05000249/LER-1981-040-01, /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

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/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 Constellation icon.png
Issue date: 12/07/1981
From: Schroeder B
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20027C803 List:
References
LER-81-040-01T, LER-81-40-1T, NUDOCS 8210270254
Download: ML20027C806 (3)
v • d • e


LER-1981-040, /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
Event date:
Report date:
2491981040R01 - NRC Website
v • d • e

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ATTACHMENT TO LICENSEE EVENT RGORT S1-10/01T-0 j

CO'C'Or.JFETH EDISCN COM'ANY (CWE)

DPISDEU UNIT 3 (ILDRS-3) f DOCKET e 050-249 During unit startup,' Rx pressure was being etaintained at i

about 50 psig 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 p

j was checked and found to be slightly fast, but within Tsch. Spec.

' hf limits. The timing was adjusted and rechecked. The CRD drive pressure was nernal. A work request has been issued to check the Q

g timing and centact condition of the single ncich control switch

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l during the upcoming refueling outage.

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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

all reactor protective systems functioned as designc?. If the F

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control switch irvestigation proves inconclusive. the CRD will be j

replaced prior to startup at BOC-8.

No further action oceaed j

f necessary.

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RPS icet Stirtup r,yu.3 3

, tc A: r,,,, i be stfe a t t e.a t [5 % in nfr.tsin Rx critical and Rx pressure less then 50 psig, due to llPCI ' F'" r Mm errics er t i

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being inop., inserted rc.d N-9 fror. position 04 to 02.

Rx vent subcritical and pressure E Jftr$

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

.. : L, ip eventually decreased to 32 psig.

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

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_ An irmned.iate review of tl..s SRM and IRM recorder traces indicated that a period of h;M.y,gy, p ug lees than 5 neconds occurred prior to the Rx scra. NFS and the nuclear er.gineers are

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investigating. An onsite review vill be performed prict to Rx stattup.

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