ML18347B178

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License Event Report LER-78-000-00 Re Out-of-Sequence Rod Withdrawal
ML18347B178
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/28/1978
From: Hoffman D
Consumers Power Co
To: James Keppler
NRC/RGN-III
References
LER 1978-000-00
Download: ML18347B178 (2)


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consumers Power

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-.-"J company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

  • Area Code 517 788-0550 April 28, 1978 _:,,, ..,.,,
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Mr James G Keppler r:n ~

Office of Inspection and Enforcement <!> '-9 Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LER OUT-OF-SEQUENCE ROD WITHDRAWAL The reverse side describes a reportable occurrence under Technical Specifi-cation 6.9.2.A.2 for the Palisades Plant. This event was identified by TWX on April 17, 1978.

David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement

NRC FORM366

  • PALISADES U.S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT CONTROL BLOCK: I 1

10 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~8 IM I I I p I A I LI 1 101 010 I 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 101 411 11 I ll l 101 I 10 7 9 LICENSEE CODE 14 ~5 LICENSE NUMBER

  • 25 26 LICENSE TYPE JO 57 CAT 58 CON'T

!TI:!]  :~~~~~ ~I o I 5 I o I o I o I 21 5 I 5 IG)I o I 4 11 I 5 I 71 8 I© I o I 4 I 2 I 8 I 7 I 8 10 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

IDuring Low Power Physics Tests, regulating group 2 rods were withdrawn out-I

!]JI] jof-sequence ... This is contrary to the requirements of TS 3.10.5.b and the CQIIJ jLow Power Physics Test procedures. The out-ofmsequence maneuver occurred

[£ITJ Jduring sequential rod worth measurements when a faulty position indication C2:I§] 1for CRDM '#.25 (group 1) indicated it was fully withdrawn. When the condi-t m2J 1 tion was detected, a different target rod was selected and the test con-

[]]]] tinued. Continuous boration was in progress.

1 I 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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7 8 IRIB I@

9 10 w@ w@ 1c1R1n1R1v1E1@ w@

11 12 13 18 19 w@

20 SEQUENTIAL OCCURRENCE REPORT REVISION r.:;.., LE RIRO CV ENT YEAR REPORT NO. CODE TYPE NO.

'0 REPORT NUMBER I 7I8I .

21 22 l==J 23 101"0191*

24 26 L::j 27 10111 28 29 L!J 30 L=J J1 L2J 32 ACTION FUTURE EFFECT SHUTDOWN r:;::;., ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM ~UB. SUPPLIER MANUFACTURER W@W@ LI.JC§) ~ I ol o Io Io I lli.J@ 1.1U@ LBJ@ I c 14 19 Io l@

33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

jThe operators and test engineer failed to realize that selecting a target

!J:II] 1rod with defective position indication might result in improper sequencing.!

EIJ]J 1Precautionary statements have been added to the reactor control system IJ:II] Joperating procedure and the yellow engraved tag installed on the control IJJ3] 1room console adjacent to the rod selector switches.

7 B 9 80 FACILITY IJQ\ METHOD OF STATUS  % POWER OTHER STATUS \.:::;J DISCOVERY DISCOVERY DESCRIPTION

[ill] lliJ@ Io Io I o l@I N/A LJU@I Operator Observation 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT r:::;;.,

RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @

[2]TI Lk.J@ UJ@I N/A I 45 N/A 8 9 10 11 44 80 PERSONNEL EXPOSURES ~

NUMBER r:;::;., TYPE DESCRIPTION

[2IZJ I o I o I o lLJ@ __N_/_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____.

7 8 9 11 12 13 80 PERSONNEL INJURIES Q NUMBER DESCRIPTION~

~ Io I o I ol@.___N_:./_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____.

7 8 9 11 12 80 LOSS O* OR DAMAGE TO FACILITY 143' TYPE DESCRIPTION '.:::::J

[Q2:) ~@).___N_/A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____.

7 8 9 10 80 PUBLICITY C\ NRC USE ONLY ISSUED(,;\ DESCRIPTION~

. [ill] lJLJ6~_N...:.../_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __. II IIIIIIII III 7 8 9 10 58 69 80