ML20064H471

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Reportable Occurrence 50-219/78/33-1P on 781214:during Routine Reactor Startup Following Scram from Full Pwr,A Reactor Scram in Range 1 of IRMs Occurred for Less than 5 Seconds.There Was No Safety Significance
ML20064H471
Person / Time
Site: Oyster Creek
Issue date: 12/14/1978
From: Rone A
JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML20064H465 List:
References
NUDOCS 7812200240
Download: ML20064H471 (2)


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Ceca per,_1j,, 1773 Cccurrance:

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'eport Date:

Ca rcer i1 1973 Occurrence:

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Oy!rER CREEK NUCLEAR GPIERATING STATICN 70RKED RIVER, NEW,lERSEY G8731 Reportahte Ccc>rrevne Reoort No. 50-21!1/78/33-1P

[DENTIFICATION While per'orming a routine reac tor startup following a :; cram

'F OCCURRENCE:

f rom ful l powe r, a reactor pecico less tnan five seconds occurred resulting in a scram in range one of tne IRH's.

This event is considered to be a reportable occurrance as defined in the Technical Speci fica tions, partgrapa 6.9.2.a 4

CNDITIONS PRIOR Steady State Po er Rmtine 3burdown TO OCCURREhCE:

' ot Stancby Operation d

Cold Shutdown Lead Changes During Refueling Shutdown 2cutine Power Cperation X

Routine S tar +.up Other (5:eci fy)

Operation Mouerator temp.:

3UG"F.

Reactor pressurs:

190 psig Recirculation flow:

5.2 x 104 gpm Snucce Range monitor count rate:

450 c;s Reactor at peak xenon.

Rod worth minimizer in service withdrawal sequence VIII A-1.

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ESCRIPTION Co December 14,1978, at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />, a reac tor scram occurr+c 1F CCCURRENCE:

in rance one of the IAM's.

At the time of the scram, con trol rods were being withdrawn for.sporoach to critical as part of recovery operations following a scrma from full power at approx-imately 19C0 nours on Cecceber 13.

Because of tne high xenon concentrations, an accurate estimated critisal position was rn*.

possible.

The operator at tne controls was using SRM count rote informition as the guide for approach to cri t 'cil.

Since the 3 M count i ate had changed only slightly (425 tn 450 cps) from th(

start of the rod withdrawal crecess, it was thougnt that the reactor was still strongly subcritical; hence. rods were being withdrawn in t4e ' notch override mode.'

Whan cen*.rol rod 10-41 (first rod in Group 9) was witndrawn to notch aesition (10), tne reactor becant critical on an estimated 2.3 seccod r+riod.

The operator atteupted to insert the rod using the 'e erger.cy rod in" control switcP. to no avail.

Tha neutron f1,;.x.ncursi Sn was terninated by a reactor scram in range ene of the IRF's.

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