05000325/LER-1979-001-03, /03L-0 on 790104:HPCI Sys Failed Response Time Periodic Test.Testing to Be Done Again After Reactor Startup,When Steam Is Available.Event Cause & Corrections to Be Submitted After Satisfactory Testing

/03L-0 on 790104:HPCI Sys Failed Response Time Periodic Test.Testing to Be Done Again After Reactor Startup,When Steam Is Available.Event Cause & Corrections to Be Submitted After Satisfactory Testing

ML19269C606
Person / Time
Site:	Brunswick
Issue date:	02/02/1979
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19269C605	List: 05000325/LER-1979-001, Forwards LER 79-001/03L-0 05000325/LER-1979-001-03, /03L-0 on 790104:HPCI Sys Failed Response Time Periodic Test.Testing to Be Done Again After Reactor Startup,When Steam Is Available.Event Cause & Corrections to Be Submitted After Satisfactory Testing
References
LER-79-001-03L, LER-79-1-3L, NUDOCS 7902060214
Download: ML19269C606 (1)

LER-1979-001, /03L-0 on 790104:HPCI Sys Failed Response Time Periodic Test.Testing to Be Done Again After Reactor Startup,When Steam Is Available.Event Cause & Corrections to Be Submitted After Satisfactory Testing

Event date:
Report date:
3251979001R03 - NRC Website

text

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LICENSEE EVENT REPORT l

l l

l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

CONTROL BLOCK:

N l C l B l E l P l 1 l@l 0 l 0 l - l 0 l 0 0l0l0l- 0l0l@l4 1l1l1l1l@l l

7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 68 CON'T 3o[OR L l@l 0l 5 l 0 l - l 0 l 3 l 2 l 5 @l 0 l 110 l 4 l 7 I 9 @l 0 l 2 0]2l7 9 l@

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8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE. CONSEQUENCES h o

2 l The HPCI system failed response time Periodic Test, P.T.45.3.4.

A Technical o

3 l

Specification response time of 130.0 seconds is required, and on 1/4/79, a responsel o

4 I

time of 30.2 seconds was attained.

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s I (Technical Specification 3.3.3) 1 0

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8 l

l 80 7

8 9 E

CODE SUSCO E COMPONENT CODE SUB ODE SUB E

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7 8

9 10 11 12 13 18 19 20 SEOUENTIAL OCCURRENCE REPORT REVISION LE EVENT YEAR REPORT NO.

CODE TYPE N O.

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_ 21 22 23 24 26 27 28 29 30 31 32 KN A O

O P NT M

HOURS 22 S8 FOR 8.

SUFPL1 MANUFAC RER 9 l 9 l 9 l@

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Z 33 25 36 37 40 di 42 43 44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS h i

o l Troubleshooting work on the governor controls (EGM-EGR) was in progress when the l

unit was shut down on 1/13/79 for a refueling outage.

Response time testing will bel j3 ;i; i

2 I

attempted again after reactor startup, when steam is available following the refuel-l 3

l ing outage. A revision to this report will be submitted describing event cause and l corrective actions after the response time test has been completed satisfactorily.

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7 8 9 80 STA

% POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION NA l

lB l@l Periodic Test l

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5 ACTIVITY CO TENT AMOUNT OF ACTIVITY LOCATION OF RELEASE RELEASE @D OF RELEASE lZ l@l l Z]

NA l

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1 6

7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE D ESCRIPTION [0 l 0 l 0 l@l Z l@l NA l

1 7

PERSONNEL INJU IES NUMRER

DESCRIPTION

NA l

[1 lf.] l 0 0l0l@l 7

8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE

DESCRIPTION

] @l NA 9

7 8 9 10 80

[ 2_Lo,J W@ DESCRIPTION v4s 7g02 0 6 0 2/V l l l l l l l l l l l l l :;

PUBLICITY A

NRC USE ONLY ISSUED o

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8 9 to 68 69 80 7.

919-457-6701

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