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| {{Adams
| | #REDIRECT [[05000324/LER-1979-057-03, /03L-0 on 790717:safety Relief Valve Lifted & Reset at 970 Lb for No Apparent Cause.Valve Solenoid & Operator Replaced.Supplemental Rept Will Be Issued When Results Received]] |
| | number = ML19254E513
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| | issue date = 10/29/1979
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| | title = /03X-1:on 790717,during Normal Power Operation, Safety Relief Valve F013E Lifted & Reset Approx Five Minutes Later at 970.Cause Unknown.Electrical Check Made of Valve Operator.Valve Solenoid Replaced
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| | author name = Tollison A
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| | author affiliation = CAROLINA POWER & LIGHT CO.
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| | addressee name =
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| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
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| | docket = 05000324
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| | license number =
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| | contact person =
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| | document report number = LER-79-057-03X, LER-79-57-3X, NUDOCS 7911010411
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| | package number = ML19254E503
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| | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
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| | page count = 2
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| }}
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| {{LER
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| | Title = /03X-1:on 790717,during Normal Power Operation, Safety Relief Valve F013E Lifted & Reset Approx Five Minutes Later at 970.Cause Unknown.Electrical Check Made of Valve Operator.Valve Solenoid Replaced
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| | Plant =
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| | Reporting criterion =
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| | Power level =
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| | Mode =
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| | Docket = 05000324
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| | LER year = 1979
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| | LER number = 57
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| | LER revision = 3
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| | Event date =
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| | Report date =
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| | ENS =
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| | abstract =
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| }}
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| =text=
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| {{#Wiki_filter:..
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| .4
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| '7 77)
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| LICENSEE EVENT REPORT CONTROL BLOCK: l l
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| l l
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| l l lh (PLEASE PRINT OR TYPE ALL RkOUIRED INFoRMATION) 1 6
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| (n.LC l s'I E le 12 l@l o lo l l o lo l o l o lo lo lo l@l4 1 Il 11 11 l@l l@
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| o 2
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| 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 68 CON'T 5$R$ l L l@l 015 l 0 l-lo 3l214l@lo 7 11 7
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| 7 9 h 1l0 2 l9 l7 9l@
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| o 1
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| 7 8
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| 60 61 DOCKET NUMBEF, 68 69 EVENT DATZ 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 12 l During normal power operation, safety relief valve FCl3E lif ted and reset approximatelt al 1 five minutes later at 970# for no apparent reason and with no indication of previous o
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| l leakage. Plans were made to shutdown for F013E repair the next weekend. Two days l
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| O 4
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| ITTTI l later, F013E lif ted at 980# and reset at 915# af ter power had been reduced to 537..
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| A 10 is I normal reactor shutdown was then commenced to. repair the valve and prevent any further of7 l chance of inadvertant valve operation.
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| l 0
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| 8 l Technicc1 Specification 3.4.2, 6.9.1.9b l
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| 7 8 9 80 E
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| CODE SUSC E COMPONENT COC 1 SUB ODE S
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| E g
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| l C l C l@ lE l@ lB l@ l Vl Al Ll Vl Li P @ W@ g @
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| 7 8
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| 9 to 11 12 13 18 19 20 SEQUENTI AL OCCU R RENCE REPORT REVISION LER/RO EVENT YE AR REPORT NO.
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| CODE TYPE N O.
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| @,RE g l217 9l 8
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| l0 5l 7l y
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| l0l3l lXl [J
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| g 22 23 24 26 27 28 29 30 31 32 K N ACT ON P NT M
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| HOURS 22 S8 i FOR b 8.
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| SUP L MANbF l2 0g C RER [C jgl34Z lg l A lg
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| l Yl g l Yl g lN lg lT l
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| 33_
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| 35 M
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| 3 40 el 42 4
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| M 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1
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| O l An electrical check of the valve opcrater indicated no electrical fault. The valve g l solenoid was replaced as a precautionary meas tre.
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| The valve operator was replaced andi the failed operator was sent to Wyle Laboratory for failure evaluation. Wyle Labora-l g
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| l tory reported that the pilot valve assembly was leak tested with nitrogen prior te 3 3 g l disassembly. Leakage was beyond measurement capability of the bench test.
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| (CON'T) l 7
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| 8 9 30 STA
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| % POWER oTHER STATUS blS O RY DISCOVERY DESCRIPTION A WQ l 0l 9l 4l@l NA l
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| { @l Operator Surveillance l
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| AblVITY 80 CO TENT RELEASED OF RELEASE AMOU.
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| OF ACTIVITY LOCATION cF RELEASE
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| @ l 2, l@l NA l
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| lNA l
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| 1 6
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| PERSONNEt ExPOSMES NUM8ER TYPE
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| ==DESCRIPTION==
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| Ql 0 l 0 l@l Z l@l NA l
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| i 7
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| PERSONNE L INJU IES Q l 0l U 0 l@l NA 1281 011 NUMBER
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| ==DESCRIPTION==
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| i i
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| 7 8 9 11 12 80 LoS$ OF OR DAMAGE TO FACILITY TYPE
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| ==DESCRIPTION==
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| @l NA l
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| 1 9 7
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| 8 9 to go PUBLICITY
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| //
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| NRC USE ONLY 45 7911010
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| //
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| ISSUE D
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| ==DESCRIPTION==
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| [2J,0,] 1,,,N,jhl NA ll lllll l
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| ll{
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| 7 8 9 10 68 69 80 %
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| PHONE: 919-457-4521 E
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| NAME OF PREPARER A. C. Tollison. Jr.
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| LER CONTINUATION -- RO# 2-79-057
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| \\
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| Facility:
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| BSEP Unit No. 2 Event Date:
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| 7-17-79 CAUSE DESCRIFTION AND CORRECTIVE ACTIONS:
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| Moderate steam cuttin,. the seat and disk were verified during disassembly.
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| c Target Rock's opinion is that the steam cutting of the seat and disk was the cause of the inadvertant operation of the valve. Target Rock recomends in-stalling model 7567F main steam relief valv(, which are insensitive to pilot leakage. We are awaiting field evaluation of these valves before consideration is made for us to use them.
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| 1281 012
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| }}
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| {{LER-Nav}}
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