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| {{Adams
| | #REDIRECT [[05000346/LER-1979-118-03, /03L-0:on 791126,after Low Level Alarm Received & Reactor Coolant Pump 1-2 Was Tripped,Flux Trip Setpoint Was Readjusted to Value Slightly in Excess of Tech Specs.Caused by Procedural Deficiencies.Mods Prepared]] |
| | number = ML19323H308
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| | issue date = 12/21/1979
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| | title = Revised 79-118/03L-1:on 791126,when Reactor Coolant Pump Tripped,Reactor Protection on Sys High Flux Setpoint Reduced to 78.5% Full Power,Exceeding Limit.Caused by Procedural Deficiency Due to Incorrect Info
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| | author name = Kocis R
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| | author affiliation = TOLEDO EDISON CO.
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| | addressee name =
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| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
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| | docket = 05000346
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| | license number =
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| | contact person =
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| | document report number = LER-79-118-03L, LER-79-118-3L, NUDOCS 8006120357
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| | package number = ML19323H305
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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 = Revised 79-118/03L-1:on 791126,when Reactor Coolant Pump Tripped,Reactor Protection on Sys High Flux Setpoint Reduced to 78.5% Full Power,Exceeding Limit.Caused by Procedural Deficiency Due to Incorrect Info
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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 = 05000346
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| | LER year = 1979
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| | LER number = 118
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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:m runm var U $. NUCLE AJ (dRL%/JV@LK/ RCulletR3 11118 LICENSEE EVENT REPORT ONTROL BLOCK: l l
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| l l
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| l l
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| lh (PLEASE PRINT CR TYPE ALL RECUlRED INF!RMATl!N) 8 6
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| o l i j l 0 l H l D l B l S l 1 l@l 0 l 0 l - l 0 l 0 l N l P l F l - l 0 l 3 l@l 4 l 1 l 1 l 1 l 1 l@l l
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| lg 8 9 LICENSEE CODE 14 15 L8 CENSE NUMBER 25 26 LICENSE TYPE JO b 7 CA T bd COYT 01 1_l 3[nN l Ll@l 0l 5 l 0 l - l 0 l 3 l 4 l 6 l@l 1 l l l 2 l 6 l 7 l 9 l@l1 l 2 l 2 l 1 l 7 l 9 l@
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| 8 60 61 DOCKET NUMB E R (J
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| 63 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10 l 2 l l On November 26, 1979, a low oil level alarm for Reactor Coolant Pump (RCP) 1-2 was l
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| 6 o l3l l received.
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| Reactor power was reduced and the RCP was tripped. The Shift Foreman in-l O l4 l l structed personnel to reduce the Reactor Protection System (RPS) high flux setpoint l
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| l i
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| o l s t l to 78. 5% of full power. During a log review at 0800 hours on 11/27/79, it was found l
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| l o l6 l l that the value of 78.5% was in excess of the 78.3% value allowed by Technical Specifi ;
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| o l1] l cation 2.2.1 for three RCP operation. There was no danger; the ectual setpoints ex-l o is l l ceeded the tech spec value by 0.08% of the allowed value.
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| (NP-33-79-135) l 8 9 80 SYSTEM
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| ==CAUSE==
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| CAUSE COMP.
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| VALVE CODE CODE SUBLOOE COMPONENT CODE SUSCODE SUBCODE 019]
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| lI l Al@ Q@ l Zl@ lIlN l S lT lR lU l@ g@ g @
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| 8 9
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| 10 II 12 13 13 19 20 SEQUENTIAL OCCURRENCE REPORT REVISloN EVENT YEAR REPORT NO.
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| CCDE TYPE N O.
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| O" y"LE R < RO l7l9l
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| [ _j l1 l1 l8l l -l l0 l3 l lL l 9
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| W tugAT
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| _ 21 22 23 24 26 27 28 29 30 31 32 iX N ACT ON ON PLANT T
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| HOURS 22 5 B IT FoR B.
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| SUPPLIE MAN 1ATRE3lg l E lglJ4G lg l Z lg lZl@
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| l0l0l0l l
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| l N lg l B i l
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| i 33 33 36 J/
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| 40 4i 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h ilall The setpoints were readjusted to within the allowable value by 0850 hours on 11/27/79.l t
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| gl The cause of the incorrect setpoint setting has been attributed to procedural defici-!
