ML18348A261

From kanterella
Jump to navigation Jump to search
License Event Reports 1977-006-00 & 1977-008-00 Control Rod Misaligned
ML18348A261
Person / Time
Site: Palisades Entergy icon.png
Issue date: 02/02/1977
From: Hoffman D
Consumers Power Co
To: James Keppler
NRC/RGN-III
References
LER 1977-006-00, LER 1977-008-00
Download: ML18348A261 (4)


Text

.... ...

consumers

  • Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
  • Area Code 517 788-0550 February 2, 1977

~..r James G Keppler Office of Inspection & Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR

  • PALISADES PLANT, ER-77-06, ER-77 CONTROL ROD MISALIGNED Attached are reportable occurrences which relate to the Palisades Plant. These occurrences involve the misalignment of a control rod. Per telecon with Mr Ken Baker (NRC, Region III), an extension beyond the 14-day submittal was granted.

David P Hoffman Assistant Nuclear Licensing Administrator FEB 7 1977

. 9ut:ENSEE EVENT REPORT

  • Palisades CONTROL BLOCK:._!__.._..__..__...___.l~I [PLEASE PRINT ALL REQUIRED INFORMATION]

1 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

  • IM I I Ip I A I LI ii I oI ol -1 o I o I o I o I o1-1 o Io I I 41 i I ii ii ii Io I 1 I 7 8 9 14 15 25 26 30 31 32 FIEPOFIT . .F!EPORT

. TYPE** *SOURCE * '00CKl;T **NUMBER* ** *** EV.EN:f***DATE . REPORT CATE fal1 ICONT r **I -*I WllJ I ol 51 ol-lo l215l5r lol1l 1l 1l 1l 1I lo l2lol2l1l1I 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION lol2I I Following a feed-water pump trip, the operator a~tempted to avert a reactor trip by I.

7 8 9 80 lol3I I manually running in the control rods, but 4id not switch.mode selector from auto to I 7 89 . 80 lol41 I manual resulting iri rod No 38 being driven in 13.6 inches below the group before .I 7 8 9 80 lol51 *1 realizing the error. The other* operator immediately tripped the plant. I 7 8 9 80 lol6I ~'----------------------------------...,..----------------(ER 7 8 9 PRIME

__-7_7_-o_B_)______~I80 SYSTEM CAUSE COMPONENT COMPONENT COOE COOE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION 0

@0 lRI *Bt -~ ., c I 0 I Nl'RI *01p*DI *t!J* Ic I* 4* l9 *1o I L!J 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION Iola! I Personnel Error 1.

7 8 9 80 10191

~~

~9 9'--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~8~0 80 FACILITY METHOO OF 7

IIEI8 STATUS l..£1 9 10

% POWER 12 13 OTHER STATUS I 0 I 3 I 5 I .___,..,.._NA_ ____.,.I 44 w

DISCOVERY 45 46 Ol!;1COVERY DESCRIPTION l...,....__ _ _N_A_ _ _ _ _ _ _~I 80 FORM OF W I_____NA_ _ ____.I ACTIVITY CONTENT .

7 rn 8 RELEASED U]

9 OF RELEASE 10 11 AMOUNT OF ACTIVITY 44 45 LOCATION OF RELEASE NA 80 PERSONNEL EXPOSURES w

NUMBER TYPE .DESCRIPTION II§] I o I oI 01 NA 7 8 9 11 12 13 80 PERS.ONNEL INJURIES

. NUMBER DESCRIPTION 7

1IE18 9I oI oI ol11 12 NA 80 PROBABLE CONSEQUENCES lilll8 9 NA 7 80 LOSS OR OAMAGE TO FACILITY 7

[fil 8 9 w

TYPE 10 OESCRIPTION NA 80 PUBLICITY om 89 '****** .*

NA 80

  • ADDITIONAL FACTORS 7

DEi8 9 NA 80 NA DE 7 89 80

'l... * ~ -

9LlCENSEE -EVENT .REPORT. Palisades CONTROL BLOCK: I I I I J I I [PLEASE PAINT ALL REQUIRED INFORMATION]

1 6 LICENSEE UCEN SE EVENT NAME LICENSE NUMBER TYPE* TYPE

. IMIIIPIAILlll 1°1°1-1°1010101°1-10101 14 Ii 11 11 11 I I 01 1J B9 . 14 15 . 25 26 30 31 32 REPORT- REPORT

'"TYPE ,* .. 'SOURCE * ..... QQCKl;T 'NUMBER* . EVENT-

  • DATE* REPORT DATE.

fOl1lcoN'T f *-*pq. W U!.J I 01 51 01-1 o 12 I 5 I 5I I o I l I l I 71 7I 71 1012101211111 7 B 57 5B 55! 60 61 6B 69 . 74 75 BO EVENT DESCRIPTION lol 21_1 During critical approach for trip recovery, a RO trainee inadvertently pulled rods I 7 8 9 BO.

lol31 I. while in manual individual rather than manual sequential resulting in rod No 21 being I 7 B 9 . 80 lol41 I 9 .1 inches .above the lowest rod in the bank. He immedi~tely reinserted the rod back .I 7 B 9 80 lolsf J to bank level. (ER-77-06) I 7 8 9 80 lof6l 7 8 9 PRIME 80 SYSTEM CAUSE COMPONENT* COMPONENT

.@El t
Rl B-1 7 8 9 10 COOE w .'lC"f CODE .

11 . 12.

COMPONENT 'cooE 0 INYRl'"OlD) 17 SUPPLIER "l2!J 43 44 MANUFACTURER

  • 1c I 4 l9 *1 o I 47 VIOLATION w48 CAUSE DESCRIPTION Iola! I Personnel Error I 7 8 9 80 lalsl

~:___: _______________________________________ ___.::

FACILITY METHOD OF

. DISCOVERY DESCRIPTION w

STATUS  % POWER OTHER STATUS .DISCOVERY

[ill] ~ Io I al oI NA NA 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT rn RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

~

9 L!JI 10

- __N_A_ _ _____.,44.I 11 I

4.,..5------------------~80 NA.

7 8 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 7

IIEI8 9I o1 o1. °'

11 L~J 12 13 NA 80 PERS'ONNEL INJURIES NUMBER DESCRIPTION EEi I 01 01 0111 7 8 9 12 NA 80 PROBABLE CONSEQUENCES

"(ill] NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION EID~ NA 7 8 9 10 80 PUBLICITY

[ill] NA FACT~~s 8 80

  • :DDmONAL E1fil8 9 NA 7 80

[Tifil NA 7 89 80

_ j

consumers

  • Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
  • Area Code 517 788-0550 February 8, 1977 Mr James G Keppler Office of Inspection & Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - WITHDRAWAL OF ER_.:77 CONTROL ROD MISALIGNED By letter dated February 2, 1977, Event Report 77-06 for the Palisades Plant was transmitted to the Office of Inspection & Enforcement, Region III. After reviewing the event, the plant staff determined that this event was not re-portable and obtained the concurrence of the IE staff.

The reactor was subcritical at the time of the control rod No 21 misalignment and the event is, therefore, not reportable per the re~uirements of Technical Specifications, Section 3.10.4.a. LER-77-06 is, therefore, withdrawn.

David P Hoffman Assistant Nuclear Licensing Administrator FEB 10 1977