ML19345G102

From kanterella
Jump to navigation Jump to search
Ao:On 750315,while Exercising Control Rod Drives,Control Rod E-4 Stuck at Notch 00.Malfunction Does Not Impair Ability to Control Reactor.Maint Will Be Performed on Rod to Determine Cause of Sticking During Next Refueling Outage
ML19345G102
Person / Time
Site: Humboldt Bay
Issue date: 04/14/1975
From: Crane P
PACIFIC GAS & ELECTRIC CO.
To: Goller K
Office of Nuclear Reactor Regulation
References
4147, NUDOCS 8103020360
Download: ML19345G102 (1)


Text

.

s.

PACIFIC CrAS AND E LE C T ILIC C O M PANY F6WIE j

77 BEALE STREET

  • SAN F R A N CISCO, C ALIFOR N f A 94106. (415 ) 781-4211

"""c o""'**"

r:
':::w.;7:::~

vies eus,os.,.".e unni cou m

..,.., g.;.....7,,,.;.....

eg;,. ;,,y,.......

D-*8**'m'******

uALcoLuM.FuaeusH

.SSOCl ATE totnet.LL COUeniKL April 14, 1975 '

w.u..-...uo..

.y';g:..

5.:.:.,:..p5.:.:.5q,.,

c,,,.6.,.,,,...u.,,.

-... e o 6 -......, u o.

4-

  • 1=:::::.
==:n:::::,,

e..u....e....s..

L

.:::::::::: ~~
nu~.::::,....

-a,v o.t..t

; r
: :, ;.,,.

.ic.<a oa.cea

.e c::::.:cc:............... ira:. :::-~~~

so-.....sa v.',

A e m-s L

Mr. Karl R.

Goller I

Office of Nuclear Reactor Regulation C, f.,

U. S. Nuclear Regulatory Commission ~

Vf Washington, D.

C.

20555 Re:

Docket No. 50-133 License No. DPR-7

Dear Mr. Goller:

'x,__.p' Pursuant to Section IX.H.2.b. (2) of Appendix A to the Humboldt Bay Unit No. 3 Facility Operating License, we are hereby notifying you of a malfunction of control rod drive E-4.

On March 15, 1975, while exercising control rod drives in accordance with Technical Specification require-ments, control rod E-4 stuck at notch "00" (fully inserted).

Several attempts were made to move the rod from its stuck position, all of which were unsucressful.

The maintenance history card for the control rod drive showed no previous problems with the drive.

It has been determined by investi-gation that the malfunction does not impair the ability to control the reactor and that the impairment of the perform-ance of additional components of the control rod system is not imminent.

The Unit has continued operation with control rod E-4 fully inserted.

Maintenance will be performed on the rod to determine the cause of the sticking during the next refueling outage, which is scheduled in June.

There was no activity released, no personnel exposure or injuries, no off-site consequences nor damage to the facility as a result of this control rod drive malfunction.

er truly you

/)

t P

lip A rane, J PAC:m cc:

Mr.

R.

H. Engelken g ; y '7 U.

S. Nuclear Regulatory Commission msoaoJ55" P00R ORIGINAL

_