ML20064H471
| 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) | |
Text
a nitial *el?ctone cate of
'eport Da t e.
Ceca per,_1j,, 1773 Cccurrance:
Dec e--b e r
' ', '?'S nitial Wr.t an
'Imo of
'eport Date:
Ca rcer i1 1973 Occurrence:
415 s
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.
i
- 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At the time of the scram, con trol rods were being withdrawn for.sporoach to critical as part of recovery operations following a scrma from full power at approx-imately 19C0 nours on Cecceber 13.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 rods were being withdrawn in t4e ' notch override mode.'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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