ML17173A613

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Forwards LER 79-008/03L-0
ML17173A613
Person / Time
Site: Dresden Constellation icon.png
Issue date: 02/09/1979
From: Stephenson B
COMMONWEALTH EDISON CO.
To: Keppler Jr
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17173A614 List:
References
79-135, NUDOCS 7902220011
Download: ML17173A613 (3)


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Commonwealth Edison oresden Nuclear Power Station R.R. #1


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February 9, 1979 BBS LTR # ~9-135 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

.Reportable Occurrence Report //79-8/031-0, Docket #050-237 is hereby submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2.(b),

conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.

B.B. Stephenson Station Superintendent Dresden Nuclear Power Station BBS:lcg Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC

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1.J nC1-""01'+ ::t2~ .NUCLEAH REGULATOHY CUM.v11:;s10*~

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LlCE.NSEE EVENT REPOP.T SON TROL GLOC1':: r,_j_ . . _ _ _ _ *..._l_..___!*__,_. . ._\__,! Q (PLEASE PRINT OR.TYPE ALL REQUIRED INFORMATION)

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I s 9 LICE.\JSSE CODE 14 ;5 LIC!ONSE NU~IUER . 25 26 LICENSE TYPE JO 57 CAT 58 CON'T

~  :~~~~~ ~©I o I s I o 1 o 1o I 2 I 3 I 1 101. o I 1 12 ! 6 I 7 I 9 !G) I o I 2 I o I 9 I 1 I 9 IG) 7 8 GO 61 DOCKET NU\IBER GS 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ .

I During steady state operation, the LPCI system minimum flow valve M0-2-1501-ll'.3.Ai failed to close completely while performing the *LPCI pump operability surveillance (DOS 1500-6). The valve was closing when the breaker tripped. The valve automati- I cally closes.when sufficient flow is sensed in the LPCI pump discharge header.

Safety significance was minimal since remaining 3 LPCI pumps were available to meet I

~ I the required system flow. No previous similar occurrences.

liill 7 8 9 80 SYSTE~.1 C,>.oJSE C,>.USE CO\:?. VAL\'E CODE CODE SUSCODE COMPONENT CODE SUB CODE SU BC ODE CUI]

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8 11 12 13 18 19 20 SEQL*ENTIAL OCCURRENCE REPORT REVISION

@ LER'RO LVENT YEP.A REPORT NO. CODE TYPE NO.

REPORT

  • NUMBER I 71 91 L::::J 10 I 01 81 1...---1 I28 01 3129 L.!'.J L=l lQJ 21 22 23 24 2G 27 30 31 32 ACTION FUTURE EFFECT SHUTDOWN Q
  • ATTACHMENT NPRD*4 PRIME CCMP. COMPONENT TAKEN ACTION ON ?L,>.NT METHOD HOURS ~ SUBMITTED FQR.\1 :;us. SUPPLIER MANUFACTURER W@UJ@

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35 Lll .1 36 37 01 01 01 01 40 Ll!J@

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  • 44 zl 91 91 91@)

47 43 CAUSE CE:SCRIPTION AND CORRECTIVE ACTICNS @

The cause of the failure is unknown. The valve operator motor and the thermal ove:.:..J OJJJ I load contacts were checked with no anomalies found. The breaker was reset and the valve was successfully cycled three times from the control room. While cycling, electrical maintenance checked the amperage of the motor and found it satisfactcrry.

No further corrective action is planned.

ITm 8 9 80

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OTHER STATUS @

FACILITY METHOD OF

  • STATUS  % POWER DISCOVERY DISCOVERY DESCRIPTION '231

~Li@ 10 18 17 l@)l.____N_A______~ ~~~l~~~S_u_r_v_e_1_*_1_1_an~c_e_*~T_e_s_t_i_n_g___ * -~~----'

8 0 10 12 11 44 45 46 80 ACTIVITY CON TENT (.;';\

P.ELSASED o;: REL::,>.SE AMOU~.JT OF ACTIVITY LOCATION OF RELEASE

~ ~@ ~@.__I____ NA_ _ ___, NA 7 ij 9 10 11 44 45 80 80 80 NRC USE ONLY

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~commonwealth PART 1/ Tl TLE OF DEVIATION Edison . *

DEVIATION REPORT STA o* 2 UNIT YEAR 79 -

NO; 12

  • OCCURRED

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LPCI Min Flow Vlv Brkr Trip DATE TIME*

SYSTEM AFFECTED 1500 PLANT CONDITIONS TES*Ti i-..!G LPCI Run 2208 725

!XJ CJ MODE PWR (MWT) LOAD(MWE) YES NO DESCRIPTION OF. EVENT While conducting LPCI pump'operability surveillance DOS 1500-6, the LPCI min flow vlv. breaker tripped when the vlv .. was attempting to close. (2-1501-13A)

DESCRIPTION OF C.~USE Un kl). own OTHER APPLICABLE INFORMATION Breaker reset; vlv was exercised three times successfully EQUl.PMENT [iJ YES DR NO. WR NO.

T. A. Ciesla 1-26-79 FAILURE ONO NA 719 .*. RESPQ_NSIBLE SUP!'RVISOR DATE PART 2 I OPERATING ENGINEERS COMMENTS

_:Redundant< LP CL.pumps_ available to meet reduced system flow.

.SAFETY-TYPE OF DEVIATION EVENT OF POTENTIAL TECH SPEC NON-REPORTABLE ANNUAL . RELATED REPORTABLE OCCURRENCE. PUBLIC INTEREST VIOLATION OCCURRENCE REPORT I NG WR ISSUED

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