05000312/LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted

Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted

ML19343C533
Person / Time
Site:	Rancho Seco
Issue date:	03/17/1981
From:	Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML19343C534	List: 05000312/LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted 05000312/LER-1981-011-03, /03L-0:on 810217,reactor Bldg Sump/Decay Heat Removal Sys Flow Path Obstructed.Caused by Installation of Blank Test Flanges on Suction Lines.Flanges Removed & Test Procedure Revised
References
NUDOCS 8103240453
Download: ML19343C533 (1)

LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
3121981011R00 - NRC Website

text

-

~

1SMUD 95813; (916) 452-3211 v SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, Box 15830, Sacramento, California March 17, 1981

<s

.'N *AW -.

. gg y 3

Mr. R. H. Engleken, Director Region V Office of inspection & Enforcement ej..._. S g Walnut Creek P16za, Suite 202

-, Q <$

1990 North Can'fornia Boulevard t

~

Walnut Creek, CA 94596 g".Y 3

/T/*.Zn

' '. s Re: Operating License DPR-54 k &['/.

4 Docket No. 50-312 Reportable Occurrence 81-11 "hlf, g

' [~ ~4

^

~-t y ke,y u

's I

Dear Mr. Engelken:

In accordance with Technical Specifications for 46p' Rev.i s.iiry,ar/

ho Seco Nucle(

Generating Station, Section 6.9.4.2c, and Regulatory Guide is y jgbnfit t i ng i

Section C.2.b(3) the Sacramento Municipal Utility District a thirty-day report of Reportable Occurrence 81-11.

On February 17, 1981, during refueling operations, a condition was established in which blank flanges were installed on the inlets to both DHR The blank flanges were installed in suctions from the reactor building sump.

preparation for the Local Leak Rate Test of building penetration numbers 30 and 31.

Although there are no specific requirements or restrictions associated with the RB sump lines during cold shutdown, a need for access to the sump could that water was inadvertently lost f rom the reactor or fuel arise in the event canal during refueling operations. Being cognizant of this, the procedure gov-erning refueling, STP 227, addressed the status of the DHR systems and the RB s mp lines via an applicable limit and precaution. However, the surveillance procedure under which the Local Leak Rate Test was being performed, SP 205.02, did not specify any restrictions associated with the sump lines.

fuel movement was stopped until Upon discovering the discrepancy, the blank test flanges were removed. The surveillance test, SP 205.02 - Local Component Leak Rate Surveillance Testing, has been revised to specifically pro-installing blank test flanges on both RB sump lines simultaneously.

hibit Since the plant was shutdown for refueling, there were no transients nor power reductions associted with this event.

Respectfully submitted,

/1/;ocO.

.s ohn J. Mattimoe

/f Assistant General Manager and Chief Engineer l&E Washington (30) cs:

MIPC (3) ~

810824 OEPRl-NSAC

--c4 tiro eg $

NN b

r,, c r e, c 1me, s r, v i s c uont reis eoo.ooo is 1st st ar or i