ML20085E621

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LER ER-76-002:on 760116,as-found Setting of Reactor Protective Sys Switch PS1804 & Safety Injection Sys Switches PS1801A,PS1803A & PS1804A Found Out of Calibr.Cause Not Stated.Setpoints Adjusted
ML20085E621
Person / Time
Site: Palisades 
Issue date: 02/04/1976
From: Bixel D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
LER-ER-76-002, LER-ER-76-2, NUDOCS 8308150441
Download: ML20085E621 (2)


Text

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bSEE EVENT REPORT O

Palisades CONTROL 8 LOCK:l l

l l

l l

l (PLEASE PRINT ALL REGUIRED INFORMATION) 1 8

NAME UCENSE NUMBER PE TT O1 l Ml Il Pl A l L l Il l0 l0 l-l 0l 0l0 l 0 l 0l_l 0l0 l l hl 1l 1l1l 1l l0l3l 7 89 14 15 25 26 3C' 31 32 l

NE DOCKET NUMdER EVENT DATE REPCRT DATE TYPE O 1 CON'T l l

l M

(,L_l l0 l 5 l 01-l 0 l2 l 5 l Sl l 0l1 l1l 6l Tl 6l l 0l 2l0 l hl7 l 6l 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION 95 l Durine testine the RPS switch as found setting of PS180h was out of calibration j

7 89 80 Q l by + 0.2 psi.

SIS switch as found settings of PS1801A (right) and PS1803A (left l

7 89 80 EE l and right) were out of calibration by -0.05 nsi.

SIS switch PS180hA (left) was l

7 89 80 M l found with intermittent contacts (microswitch). The set noint changes reuresent l

7 89 80 HE l changes of from 1 to h%.

All set noints vere ad.1usted and microsvitch renlaced.

l

.S'E Co"cE CouPoNENT CCCE ACTU U VOLATON e I Il A l IE l lIl Nl S IT l R lU I W

lUl0l7l5l lYl l

7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION DE l There are a total of 8 containment pressure switches manufactured by United l

7 89 80 0

-l v, actric. 9eM es 900. Model J 702-553.

Each PS has two switches with individually l 7 89 80 Q l ad.1usted set points. The one microsvitch replaced was P/N BZR814-A2. The l

FAtluTY METHOO OF STATUS

% POWER OTHER STATUS DISCOVERY CisCOVERY CESCAFTON LeJ l Ol al 01 I UA I

Lt.J l

NA I

1 7 8 9

10 12 13 44 45 46 80 RELE SED OF REL AMOUNT CF ACTMTV LOCATON OF AELEASE E5 lZl

[Zj SE l NA l

l NA l

l 7 8 9

10 11 44 45 80

)

PERSONNEL EXPOSURES NUMBER TYPE CESCRIPTON l

DE 1010101 LZJ l

NA l-7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTON l 0l 0l 0 [

l NA 1

l 7 89 11 12 So PROBABLE CONSEQUENCES

]E l Since other settings were found satisfactory, this vould not have lead to improper l 7 89 initiating.

So LOSS OR OAMAGE TO FAC!UTY TYPE DESCAPTCN

@Wl UA l

7 88 18 8308150441 760204 80 PUBLICITY PDR ADOCK 05000255 6

H l NA PDR l

7 89 80 ADDITIONAL FACTORS 3l (Cause Description Contd) application of these switches is well within their l

/ 89 80 DE l specified capabilities. Additional testing vill be performed to determine l

7 89 further action.

80

O O

x General Offices: 212 West Micmgan Avenue Jackson, Michigan 49201. Area Code S17 788 0550 February 5, 1976

  • si %g 4

s Mr James G. Keppler i

I pg2I/Q Office of Inspection Enforcement 7,

g Region III US Nuclear Regulatory Co= mission T99 Roosevelt Road Gut N

S Glen Ellyn, IL 60137

\\

DOCKET 50-255, LICENSE DPR 2 PALISADES PLANT, ER-76-02 FPS / SIS - PS OUT CF CALIBRATION Attached is a reportable occurrence which relates to the Palisades Plant. This occurrence has been classified as a reactor protection system or engineeged safety feature instrument setting which was found to be less conservative ~

than those established by the Technical Specifications but which do not prevent the fulfillment of the functional requirements of the affected system.

/v f~ '

f V

~

.v C David A. Bixel Assistant Nuclear Licensing Administrator CC:

File 1466 ya ce, e