05000366/LER-1980-133-03, /03L-0:on 800923,reactor Water Level Switches 1 & 2 Tripped at 121 & 123 Inches of Water,Respectively,Contrary to Tech Spec Max of 117.19 Inches.Caused by Setpoint Drift. Switches Recalibr & Tested Successfully

From kanterella
(Redirected from ML19347C028)
Jump to navigation Jump to search
/03L-0:on 800923,reactor Water Level Switches 1 & 2 Tripped at 121 & 123 Inches of Water,Respectively,Contrary to Tech Spec Max of 117.19 Inches.Caused by Setpoint Drift. Switches Recalibr & Tested Successfully
ML19347C028
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 10/09/1980
From: Nix R
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19347C026 List:
References
LER-80-133-03L, LER-80-133-3L, NUDOCS 8010160475
Download: ML19347C028 (2)


LER-1980-133, /03L-0:on 800923,reactor Water Level Switches 1 & 2 Tripped at 121 & 123 Inches of Water,Respectively,Contrary to Tech Spec Max of 117.19 Inches.Caused by Setpoint Drift. Switches Recalibr & Tested Successfully
Event date:
Report date:
3661980133R03 - NRC Website

text

?tRC PUMM Job u. a. evuwLs.mn ncuuta e un a t,ummeaaeveu 177)

\\_/

LICENSEE EVENT REPORT l i CONTROL BLOCK: l l

l l

l l

l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

. _ l o l i l I G l A*] E l I l H l 2_j@l 0 l 0 l 0 l 0 l 0 l 0 l 0 10 l0 l0 l0 l@l4 l1 l1 11 l1 l@l l

l@

8 9 uCENsEE CODE 14 15 LICENSE NUMSEH 26 26 UCENSE TYPE Ju 57 CA T 58 q ]

'T ON jolij go"T l L lgl0 l 5 l0 l0 l0 l3 [6 l6 @l0 l9 [2 l3 l8 l0 \\@l1 l0 l0 l 9 [8 l0 l@

7 8

60 61 DOCKET NUM8ER M

60 EVENT OATE 74 7b REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h lOl2l l With the plant in steady state operation at 2414 MWT while perforraing HNP-l l

1o la11 2-3:

Reactor Water Level Instr. F.T. &

C., 2B21-N025A reactor level J

lO l4 l l switch, switches 1 & 2 tripped 0 121 and 123 inches of water respectively.

l i :,.

10 i s i i Tech. Specs Table 3.3.2-2 requires actuation @ f 117.19 inches of water.

l l

l O 16 l l Redundant switches 2B21-N025B and 2B21-N024A & B were in tolerance plant l

l lOj71 l operation or the public health and safety were not affected. This event j

lo la l I was repetitive as last reported on LER #50-366/1980-72.

l 80 7

8 9 SYSTEM

CAUSE

CAUSE CO*.1P.

VALVE CODE CODE SUBCODE COMPONENT CODE SUSCODE SueCODE lo19l l 1l A l@ {@ {Q l Il Nl Sl Tl Rl Ul@ l S l@ g @

7 8

9 10 11 12 13 18 19 zu SEQUENTI AL OCCURRENCE REPORT REVISION LER RO EVENT YE AR REPORT NO.

COOE TYPE N O.

h RE,P

_9 22 23 24 26 27 28 29 30_

l_l l 0l l 8l 0l

[--]

l1 l3 l 3l l,, - l l 0l 3 [

lLj RT 31 32 AK f AC ON ON PL T MT HOURS SB IT FO t HUB.

SUPPLIE MAN FA URER

.O it isiz is t_z_Je t_zJe i0 i0 i Oi Oi me i Nie i Nie iv i Oi ti Ois 33 34 35 36 3/

40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h lil0ll The cause of this event has been attributed to setpoint drift. The l

li li l l level indicating switch, a varway model 4418, was immediately recali-I

, 7 l

brated and functionally tested successfully. A generic review revealed l

M l,l3ll no inherent problems. No further reporting required.

l U_e.J l I

7 8 9 80 ST S

% POWER OTHER STATUS 15 JV R DISCOVERY DESCRIPTION Surveillance l E l@ l0 l 9 l9 [gl N/A l

l lgl l

t s 7

8 9 10 12 11 44 45 46 80 ACTIVITY CONTENT RELE ASED OF RFLEASE AM t T OF ACTIVITY LOCATION OF RELEASE lt l6i I Z l h [Zj@l l

l N/A l

7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBEH TYPE DESCRIP TION l1 l 7 l l 0 l 010 l@l z lgl N/A l

nRSONNu'IN,UJiES OtSCRiPriONh NumrR N/A l

I rlR I I 0101 O l@l 7

8 9 11 12 80

% y"S OF OR DAMAGE TO FACILIrY LOS i

oe sca'"'o~

NfA l

,gj l

7 8 9 10 80 tsSWi@ DESCRIPTION N/A l

lllllllllllllj 4a 12l oil l

S 0% 16MM R.T. Nix 9i2-367-7781 o

NAVE OF PREPARER PHONE:

Dww-w wwr u. wa - v._m

f'

()

LER /!: 50-366/1980-133 Licensee: GEORGIA POWER CO !PANY Facility Name:

EDWIN I. IIATCH Docket if : 50-366

Narrative

Report for LER 50-366/1980-133

's On September 23, 1980, while the reactor was operating at steady state power of 2414 MWT, while performing UNP-2-3101, Reactor Water Level Instrument F.T.6C., reactor level switch 2B21 NO25A switches 162 were found to actuate at 121 and 123 inches of water increasing respec-tively Tech Specs Table 3.3.2-2 requi res actuation at < 117.19 inches of water increasing.

Redundant switches 2B21 N025B and 2B21 NO24 A&B were operable and in tolerance. Plant operation and the public health and safety were not affected. This event was repetitive as last reported on LER // 50-366/1980-72.

The cause of this event has been attributed to setpoint drift. The switch immediately recalibrated and functionally tested successfully.

Unit was one uses the same type of level indicating switch, a Yarway model 4418, for this application.

(

)

'~~'

A generic review reveal no inherent problems.

The Unit is now in full compliance and no further reporting is required.

?

OL]

3

?

s 4dLAMWit15.dmeary,pr.dpl4sonsgr w e,aM YaieMM:WC%" AsW a3%W' a Ex.

e 4

a'% -

  • v
  • /1