator 12 Switchgear Would Not Close in on 21 4-kV Bus Per Tech Spec.Caused by High Resistance at Secondary Disconnect.Continuity of Closing Circuit Interlocks Verified & Switchgear Tested | /03L-0:on 810113 Diesel Generator 12 Switchgear Would Not Close in on 21 4-kV Bus Per Tech Spec.Caused by High Resistance at Secondary Disconnect.Continuity of Closing Circuit Interlocks Verified & Switchgear Tested | | | 05000318/LER-1981-007-03, MSIVs 21 & 22 Failed to Shut within Required Time Limit.Caused by Galled Stems of Packing Junk Ring.Rings Replaced | MSIVs 21 & 22 Failed to Shut within Required Time Limit.Caused by Galled Stems of Packing Junk Ring.Rings Replaced | | | 05000317/LER-1981-007-03, /03L-0:on 810112,engineered Safety Features Actuation Sys Sensor Channel Ze for Steam Generator 12 Pressure Placed Out of Svc.Caused by Failure of Transmation Isolator (230IT) 1-E/E-1023B.Isolator Output Found Low | /03L-0:on 810112,engineered Safety Features Actuation Sys Sensor Channel Ze for Steam Generator 12 Pressure Placed Out of Svc.Caused by Failure of Transmation Isolator (230IT) 1-E/E-1023B.Isolator Output Found Low | | | 05000317/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000318/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000317/LER-1981-008, Forwards LER 81-008/01T-0 | Forwards LER 81-008/01T-0 | | | 05000318/LER-1981-008-03, /03L-0:on 810113,steam Generator 22 Low Pressure Bistable Meter 2D Found Out of Calibr & Signal Isolator 2-E/E-1023A Failed.Caused by Natural Wear & Aging.Cause of Isolator Failure Not Stated | /03L-0:on 810113,steam Generator 22 Low Pressure Bistable Meter 2D Found Out of Calibr & Signal Isolator 2-E/E-1023A Failed.Caused by Natural Wear & Aging.Cause of Isolator Failure Not Stated | | | 05000317/LER-1981-008-01, /01T-0:on 810203,discovered That When Fire Hose Stations in Auxiliary Bldg & Unit 2 Containment Bldg Were Isolated,Backup Fire Hose Not Routed as Required.Caused by Personnel Error.Backup Hoses Routed as Required | /01T-0:on 810203,discovered That When Fire Hose Stations in Auxiliary Bldg & Unit 2 Containment Bldg Were Isolated,Backup Fire Hose Not Routed as Required.Caused by Personnel Error.Backup Hoses Routed as Required | | | 05000318/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000318/LER-1981-009-03, /03L-0:on 810330,during Normal Power Operation, Motor Operated Isolation Valve in Saltwater Sys Would Not Operate Electrically.Caused by Tripped Overload Devices on Phase a & C.Devices Reset | /03L-0:on 810330,during Normal Power Operation, Motor Operated Isolation Valve in Saltwater Sys Would Not Operate Electrically.Caused by Tripped Overload Devices on Phase a & C.Devices Reset | | | 05000317/LER-1981-009-03, /03L-0:on 810205,reactor Protector Sys Channel D Trip Units Bypassed.Caused by Increase in Temp Detector Resistance,Probably Due to Increased Connection Resistance in Containment.Input Removed from Channel D | /03L-0:on 810205,reactor Protector Sys Channel D Trip Units Bypassed.Caused by Increase in Temp Detector Resistance,Probably Due to Increased Connection Resistance in Containment.Input Removed from Channel D | | | 05000318/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000317/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000318/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000318/LER-1981-010-03, /03L-0:on 810301,power-operated Relief Valve ERV-402 Failed to Seat Resulting in Valve Isolation.Caused by Insufficient Pressure in Sys While Filling Rcs.Pressure Raised & Valve Seated | /03L-0:on 810301,power-operated Relief Valve ERV-402 Failed to Seat Resulting in Valve Isolation.Caused by Insufficient Pressure in Sys While Filling Rcs.Pressure Raised & Valve Seated | | | 05000317/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000317/LER-1981-010-03, /03L-0:on 810123,nipple Broken on Valve CV-5178, Salt Water Emergency Return Isolation from ECCS Pump Room Coolers.Caused by Lead Brick Fall During Const of Lead Shield Wall.Valve Isolated & Nipple Replaced | /03L-0:on 810123,nipple Broken on Valve CV-5178, Salt Water Emergency Return Isolation from ECCS Pump Room Coolers.Caused by Lead Brick Fall During Const of Lead Shield Wall.Valve Isolated & Nipple Replaced | | | 05000317/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000317/LER-1981-011-03, /03L-0:on 810212,thermal Margin/Low Pressure & Steam Generator Low Pressure Trip Units Bypassed While Investigating Intermittent Failures of Reactor Protective Sys Channel D Steam Generator Pressure | /03L-0:on 810212,thermal Margin/Low Pressure & Steam Generator Low Pressure Trip Units Bypassed While Investigating Intermittent Failures of Reactor Protective Sys Channel D Steam Generator Pressure | | | 05000318/LER-1981-011-03, /03L-0:on 810404,steam Generator 21 Pressure Instrument 2-PY-1013D Failed,Causing Channel D Thermal Margin/Low Pressure Trip.Caused by Failure of Sealed, Nonadjustable,Solid State Load Isolator.Device Discarded | /03L-0:on 810404,steam Generator 21 Pressure Instrument 2-PY-1013D Failed,Causing Channel D Thermal Margin/Low Pressure Trip.Caused by Failure of Sealed, Nonadjustable,Solid State Load Isolator.Device Discarded | | | 05000318/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000317/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000317/LER-1981-012-03, /03L-0:on 810213,while Shifting from 1 to 2 Running Charging Pumps,Letdown Relief Valve CVC-345-RV Lifted & Failed to Reseat.Possibly Caused by Pressure Surge in Line.Valve Matls Review Being Conducted | /03L-0:on 810213,while Shifting from 1 to 2 Running Charging Pumps,Letdown Relief Valve CVC-345-RV Lifted & Failed to Reseat.Possibly Caused by Pressure Surge in Line.Valve Matls Review Being Conducted | | | 05000317/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000317/LER-1981-013-03, /03L-0:on 810217,inboard Turbine Bearing Journal in Auxiliary Feedwater Pump 11 Was Found Heavily Heat Scored & Babbit Matl Was Suspended in Oil.Probably Caused by Improper Oil Level or Contaminated Oil.Procedures Changed | /03L-0:on 810217,inboard Turbine Bearing Journal in Auxiliary Feedwater Pump 11 Was Found Heavily Heat Scored & Babbit Matl Was Suspended in Oil.Probably Caused by Improper Oil Level or Contaminated Oil.Procedures Changed | | | 05000318/LER-1981-013-03, /03L-0:on 810304,while Installing Instrumentation, Temporary Shunt Opened,Causing Loss of Power to Low Pressure Safety Injection Pump 22 & Momentary Loss of Shutdown Cooling Flow.Caused by Opened Lead on One End of Shunt | /03L-0:on 810304,while Installing Instrumentation, Temporary Shunt Opened,Causing Loss of Power to Low Pressure Safety Injection Pump 22 & Momentary Loss of Shutdown Cooling Flow.Caused by Opened Lead on One End of Shunt | |
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