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| gl encies in that correct and concise information was not provided. Appropriate pro-l
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| ,13l l cedure modifications have been prepared to correct these deficiencies.
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| ital l l
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| 8 9 80 SA S
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| % POWER oTHER STATUS DIS O RY DISCOVERY DESCRIPTION iTs1 l El@ l 0l 6 l 8 l@l NA l
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| lB [gl Routine log review l
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| ACTIVITY CO TENT r"N m.!?MO Or nt Lt.ot AMOUNT OF ACTIVITY LCCM.o.10F RELEASE @
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| iTel U @ l zl@l NA l
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| i NA 7
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| l 8 9 to 11 44 45 80 TERSONNEL EXPOSURES NUMBER TYPE
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| ==DESCRIPTION==
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| iTl 1 01 el el@Lz J@l "A
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| I PERSONNEt INJURIES NUMBER
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| ==DESCRIPTION==
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| g l 0l 0l 0l@l NA l
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| 8 9 11 12 80 LOSS OF OR DAMAGE To FACILtTV TY/E
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| ==DESCRIPTION==
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| LL9.J LzJ@l NA l
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| 8 9 10 80 ISSUE
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| ==DESCRIPTION==
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| E LN_j @ l NA l
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| llllllllll lll5 8 9 10 68 69 80 ;;
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| VR 79-178 &nRQ7 Men Kods W4WN M N {
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| PREPAREn
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| : pgogg, 8006120%r7
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| TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR PO'<!ER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-135 DATE OF EVENT:
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| November 26, 1979 FACILITY:
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| Davis-Besse Unit 1 8
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| IDENTIFICATION OF OCCURRENCE: After tripping Reactor Coolant Pump (RCP) 1-2, the flux trip setpoint was readjusted to a value slightly in excess of technical opecifications Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWT) = 1885 cnd Load (Gross MWE) = 638.
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| Description of Occurrence:
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| At 2145 hours on November 26, 1979, a motor lower bearing oil level alarm low (L808) for RCP 1-2 was received in the control room. As dictated by the immediate action of EP 1202.16 RCP and Motor Emergency Procedure, reactor power was reduced and RCP 1-2 was tripped.
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| Instrument and Control personnel were then called to lower the flux trip setpoint corresponding to three RCP operation.
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| By 0000 hours on November 27, 1979, the new flux trip setpoint value was obtained from the Shif t Foreman and the trip bistables were reset.
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| During log review at 0800 hours on November 27, 1979, the 78.5% setpoint value ob-teined from the Shif t Foreman was discovered to be in excess of 78.3% which is the maximum allowed per the Technical Specification 2.2.1 for three RCP operation.
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| An cdditional setpoint adjustment was completed by 0858 hours on November 27, 1979, to lower the trip bistable setpoint within technical specification requirements.
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| ?
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| (
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| Designation of Apparent Cause of Occurrence: The cause for incorrectly setting the flux trip setpoint has been attributed to procedure deficiencies in that correct and concise 3
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| information was not provided.
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| The EP 1202.16, RCP and Motor Emergency Procedure used during the trip of RCP 1-2 does not relate a need for resetting the trip setpoints to
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| 'cny value or specify the value.
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| Analysis of Occurrence: There was no danger to the health and safety of the public cr to station personnel.
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| By the procedure, trip voltages set into the bistable may h;ve a tolerance of (+) 0.000 VDC to (-) 0.060 VDC with respect to the percent rated thermal pow'er desired. This maintains tapt the actual setpoint applied may be more c:nservative than that specified.
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| In this case, the actual voltage to which the bistables were set corresponds to 78.46% of rated thermal power.
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| This value exceeds tschnical specifications (by.08% of the allowable value) which is. expected to be within safety margins.
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| Carrective Action: Modifications will be prepared to the RCP and Motor Emergency
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| . Procedure EP 1202.16 and Power Operation PP 1102.04 to reflect technical specifica-tisn requirements for three RCP operation flux trip setpoints.
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| Failure Data: There have been no previously reported procedural difficulties con-c;rning reactor protection system high flux trip setpoint.
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| i LER #79-118
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| ~
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| }}
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| {{LER-Nav}}
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