ML20024F408

LER 83-079/03L-0:on 830809,main Steam Line & Reactor Water Sample Valve Relay 1A71-K7A Determined Operating in Degraded Mode.Caused by Component Failure.Coil & Contacts Replaced. W/830901 Ltr

ML20024F408
Person / Time
Site:	Hatch
Issue date:	09/01/1983
From:	Nix H, Tipps S GEORGIA POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
GM-83-872, LER-83-079-03L, LER-83-79-3L, NUDOCS 8309090351
Download: ML20024F408 (4)

Text

-. . . .

NRC FCRM 386 ' U.S. NUCLEAR REGULATCRY COMMISSION

. (7 77)

LICENSEE EVENT REPORT

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CONTROL BLOCK: l 1

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATioN) o , l G l A l E l I l H l 1 lg 0 l 0 l- l 0 l 0 l 0 l 0 l 0 l- l0 25l 0 lg 4 l1 l1 l1 l1 lgl l lg 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 26 LICENSE TYPE 30 57 CAT 58 CON'T a

IT m ,g "J L']@l I 5I I I I 12iiigi0i8iOi9!8isigioi9ioirisi3ig 68 69 EVENT DATE 74 75 REPORT DATE 80 7 1s 60 61 DOCkdTNUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h gl Shift personnel found relay 1A71-K7A overheated. Relay 1A71-K7A (main l g 3 ; steam line & reactor water sample valves relay) was determined to be l y,,,,; operating in a degraded mode. The relay was subsequently de-energized. l t

n ,3 y ; Unit 1 received a one-half group 1 isolation. This event is contrary to l

0 6 l the requirene ts of T.S. Table 3.2-1. The group 1 "B" trip system g go g7l l remained operable. This event is non-repetitive; however, this event is l l 1

considered to be a generic failure.

1 O la i I l 7 8 9 80 DE CODE S BC E COMPONENT CODE SUB ode SU E 7

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l S l D lg 9 10 31 g 12 g lRlElLlAlYlXlg 13 18 9 g ]g 20

_ SEQUENTIAL OCCURRENCE REPORT REVISION LE R/RO EVENT YEAR REPORT NO. CODE TYPE N O.

@ Nug "E l21 8l22 3l g23 l 0l 7l 9l 24 26 y

27 l0l3l 28 29 l Ll 30 b

31 W

_ 32 KN A ON PLANT ME HOURS 22 S8 i FOR B. SUP L MANUF CTURER gggg gg i 33 34 yg 35 36 3l70 l0 l0 lU40l ]g 41 gg 42

]g 43 l Gl 0l 8 l 0lg 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h

, o l The cause of this event is component failure. The coil and contacts on  ;

relay 1A71-K7A were replaced. The relay was satisfactorily functionally i

! tested on 08/10/83 and returned to operable status. ,

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1 4 l l 1 7 8 9 80 5

ST S  % POWE R OTHER STATUS I Y DISCOVERY DESCRIPTION

i s [EJQ l lj 0l 0lgl NA l ] gl Operator Observation l 5

ACTIVITY CO TENT e RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE i 1 6 g ]gl NA l l' NA l t -7 8 9 10 11 44 45 80

! PERSONNFL EXPOSURES .

NUMBER TYPE DESCRIPTION

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i 7 1010 I O l@L2J@l

• l PEnSONNEL Imu%ES NUMBER DESCRIPTION i a l 7 8 9 1010101@l12 11 80 l

LOSS OF OR DAMAGE TO FACILITY

. TYPE DESCRIPTION i 9 L2j@l NA l 7 8 9 10 80 1s$

8 9090351 830901 NRC USE ONLY ,

7 2 0 8 9

@l DESCRIPTION @

.10 MA DR ADOCK 05000321 PDR l

68 s9 lllllllllllllj 80 s S. B. Tipps (912)367-7851 o

. _ _ _ . . _ . ,__ NAME O{fREPARER ' PHONE: S,

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NARRATIVE REPORT FOR LER 50-321/1983-07,9 '

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LICENSEE  : GEORGIA POWER COMPANY FACILITY NAME  : EDWIN I. HATCH DOCKET NUMBER ~  : ~50-321 .

