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NRC FORM 368                                                                                                            U. E. NUCLE AR REQULATORY COM4flSSION (7 77) t.ICENSEE EVENT REPORT                                                                EXHIBIT A CONTROL BLOCK: l l i
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PHONE:          !*        bb*
7901150')T
 
1.
Repor?4ble Occurrence Report TJo. 50-368/7t!-22
: 2. Report Date: 01-03,79                3. Occurrence Date: 12-19 78 4    Facility: Arkansas Nuclear One-Unit 2 Russellville, Arkansas
: 5. Identification of Occurrence:
This ROR concerns the failure to take corrective action required by technical specification 3.1.3.1.
6    Conditions "rior to Occurrence:
Steady-State Power                      Reactor Power              MWth Hot Standby                X          Net Output
_                                  HWe Cold Shutdown                            Percent of Full Power        %
Refueling Shutdown                      load Changes During Routine Power Operation Routine Startup Operation Routine Shutdown Operation Other (speci fy)
: 7. Description of Decarrence:
During approach to criticality, safety group CEA A-52 stopped withdrawal at approximately 144 inches withdrawn due to a failed lift (011.
g . . . . .      . ~ a ,. :.
 
Reporta>1e Occurrence Report No.      50-368/78-22
: 8.      Designation of Apparent Cause of Occurrence:
Design                              Procedure Ibnufacture                          Unusual Service Condition including Environmental Installation /
Const ruct ion                      Component Failure (See Failure Data)
Operator Other (specify)    X NRC inspector interpretation of technical specification
: 9.      Analysis of Occurrence:
1he CEA was known to be trippabic, aligned within 7 inches of other group A rods, and was within limits for full out position; Therefore, the CEA was considered as operational, and mode 2 operation was established.
 
Reportable Occurrence Report No. 50-368/78-22
: 10. Corrective Action:
With the NRC ruling that the CEA was inoperabic, the plant should have confomed with the requirements of action statement T.S. 3.1.3.1.c, which would not allow the mode change from 3 to 2.
: 11. Failure Data:
      'Ihis incident did not endanger the health and safety of the public since the CEA was trippable and is considered an isolated occurrence.}}

Latest revision as of 19:22, 1 February 2020

LER 78-022/01T-0 on 781219:safety Group Control Element Assembly A-52 Stopped Withdrawing at 144 Inches Withdrawn. Caused by Failed Lift Coil
ML19267A345
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 01/03/1979
From: Shively C
ARKANSAS POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19263B246 List:
References
LER-78-022-01T, LER-78-22-1T, NUDOCS 7901150071
Download: ML19267A345 (4)


Text

..

NRC FORM 368 U. E. NUCLE AR REQULATORY COM4flSSION (7 77) t.ICENSEE EVENT REPORT EXHIBIT A CONTROL BLOCK: l l i

l l l

.h l (PLE ASE PRINT OR TYPE ALL REQUIRED INPORMATION) 8 lAIRIAldlOl7l@16l olol-l o lo lo clo l-lolol@ldl I l I ll1l@l P S 9 UCENsEE CODL to uctNst NuusEm 26 26 UC&NSE TV,5 40 67 CATI tol@

CON'T o i I $ Ou's 6L.L_)@lo l foOCK6T 8, I o loNvMBP ER131' 18 l@l i EVENT 6A GG I 2-1

  • 91'r Bl@lol8 DATE 74 16 RE, olJ ORT oATE 7 19l80 @

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Oio o 2 lDurlna ,a doewoeth ii Es cy;U c,s\* A v ..folloWIno, A f eh.40c br*. s dt.o' n e, 90wler I f-

$4bhis broun OEA A-s2 &nnect withdravial a -

- Ikstzebe'wTedtng .e, f o 4 1l44 abikr "R(hdrauln due lo 7. alled Ik cod . cEA i.>as kaaion to be, o s It cI. M.le, dinned (dikr.tA 'I 'ndes ed cher brouc k rodk. and tuas Widid o e IUm'sh5 Iof[ull cul 'tOs;Uon'.deve[twe; de DEA roar cows:Jered as nost Mah ITTTI l. bad Mode 2 DoerdloA h)As eMided Me NE in5, h edof \&kof kbedl o a ib Ntens,ee kh i khls iMt an t'nterred inke#DeldE.ho Em'ihar ocewr(set *5.

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7901150')T

1.

Repor?4ble Occurrence Report TJo. 50-368/7t!-22

2. Report Date: 01-03,79 3. Occurrence Date: 12-19 78 4 Facility: Arkansas Nuclear One-Unit 2 Russellville, Arkansas
5. Identification of Occurrence:

This ROR concerns the failure to take corrective action required by technical specification 3.1.3.1.

6 Conditions "rior to Occurrence:

Steady-State Power Reactor Power MWth Hot Standby X Net Output

_ HWe Cold Shutdown Percent of Full Power  %

Refueling Shutdown load Changes During Routine Power Operation Routine Startup Operation Routine Shutdown Operation Other (speci fy)

7. Description of Decarrence:

During approach to criticality, safety group CEA A-52 stopped withdrawal at approximately 144 inches withdrawn due to a failed lift (011.

g . . . . . . ~ a ,. :.

Reporta>1e Occurrence Report No. 50-368/78-22

8. Designation of Apparent Cause of Occurrence:

Design Procedure Ibnufacture Unusual Service Condition including Environmental Installation /

Const ruct ion Component Failure (See Failure Data)

Operator Other (specify) X NRC inspector interpretation of technical specification

9. Analysis of Occurrence:

1he CEA was known to be trippabic, aligned within 7 inches of other group A rods, and was within limits for full out position; Therefore, the CEA was considered as operational, and mode 2 operation was established.

Reportable Occurrence Report No. 50-368/78-22

10. Corrective Action:

With the NRC ruling that the CEA was inoperabic, the plant should have confomed with the requirements of action statement T.S. 3.1.3.1.c, which would not allow the mode change from 3 to 2.

11. Failure Data:

'Ihis incident did not endanger the health and safety of the public since the CEA was trippable and is considered an isolated occurrence.