05000298/LER-1980-044-01, /01T-0:on 801115,reactor Scram Occurred & Normal Cooldown Rate Exceeded.Caused by Failed Card (Westinghouse- Hagan 398522) in Computer Controlled Turbine Control Sys Forcing Main Steam Bypass Valves to Remain Open

/01T-0:on 801115,reactor Scram Occurred & Normal Cooldown Rate Exceeded.Caused by Failed Card (Westinghouse- Hagan 398522) in Computer Controlled Turbine Control Sys Forcing Main Steam Bypass Valves to Remain Open

ML20002B939
Person / Time
Site:	Cooper
Issue date:	11/25/1980
From:	Borer P NEBRASKA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20002B938	List: 05000298/LER-1980-044, Forwards LER 80-044/01T-0 05000298/LER-1980-044-01, /01T-0:on 801115,reactor Scram Occurred & Normal Cooldown Rate Exceeded.Caused by Failed Card (Westinghouse- Hagan 398522) in Computer Controlled Turbine Control Sys Forcing Main Steam Bypass Valves to Remain Open
References
LER-80-044-01T, LER-80-44-1T, NUDOCS 8101070357
Download: ML20002B939 (1)

LER-1980-044, /01T-0:on 801115,reactor Scram Occurred & Normal Cooldown Rate Exceeded.Caused by Failed Card (Westinghouse- Hagan 398522) in Computer Controlled Turbine Control Sys Forcing Main Steam Bypass Valves to Remain Open

Event date:
Report date:
2981980044R01 - NRC Website

text

)ERt. FORM 366 U. S. NUCLEAR REGUL ATORY COMMISSION 17 771 LICENSEE EVENT REPORT CONTROL BLOCK. l l

l l

l

! Ih (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI O

lo l t l l N! El Cl Pl Rl l@l 0l 01-l 0l O! 0l 0l -l 0l Oi 0l@l4l1l1lllll@l l

l@

7 3 J LICENSEE CODE 14

?$

UCENSE NLV8EH 45 26 LICENSE TYPE JO 57 S A T $8 CON'T lolil 5C"C; I t}@l015 l 0101012191 sl@l il il il 4 al d@l 11 11 21 51 81 01@

l 4

60 61 OOCK ET NLMBER o8 69 EVENT D ATE 74 7$

RE POR T D ATE e,0 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l o 12 l l During APRM surveillance testing (S.P. 6.1.29), a reactor scram occurred.

Follow-I to43; l ing the ecrat, the normal cool down rate of 100 F/hr was exceeded. (T.S. 3.6.A.1) i 1914 I ! There were no adverse consequences from the standocint of cublic hoalth and I

lo is] isafety. This transient is similar to a stuck ocen relief valve transient and is I

( ? !6 I Inot limiting in the reactor vessel thor-n1 cvela,nnivR4R-I lo i:1 l I

t ola i I I

do 7

a3 SYSTEM

CAUSE

CAUSE COMP VAL %E CODE CODE SLBCOCE COVPONENT CODE SL8 CODE SUBCCDE loj91 l El El@ d@ l d@ l 11 'I Sl Tl RlU l h W @ W @

7 9

3 to it IJ r3 is la An SE QUE N TI A L OCCUR R E NCE REPORT REV853ON

_EVENTvfAR R EPOR T NO.

COOE TYPE NO.

@ lg a no 18101 1-1 l014141 1/_]

10 11 1 LT_J L--l 10 1 j,ga;

_ 21 22 21 24 26 27 29 23 30 11 22 ACTION FUTURE EFFECT SHUTDOWN ATT AC MVENT NP R O-4 PRIVE COMP.

COMPONENT TAKEN ACTION ON PLANT VETHOD wCURS <+

SUBMITTED FORMbv8.

SUPPLIE R VANUFACTURER l A@l J.j@

la j@

l_G.j@

l0l0l I

l

(.N._j @

l l@

W@

lWl1l2l0l@

JJ J4 35 36 3

40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l i j o l l A failed card (Westinghouse-Hagan #398522) in the ecmouter controlled turbine con- !

en,rene I Ii ii l l trol svstem caused the main steam bvoass valves to rem in open f ol i n u f n c.

scram. The failed component was replaced and tested during the outage subsequent i i,,,,l to the scram.

I li14 1 1 I

80 S

' POWER OTHER STATLS DIS V RY DISCOVERY DESCRIPTION li is I [E j@ l0 19 13 l@l NA l

l Al@l NA l

A TIvliv CO TENT RELEASED OF RELE ASE AMOUNT OF ACTivlTV LOCATION OF RELE ASE NA l

l NA I

l ' l 6 l [_J,] @ [_Zj@l 7

d

-)

10 11 44 45 80 PERSC%EL EXPOSLRES OESCRsPTION TYPE @l

'du?.'9 E R l i l 7 l l Ol 0l d@l d

NA I

PERsoma' wAS OnCR,PT,0N@

NUM -

lill101ol Q@l NA i

/

4 1 11 11 80 L U% OF OH D AM AGE TO F AC Ltiv type C E 5 Chip itON l ' l 91 l Zl@l NA l

4 i

10 80

""' " Ncn. Prion h W [_k[i@l NRC USE ONl V n

... o NA l

lllllll1ll 1Il2 4 j to 66 69 80 5 Paul J. Borer WC-W

{

NAVE OF PREPARER pygyg; 8101070357