05000366/LER-1982-089-03, /03L-0:on 820808,control Rod Movement Procedure Violated While Withdrawing Control Rods.Caused by Rods 30-31 & 22-23 Being Withdrawn Past Proper Rod Position During Startup.Control Rods Reinserted.Procedure Continued

/03L-0:on 820808,control Rod Movement Procedure Violated While Withdrawing Control Rods.Caused by Rods 30-31 & 22-23 Being Withdrawn Past Proper Rod Position During Startup.Control Rods Reinserted.Procedure Continued

ML20027B244
Person / Time
Site:	Hatch
Issue date:	09/02/1982
From:	Sumner H GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20027B240	List: 05000366/LER-1982-089, Forwards LER 82-089/03L-0 05000366/LER-1982-089-03, /03L-0:on 820808,control Rod Movement Procedure Violated While Withdrawing Control Rods.Caused by Rods 30-31 & 22-23 Being Withdrawn Past Proper Rod Position During Startup.Control Rods Reinserted.Procedure Continued
References
LER-82-089-03L, LER-82-89-3L, NUDOCS 8209160578
Download: ML20027B244 (2)

LER-1982-089, /03L-0:on 820808,control Rod Movement Procedure Violated While Withdrawing Control Rods.Caused by Rods 30-31 & 22-23 Being Withdrawn Past Proper Rod Position During Startup.Control Rods Reinserted.Procedure Continued

Event date:
Report date:
3661982089R03 - NRC Website

text

-

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7 771 LICENSEE EVENT REPORT

1. CONTROL BLOCK: l l

l l

l l

l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATioN) i e

[o_,Li_] l G l A l E l I l H l 2 l@l 0 l0 l-10 l010 l010 l-l010 l@l4 l1 l1 11 l1 l@l l

l@

7 8 9 LICENSEE CODE 14 16 LICENSE NUMBER 25 26 LICENSE TYPE JO

$7 CAT b6 CON'T IoI1l SUR$l Ll@l 0 l 5 l 0 l 0 l 0 l 3 l 6 l 6 l@l 01 81 0l 8l 8l 2l@l0 l 9 l 0 l 2 l 8 l2 l@

i 8

60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h o 2 l While withdrawing control rods during a normal startup, it was discov-l 10 l a l l ered that control rod movement procedure had been violated. Rods 30-31 l lO la i l and 22-23 had been withdrawn past the proper notch position without l

in isi l banking the other rods in the rod group to their proper notch postF. ion.l io is i l This is a violation of Tech Specs 3.1.4.1 because Rod Worth Minimizer l

lo l7l I was bypassed. The health & safety of the public were not affected by l

iOis i i this non-repetitive event.

l 80 7

8 9 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE lRlBl@ lAl@ J @ lZlZlZlZlZlZ l@ W@ W @

o 9 7

8 9

10 11 12 13 18 19 20 SEQUEN TI AL OCCURRENCE REPORT REVISION LE H;RO EVENTYEAR REPORT NO.

CODE TYPE NO.

O,Rg l21 81 2l l-l l0 l8 l9 l y

l0l3l l Ll 9

W 22 23 24 26 27 28 29 30 31 32 l

E N 'SCWO4 O#tfdT

'ZU WD ROuRS O22 ^'u8E" TEE' pod"U8. "Tu?PtW ufNUlfCTu"JER

^

S

,, j @

l0 l0 l0 lY l Qg Wg gg l Zl 9 l 9 l 9lg Z

d@l.G jg [5Z j g [36 33 34 _

3,,_

3/

40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i m l During normal reactor startup, rods 30-31 and 22-23 were withdrawn past i 1

li lil l their proper rod position without moving the other rods in the group to i 1

,, i their proper positions. The control rods 30-31 and 22-23 were inserted i i, 13; l to their proper positions and rod withdrawal proceeded in accordance l

D T 1I with the control rod movement procedure.

i

'SfMs*

^

% POWER OTHER STATUS DIS O RY DISCOVERY DESCRIPTION W @ l0l0l0l@l NA l

O g l Operator Observation

[

i s 1

M 4

4 4

80 A TivlTY CO TENT RELE ASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE

[.Zj@ ] gl NA l

l NA l

1 6 PERSONNEL EXPOS ES NUV9ER TYPE

DESCRIPTION

l0l0l0l@lZl@l NA l

i 7 8

PeRsONNE t iNau' lies DESCRIPTION @ NA NumE R li lR I I 010101@l l

7 8 9 11 12 80 T PE DESCR PT ON

[ ZJ@l NA l

i 9

" *,,PuotETY 8209160578 820902 80 I 2 I O l L dE @DESCRIPTIONb PDR ADOCK 05000366 NRC USE ONLY issU PDR l

NA S

g

,,, 9

,lg 7

8 9 10 68 69 80 7.

NAME OF PREPARER PHONE:

/

LER #:

50-366/1982-089 Licensee:

Georgia Power Company Facility Name:

Edwin I.

Hatch Docket #:

50-366

Narrative

Report for LER 50-366/1982-089 On 8-8-82, during normal reactor startup for the purpose of going critical and subsequently increasing to full power o per a t ion,

rods 30-31 and 22-23 were not withdrawn in accordance with control rod movement procedure.

At this time Rod Worth Minimizer was manually bypassed.

Rod 30-31, the first rod in rod group 3,

was withdrawn to position 48 full out.

Rod 22-23, the second rod in group 3,

was withdrawn to position 08 at which point the reactor went critical.

Startup continued in a

normal fashion as a

heat-up rate was established.

During the process of heating up the plant, operator observed that rods 30-31 and 22-23 had not been withdrawn in a banked configuration with the rest of the rods in group 3 as specified by control rod movement procedure.

The health and safety of the public were not affected by this non-repetitive event.

Rods 30-31 and 22-23 were inserted to 04 and the rest of the rods in group 3 were then withdrawn to 04 and rod movement continued in accordance with control rod movement procedure.

Because Rod Worth Minimizer was manually bypassed at this time; this event was a violation of Tech Specs 3.1.4.1.

To preclude recurrences of this nature, strict adherence to the procedure has been stressed to operations personnel.