ML20084N691

From kanterella
Jump to navigation Jump to search
AO 50-249/75-41:on 750908,intermediate Range Monitors 11, 12,14,16 & 18 Failed to Respond During Plant Startup. Apparently Caused by Personnel Accidentally Loosening Cables.Cables Replaced
ML20084N691
Person / Time
Site: Dresden Constellation icon.png
Issue date: 09/16/1975
From: Stephenson B
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20084N693 List:
References
611-75, NUDOCS 8306080428
Download: ML20084N691 (2)


Text

-

i; -

d Comm:n Ith Edison n () b

/r' a One First National Plaza. Chicago. Ilknois

\'

' /l Address Reply to: Post Office Box 767 '

(QC Chicago, Illinois 60690 BBS Ltr. #611-75 Dresden NUclea:' Power Station R. B. #1 Morris, 2,11nois 60450 September 16, 1975 . . ,

m

< t , * . ! !- (

m, -

s'-

Mr. James G. Keppler, Regional Director '

f Directorate of ReEulatory Operation-Region DI ' #

' -s y, - ,

U. S. Nuclear Regulatory Comission '

s 799 Roosevelt Road -

Glen Ellyn, Illinois 60137

'1

SUBJECT:

REPORT OF AENORMAL OCCURRE!CE PER SETION 6.6.A OF THE TEENICAL SPEC FAILURE OF INTER'GDIATE RA';GE FONITORS TO B SPOND R;ferences: 1) Regulatory Guide 1.16 Rev. 1 Appendix A ,

2) Notification of Region III of U. S. Nuclear Regulatory Corr.tission Telephone P. Johnson.1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on September 8,1975 '

Telegram: J. Keppler,1950 hours0.0226 days <br />0.542 hours <br />0.00322 weeks <br />7.41975e-4 months <br /> on Septcmber 8,1975 i.

R: port Number: 50-249/75-41  :

\

Report Date: September 16, 1975 Y 1

Occurrence Dates September 8, 1975 Facility: Dresden Nuclear Power Station, Morris, Illinois .

IDENTIFICATION OF OCCURRENCE Intermediate range monitors (IRM's) 11, 12, f4,16,and18failedtorespondduring s

plant start-up.

.This occurrence represents a failure,to meet limiting ecnditions

  • for operation as defined in section 3 1 of the Technical Specificationci
  • e CONDITIONS PRIOR TO OCCURRRICE .

Control rod withdrawal Unit-3 was in the start-up mcde at a power level of 4100 IGt.

was in progress.

~

DESCRIPTION OF OCCUBRBICE At approxd:::ately 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on September.8.1975, the Unit-3 reactor was brought critical for plant start-up. As reactor Lower was increased An immediate it was noted that investigation five of the eight IRM's did not appear to be responding.

8306080428 750916 wn. <

PDR ADOCK 05000249 PDR '

vi .] .

S r s ar,' -

M M

T

~ z r --

9 m

k James G. Keppl r'! . . Sehber 16, 1975 .

\ +

s

% \ .

indicated that the problem was intrinsic to the IRM's themselves rather than the 1; cal instrumentation, and a reactor shutdown,was commenced. Control rod insertion began at 0510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br />, witRall rods "in" by 0559 hours0.00647 days <br />0.155 hours <br />9.242725e-4 weeks <br />2.126995e-4 months <br />.

(

DESIGNATION OF APPARF2;P CAUSE OF OCCURRDiCE (Unusual Servicd Conditions)

\

Th:; IRM cables appeared to have been inadvertently pulled "open" by personnel working underneath the reactor vessel in cramped quarters. In addition, water was found in come of the cable connecto- c, whi:h undoubtedly contributed to the IRM response proble,1ss i The water probably entered the table connectors during the initial vessel

" hydro" Onen control rod drive flanges were discovered leaking.

ANALYSIS' 0F OCCURRENCF N

Although the IRM's would ha've been incapable of providing scram protection, the 15fo i cvarage power range monitor (APPJ1) scram logic was in effect throughout the start-up mode. Furthermore, the rod worth minimizer was operable, preventing any deviation from the established rod withdrawal sequence. Consequently, plant personnel and th3 public were not. endangered by th n occurrence. l

~

l CORRECTIVE ACTION i

The faulty IRM cables were replaced from the junction boxes in the drywell to the IRM connectors. In order to prevent a similar recurrence, the master start-up

. checklist will be revised to include a resistance check on Source Range Monitors

- (SRM's) and IBM's when c:ajor work has been performed under the reactor vessel. This i fins 1 check will be performed prior to start-up, after all work under the vessel l has been complettd.

1 FAILURE DATA s There have been no previous (IRM failures of.this nature at Dresden.

( B. 3. Stephenson I Superintendent BBS:CES:scp J File /NRC q

<\

i 1