ML19317F933
| ML19317F933 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/18/1976 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML19317F934 | List: |
| References | |
| NUDOCS 8002210647 | |
| Download: ML19317F933 (2) | |
Text
..
snaaG3 m
gs
(
);
SMUD SACRAMENTO MUNICIPAL UTILITY OfSTRICT C 1708 59th Street. Box 15830. Sacramento. California 95813;(916) 452 3211 October 18, 1976 4
ro d
Mr. R. H. Engelken
' *^
~~
Director of Regulatory Opere* ions
'[
(h"p',3 i
NRC Operations Office, Region V h,'.,
g 8
~
1990 N. California Boulevard i
f, s
.s Walnut Creek Plaza, Suite 202 4
.C y' Q L,'
Walnut Creek, California 94596 N,
NO Re: Operating License DPR-54
~
Docket No. 50-312 41 D,q{$$
~
Reportable Occurrence 76-13
/.
Dear Mr. Engelken:
In accordance with Technical Specifications for Rancho Seco Nuclear Generating Station, Section 6.9.1, and Regulatory Guide 1.16, Revision 4, Section C.2.b.4, the Sacramento Municipal Utility District is hereby reporting
,-w)
(
the following Reportable Occurrence as RO 76-13.
Y On August 22, 1976, a refueling interval surveillance check for leakage from the Decay Heat System was attempted. As the check was started on the "B" Loop, excessive leakage (greater than the Technical Specification limit of 0.63 gallons / hour) was noted at the Decay Heat Pump. The system was immediately
,f depressurized and the surveillance test stopped. The unit was in cold shutdown',
for main generator repairs while the test was run and the "A" Loop remained'in.
service while repairs were made on the "B" pump.
The leakage problem was solved on August 29, 1976, and a quarterly surveil-lance and inservice test was run to verify that the pump was operable. During this 15 minu test (actual run time was 37 minutes) a special check was made to r
verify that ne pump was not leaking. Upon completion of the surveillance test with the observation of zero leakage from the pump, the "B" Decay Heat Loop was declared operable. The reactor was then taken critical for zero power physics tests and operator training. As further verification that leakage from the "B" Loop was within acceptable limits, the refueling interval surveillance that was failed on August 22 was re-run on September 1.
Results of this check showed a total leakage rate for the entire "B" Loop of 0.0185 gallons / hour which is well below the Technical Specification limit of 0.63 gallons / hour.
..-s j"
as i
b.%), i
~
1 e
t-
\\
,/
D-s yg,,
N. /
8002 210 k(NEO 3 % - E L E C T R I C ~ $ Y 3 T E *.t SERvTNG M0'E fMAN 600.JC3 IN THE %EART Of Cat'r0 N.4
~.
i 2-October 18, 1976 l
Mr. R. H. Engelken 1
I i
)
~ This Reportable Occurrence will be discussed with appropriate personnel, stressing the need for completion of a surveillance test prior to declaring a j )
component or system operable if failure of that surveillance test was the reason-the component or system was declared inoperable.
The pump is a single-stage, 3000 gpm centrifugal pump manufactured by
_ l Babcock and Wilcox, Canada.
j Respectfully submitted,
~,
~:
AIt -s J. J. Mattimoe
[
- i Assistant General Manager #
and Chief Engineer 4
2 e
I r
. i 6
.JJM:RWC: sal i
2, -
o
+e e
- gpy
,e
-y,
.~-.
,7
'*