05000321/LER-1981-091-03, /03L-0:on 810828,while Performing HNP-1-3154 at steady-state Power,Reactor Water Level Instrument (LPCI) Ft&C,Reactor Level Indicating Switch 3 Went at 118 Inches of Water Input.Caused by Instrument Drift.Model Recalibr

From kanterella
(Redirected from ML20010J177)
Jump to navigation Jump to search
/03L-0:on 810828,while Performing HNP-1-3154 at steady-state Power,Reactor Water Level Instrument (LPCI) Ft&C,Reactor Level Indicating Switch 3 Went at 118 Inches of Water Input.Caused by Instrument Drift.Model Recalibr
ML20010J177
Person / Time
Site: Hatch 
Issue date: 09/17/1981
From: Nix R
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20010J171 List:
References
LER-81-091-03L, LER-81-91-3L, NUDOCS 8109290668
Download: ML20010J177 (2)


LER-1981-091, /03L-0:on 810828,while Performing HNP-1-3154 at steady-state Power,Reactor Water Level Instrument (LPCI) Ft&C,Reactor Level Indicating Switch 3 Went at 118 Inches of Water Input.Caused by Instrument Drift.Model Recalibr
Event date:
Report date:
3211981091R03 - NRC Website

text

f NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT j

J CONTROL BLOCK: l l

l l

l l

lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) i e

l GI Al El II HI ll@l 0101 l 0101 Ol 0101 101 Ol@l 4 l1111 Il ll@l l

l@

o i 7

8 9 LICENSEE COOE 14 lb LICENst NUMBER 2b 26 LICENSE TYPE JO

$ 7 CA T 58 j

k CON'T lolil S7%E [Lj@l 01 510101013121 i l@l 018121 RI B l 1 l@l 0] 91 ll 71811 l@

/

8 60 61 DOCKET NUMBER 68 69 EVENT DATE 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSFCUENCES h r

10 W L With the plant at steady state power of 2427 MWt and while performing i

h'4P-1-3154, Reactor Water Level Instrument (LPCI) FT&C,1821-NO31A, React-l iO i3 i l

[ O ;.t i l or Level Indicating Switch, Switch No. 3 went at 118" of H 0 input. Tech l

2 10 i s t i Specs Table 3.2-2 requires actuation </= 117.2" of H 0 which is -38" re-l 2

O o l actor level. Redundant switches 1821-N031B, C and D were operable and in l

ql tolerance. There was no effect upon safe plant operation or the health l

i 3 ig i i and safety of the public. T M s is a non-repetitive event.

l 80 7

8 9 DE CODE SUBC E COMPONENT CODE SUBC DE S

DE

+

lC lE l@ W@ l Z l@ l I l N l S lT l R l U l@ l Sl@ [Z_j @

0 9 7

8 9

to 11 12 13 18 19 20 SE QUENTI AL OCCUR RE NCE REPORT REVISION LE R RO EVENT YEAR REPORT NO.

CODE TYPE NO.

@ aE,P g l218l1l

[.--J l0l9l1l l/l l0 l3 l y

b l0 l 21 23 24 76 27 2"

29 30 Ji 32 K N AC O ON PL NT M T4 itOURS SB IT FOR b B.

SUPPL 1 R MAN FACTURER LE_J@LzJ@

LIJ@

Lz J@

l01010l0J LY_j@

LN_J@

[N_J@

l Yl0 l1 l0 l @

3J J4 35 36 3/

4e 41 42 43 44 47

/

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i 101 1 The cause of this event has been attributed tn sotonint drift. The 1

}

l1 Iii l instrument, a Yarway Model 4418C, was immediately recalibrated and I

i 7 l

returned to service.

No further reporting is required.

I i a l l

l1l4l l l

8G 7

8 9 S

% POWE R OTHER STATUS ISCO RY DISCOVERY DESCRIPTION [TTs'1 l_Ej@ l 1 l 0 l 0 l@l NA l

[B_j@lSurveillanceTesting l

i ACTIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

[_Zj @ [Z_j @ l NA l

l NA l

i s 7

8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DE SCRIPTION l0l0l0l@lZl@l NA l

i 7 PEnSONNE L iN2u'rfiES NUMBER DESCRIPilON l 0] 0] 0l@l NA l

i R 7

8 9 11 12 80 LOSS OF OR DAV AGE TO FACILITY TYPE DESCRtPTION

] @l NA l

i 9 7

8 9 to 80 PUBLICITY 810929066G 810917 NRC USE ONLY l

S PDR NA l

l l l l l l l 1 l l l l I :;

issuEn PDR ADOCK 05000321 l.J_Lo.) [J@oeSCniPfiON 7

8 y to 68 69 80 lE NAME OF PREPARER PHONE:

{

y n

e LL' No.: 50-321/1931-091 Licerisee: Georgia Power Company Fucility: Edwin I. Hatch Docket No. : 50-321

Narrative

Report for LER 50-321/1981-091.

i With the plant at steady state power of 2427 MWt and while performing HNP-1-3154, Reactor Water Level Instrument (LPCI) FT&C,1D21-N031A, Reactor Level Indicating Switch, Switch No. 3 actuated at 118" of water input.

s Tech Specs Table 3.2-2 requires actuation at </= 117.2" of water input t

which corresponds to -38" of water reactor level. The No. 3 contact of this switch provides a permissive to initiate HPCI.

Redundant switches l

1821-N031B, C_and 0 were operable and in tolerance. There was no effect upon safe plant operation or the health and safety of the public. This is i

a non-repetitive event.

Tu' cause of this event has been attributed to setpoint drift. The switch, i

a Yarway Model 4418C, was immediately recalibrated per HNP-1-5281, Yarway Level Switch Calibration, and returned to service.

[

Unit II uses the same type of instrument' in this application; however, a generic review revealed no inherent problems.

l t

l I

i 7

a

{

f s

. i 1-

---m-

--i-,,