ML20027C806

LER 81-040/01T-0:on 811201,when Rx Pressure Decreased to 32 Psig,Rod N-9 Notched from Position 02 to 04 & Then to Position 06.Cause Unknown.Work Request Issued to Check Single Notch Control Switch During Next Refueling Outage

ML20027C806
Person / Time
Site:	Dresden
Issue date:	12/07/1981
From:	Schroeder B COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20027C803	List: ML20027C802 ML20027C806
References
LER-81-040-01T, LER-81-40-1T, NUDOCS 8210270254
Download: ML20027C806 (3)

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p EVENT pssensPr ON AND PetOS ASt.E CONSEQUENCES bio g puring unit startup Ex pressure was beTng maintained at about 50 psig.in preparation forl I system operability :est. WhenRxpressuredecreasedto32psig,rodN-9wasnotche]

r l from position 02 to 04. I'nexpectedly, the rod went to position 06 nd less than a 5 1 EI l 4 second period resulted (T.S. 6.6.B.1.d). The reactor scram:ned dua to IRM Hi Hi. There g j l.2.l 2.J l 1 was no effect on public health or safety because all Rx protbetive systems functioned I El as designed. Previous occurrence: I d

R.O. 50-237-76-74.

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} g lThe cause of the t:nexpected rod mover ent from position 02 to 06 fg tinknown . Tha .iinte 1 4

} , i jnotch control switch operation and proper latcbing of the rod (nr varicio peq @ =) I guere s,ubsequently verified with no difficulties identified. Vork requent has heet l l1ssued to check single notch control switch during the next refueling outare. On-site l reviev conducted to ensure no safety lietits were exceeded prior t2 unit startuo. 1

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U ATTACHMENT TO LICENSEE EVENT RGORT S1-10/01T-0 j CO'C'Or.JFETH EDISCN COM'ANY (CWE) f DPISDEU UNIT 3 (ILDRS-3)

DOCKET e 050-249 During unit startup,' Rx pressure was being etaintained at '

about 50 psigi in preparation for KPCI system operability test.

, k~ hon Rx pressure decreased to about 32 psig, rod N-9 weis notched

from position 02 to 04. Unexpectedly, the rod went from position t 02 to 06. The rod notch override twitch was not being used at

the time and rod withdrawal was in accordance with approved station H procedures and control rod withdrawal sequecces. This caused a 6 Rx scram (IRM Hi-Ili trips). A review of SFR and IFR recorders indicated that a less than a five second period (T.S.6.6.B.I.d) occurred prior to the reactor scram.

The cause of the unexpected rod riovc= sat from 02 to 06 is unkncun. The single notch control switch operation and proper latching of the rod (at various positions) were subsequently I verified with no diffleultics identified. The control rod timing j was checked and found to be slightly fast, but within Tsch. Spec. _

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limits. The timing was adjusted and rechecked. The CRD drive pressure was nernal. A work request has been issued to check the ' hf g timing and centact condition of the single ncich control switch Q

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l during the upcoming refueling outage. i k The results of the on-site investigation and review by tne i j Nuclear Fuel Services Department found that no safety limits were j exceeded. There was no effect on public health or aafety because 7 j

all reactor protective systems functioned as designc?. If the F i control switch irvestigation proves inconclusive. the CRD will be

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replaced prior to startup at BOC-8. No further action oceaed necessary.

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c ae r i l ta rte or etviarios ccru==ro Rx Scram - IEM Hi Hi 12-1-81 1050 '. YV -

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y; g errics er t be istfe a t t e .a tng[5 % in nfr.tsin Rx critical and Rx pressure less then 50 psig, due to llPCI ' F'" r '1 #

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being inop., inserted rc.d N-9 fror. position 04 to 02. Rx vent subcritical and pressure E Jftr$

eventually decreased to 32 psig. Attempted to withdrew red r-9 with s'agle notch control , $ :k h.

.. : L, -ip3 switch fro position 02 to 04 but rod move.d out to position 06 and Rx scratrsed due to IRM ' !'y&

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R>. period to be less-thaaj'X Hi Hi. Preliininary icvestigation by ruclear engineers 4eter. lined

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i esof 5 ..l cer n A Ta se'. t%iNEts') cwc sts .,,p-i _ An irmned.iate review of tl..s SRM and IRM recorder traces indicated that a period of %jgM *%s, $:5'r p ug lees than 5 neconds occurred prior to the Rx scra. NFS and the nuclear er.gineers are h;M.y,gy, investigating. An onsite review vill be performed prict to Rx stattup.

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