LER-1980-079, /03L-0:on 801001,following Scram,D Relief Valve Stuck Open Causing Complete Depressurization of Reactor. Probably Caused by Scoring on Main Piston.Valve Replaced |
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LICENSEE EVENT REPORT
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7 8 9 UCENSEE CODE 14 15 UCENSE NUMSER 25 26 UCENSE TYPE JO 57 CAT 58 CON'T 10I1l "bRCE I L hl 0 l 5 lo l-l0 l2 l9 l3 hl1 l0 l0 l1.l8 l0 @l 1l 0 l 311 l 8 l0 l@
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8 60 61 DOCKET NUM8ER 68 69 EV ENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROSA8LE CONSEQUENCES h Io i2l l On October 1, 1980 at approximate 1v 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, the reactor scrammed due to main steam l line high radiation.
During the process of reducing plant pressure, the 'D' Relief lo la l l Valve stuck open causing a complete depressurization of the reactor and requiring a l
orywell entry to inspect and repair the valve.
A Target Rock representative arrived
,[ol4l l on site Wednesday, October 1 to assist station personnel in replacing testing, l
disassembiing and inspecting the
'D' relief valve, Replacement of the valve was lo IsI l completed Friday, October 3.
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9 10 11 12 13 18 19 20 SEQUENTIAL OCCUR RENCE REPORT REVISION LE R/Ro EVENT YEAR R EPORT No.
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3 31 40 41 42 43 44 47 CAUSE CESCRIPTION AND CORRECTIVE ACTIONS 67 lt Iol l Investigation indicated that the probable cause of the valve failing was scoring on l
,ji,,,; the main piston.
,,,,, g Startup commenced and the unit returned to service at 0209 hours0.00242 days <br />0.0581 hours <br />3.455688e-4 weeks <br />7.95245e-5 months <br /> Monday October 6.
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7 8 9 10 tt 44 45 80 PERSONNEL EXPOSURES NUMSER 39 y l 0 l 0 l 0 lhl TYPE @l DESCRIPTION Zl NA l
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Mr. M. Thomas McLoughlin 617-746-7900 g
O BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET No. 50-293 Attachment to LER 80-079/03L-0
Description
On October 1, 1980 subsequent to a reactor scram, Relief Valve 203-3D opened.
Repeated attempts at control room switch to energize /deenergize solenoid valve did not effect valve closure. The valve remained in the open position until RPV pressure decreased to 20 psig.
Accoustic instrument action installed on each valve indicated that main stage of 'D' valve was open and flowing.
Discharge thermocouple further supported that observation.
On October 2,1980, exhaustive testing of. the valve while it was on line, revealed no abnormal conditions. The valve was removed as a complete assembly (less the solenoid assembly which was removed from valve as a subassembly to preclude damage to the solenoid bonnet during handling of the valve assembly). A spare valve assembly and solenoid were installed.
Bench testing 3 disassembly, and inspection of the solenoid and air operator assemblies revealed the following anomalies.
A.
Air operator assembly leakage was measurable as greater than 0.5 SCFH.
4 B.
Solenoid assemblies internal
'O' ~ ring exhibited slight deterioration -
adhesion to the mating parts.
.i C.
Air operator assembly bushing 'O' ring seal exhibited deterioration - loss of resiliency resulting in loss of ef fective sealing of air operator " working" volume. 'O' ring was soft and difficult to extract in one piece.
D.
The solenoid assembly bonnet tube exhibited evidence of " loctite" contamination at I.D., indication of mating contact area on plunger was noted.
E.
Main guide of main stage internals exhibited two (2) local and side by side indentations or stellite hardfaced 6% dia. and similar scoring on 0.D. of piston.
F.
Air operator assembly thread seal ('thred seal') rubber insert exhibited brittleness - loss of effective sealing characteristic could not be measured due to condition of bushing oring (comment 'C' above).
l Conclusions A.
Tests, disassembly observations, and inspection revealed only one condition that's considered the probable cause of valve failure to close.
1 The indentation noted on I.D. of guide and scores on 0.D. of main piston have similar signatures and may be the result of foreign material becoming lodged (wedges between the guide and piston rod and possibly holding the main disc /
- - piston assembly in the partially open position. The suspected foreign material was not discovered during disassembly of the main' stage.
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B.
Presence of " loctite" contamination on I.D. of solenoid assembly bonnet did not affect solenoid assembly operation for intended design conditions.
C.
Leakage is attributed to deterioration of "o" ring.
NOTE: O ring deterioration is suspected to result from application of
" castor oil" to "o" ring at time of production.
Embrittlement of thread seal, "thredseal" is considered an acceptable condidtion based on visual observation which indicate
- - an effective seal was present.
D.
Deterioration of internal solenoid assembly "o" rings did not affect leak tightness characteristics of solenoid assembly.
Existing procedures and requirements for valve overhaul are considered adequate for refurbishing of worn parts of relief valves.
This is an isolated event.
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| 05000293/LER-1980-001-01, /01T-0:on 800123,fire Hazard Analysis Determined That Fire in Electrical Raceways in Several Areas of Plant Would Jeopardize Redundant Div of ECCS Sys.Cause Not Stated. Mods Planned to Be Completed by Oct 1980 | /01T-0:on 800123,fire Hazard Analysis Determined That Fire in Electrical Raceways in Several Areas of Plant Would Jeopardize Redundant Div of ECCS Sys.Cause Not Stated. Mods Planned to Be Completed by Oct 1980 | | | 05000293/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000293/LER-1980-002-02, /02T-0:on 800124,cable Separation Inadequacy Discovered Following Review of IE Info Notice 79-32. Affected Automatic Depressurization Sys Cables Will Probably Be Rerouted | /02T-0:on 800124,cable Separation Inadequacy Discovered Following Review of IE Info Notice 79-32. 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Requalification Program Will Include Sys Review | /03L-0:on 800526,during Surveillance Testing, Channel B of Rod Block Monitor Sys Determined to Be Out of Calibr.Caused by Misinterpertation of Tech Specs. Requalification Program Will Include Sys Review | | | 05000293/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000293/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000293/LER-1980-024-03, /03L-0:on 800530,reactor Core Isolation Cooling Sys Was Declared Inoperable.Caused by Faulty Auto Flow Control.Unit Repaired & Returned to Svc | /03L-0:on 800530,reactor Core Isolation Cooling Sys Was Declared Inoperable.Caused by Faulty Auto Flow Control.Unit Repaired & Returned to Svc | | | 05000293/LER-1980-025, Forwards LER 80-025/03L-0 | Forwards LER 80-025/03L-0 | | | 05000293/LER-1980-025-03, /03L-0:on 800602,fire Detection Alarm from HPCI Quadrant Sounded in Control Room on Panel C-94.Roving Fire Patrol Initiated & Immediate Investigation Conducted.Caused by Leak at Flange on HPCI Drain Line Valve AO2301-29 | /03L-0:on 800602,fire Detection Alarm from HPCI Quadrant Sounded in Control Room on Panel C-94.Roving Fire Patrol Initiated & Immediate Investigation Conducted.Caused by Leak at Flange on HPCI Drain Line Valve AO2301-29 | |
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