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Tech. Specs. section(s) which' requires reporti , '

This 30-day LER is required by sTech. Specs. section 6.9.1.9.b due to the event's ' showing. ;that (the- . unit fwas not meeting the requirements.of1 Tech. Spe c s'. ' Table " 3 '. 2--1, items 1, 4, 5, 6, 7, and 11.

- Plant conditions at the time of the event (s):

This event . occurred on 08/09/83, with the. reactor mode switch in the run position and reactor' power at 2424 MWt (approximately 100%

power).

Detailed description of the event (s):

On 08/09/83, shift personnel began looking for the source of a foul smell 'in the control room, and found the main steam line and reactor _ water sample valves relay (1A71-K7A) overheated. Thus, it was determined that relay ' 1 A71-K7 A was operating in a- degraded L mode. Relay 1A71-K7A is the relay to which each of the group 1 isolation signals is . fed for the Al channel of the "A" trip

-system. Thus, with this relay inoperable, the " REQUIRED OPERABLE-CHANNELS PER TRIP SYSTEM" could not be met for the_ following ' items of Tech. Specs. table 3.2-1: 1 (low low reactor water level), 4 (main, steam line high radiation), 5 (main steam line low pressure), .

.6 (main- steam .line high flow), 7 - (main steam line tunnel high temperature), and 11 (condenser low vacuum).

Consequences of the event (s)-

Plant operation was not affected by this event. The health and i safety of the public were not affected by this event.

' Status-of redundant or backup subsystems and/or systems:

'The'"B" trip. system' remained operable, t

Justification for continued operation:

The Group'1 " A" trip system was tripped as required by Tech. Specs.

Table 3.2-1,. Note c.'

If repetitive, number of previous LER:

This event is non-repetitive; however, this event is considered to be a_ generic failure, f

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Narrative-Report for LER 50-321/1983-079 Page Two Impact'toothersystemsand/orUnit: '

- This event had no impact on any other Unit 1 system or on Unit 2.

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cause(s) of the'ievent'(s): ' "

The cause of this event is component failure.

Immediate Corrective Action: ,

' The relay .was subsequently de-energized; this placed the "A" -trip system fin- the . tripped condition. The unit received a one-half group 1 isolation.

Supplemental Corrective Action:

The . coil and contacts on relay 1A71-K7A were . replaced . Relay 1A71-K7A was satisfactorily functionally tested on 08/10/83 and returned to operable status.

Scheduled-(future) corrective action:

Plant engineering has written a - design change request (DCR) to either replace the existing HFA relays with century series HFA relays, or to replace the existing HFA relay coils with century series HFA coils. The AE is currently working on the DCR from a design standpoint.

Action to prevent recurrence (if different from corrective actions):

N/A F

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<- Georgb Power Company

p. Post Offica Box 439 o g0//R

, . , Baxity, Georgis 31513

. Telephone 912 367-7781 4 7l. / a >' (.)

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912 537-9444 r'; // . '

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Edwin 1. Hatch Nuclear Plant

• hg September 1, 1983 GM-83-872 PLANT E. I. HATCH Licensee Event Report Docket No. 50-321 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Region II Suite 3100 101 Marietta Street Atlanta, Georgia 30303 ATTENTION: Mr. James P. O'Reilly Attached is Licensee Event Report No. 50-321/1983-079. This report is required by Hatch Unit 1 Technical Specifications section 6.9.1.9.b.

n J }-% n H. C. Nix General Manager )

dN HCN/SBT/djs '

xc: R. J. Kelly G. F. Head J. T. Beckham, Jr.

P. D. Rice K. M. Gillespie S. B. Tipps R. D. Baker Control Room Document Control

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