ML19350E522: Difference between revisions
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y | y DOCKET NO. 50-346 -} | ||
DOCKET NO. 50-346 -} | |||
UNIT SHUTDOWNS AND POWNt REDUCTIONS Davie-Be'~s' Unit 1 ' | UNIT SHUTDOWNS AND POWNt REDUCTIONS Davie-Be'~s' Unit 1 ' | ||
o UNIT NAME h, is ioni O DATE , | o UNIT NAME h, is ioni O DATE , | ||
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TELEPIIONE . ' | TELEPIIONE . ' | ||
'251- | '251- | ||
~ | ~ | ||
$ c | $ c | ||
| Line 40: | Line 37: | ||
"* C:use & Corrective + | "* C:use & Corrective + | ||
No. | No. | ||
Date g 3g ij j2gy Event 3? | |||
Date | |||
g 3g ij j2gy Event 3? | |||
N0 | N0 | ||
$" Action to | $" Action to | ||
| Line 49: | Line 43: | ||
~ | ~ | ||
$ j5g Repori* y Prevent Recurrence 6 | $ j5g Repori* y Prevent Recurrence 6 | ||
8 81 05 02 S 0 A NA NA NA NA Reactor power was reduced to approxi-mately 10% to repair FT RCIA1 (reactor coolant flow transmitter). | |||
8 81 05 02 S 0 A NA NA NA NA Reactor power was reduced to approxi-mately 10% to repair FT RCIA1 (reactor | |||
9 81 05 09 S 0 A NA NA NA NA Reactor power was reduced to approxi-mately 95% due to seal problems on Reactor Coolant Pump 2-1. * | 9 81 05 09 S 0 A NA NA NA NA Reactor power was reduced to approxi-mately 95% due to seal problems on Reactor Coolant Pump 2-1. * | ||
( | ( | ||
10 81 05 12 S 0 A NA NA NA NA Reactor power was reduced to 75% to take Reactor Coolant Pump 2-1 off. | 10 81 05 12 S 0 A NA NA NA NA Reactor power was reduced to 75% to take Reactor Coolant Pump 2-1 off. | ||
1 11 81 05 12 F 23.8 B NA NP-33-81-32 CB PUMPXX Th,e reactor tripped due to Reactor Coolant Pump 2-2 trip whleh was caused ~ | 1 11 81 05 12 F 23.8 B NA NP-33-81-32 CB PUMPXX Th,e reactor tripped due to Reactor Coolant Pump 2-2 trip whleh was caused ~ | ||
by a protective relay being replaced | by a protective relay being replaced on Reactor Coolant Pump 2-2 breaker (see Operational Summary for.further deta.ils). | ||
I 2 3 - | |||
on Reactor Coolant Pump 2-2 breaker (see Operational Summary for.further | |||
deta.ils) | |||
I | |||
2 3 - | |||
4 F: Forced Reason: Method: Exhibit G. Instructions A Etiuipment Failure (Explain) 1-Manual for Preparation of Data S: Schedu!cd B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C.Rcfueling 3 Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 40thm(Explaki4 0161) li-Operator Training & License Examination 4-Continuation F Administ ative 5-Reduction 5 ' | 4 F: Forced Reason: Method: Exhibit G. Instructions A Etiuipment Failure (Explain) 1-Manual for Preparation of Data S: Schedu!cd B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C.Rcfueling 3 Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 40thm(Explaki4 0161) li-Operator Training & License Examination 4-Continuation F Administ ative 5-Reduction 5 ' | ||
G-Operational Le ror (lixplain) Exhibit ! Same Source 6-Other (9/77) Il-Os her ( Explain) | G-Operational Le ror (lixplain) Exhibit ! Same Source 6-Other (9/77) Il-Os her ( Explain) | ||
' ' - - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ * ~ ~ * | ' ' - - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ * ~ ~ * | ||
'__ 1_____ | '__ 1_____ | ||
C 1_ _ _ _ _ _: n _ _ _ _ | C 1_ _ _ _ _ _: n _ _ _ _ | ||
~ | ~ | ||
__1}} | __1}} | ||
Latest revision as of 00:28, 31 January 2020
| ML19350E522 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/15/1981 |
| From: | Sarsour B TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19350E519 | List: |
| References | |
| NUDOCS 8106230224 | |
| Download: ML19350E522 (1) | |
Text
'
Rovimien 1 - 6/15/81 s
[ . ,
y .
v -
y DOCKET NO. 50-346 -}
UNIT SHUTDOWNS AND POWNt REDUCTIONS Davie-Be'~s' Unit 1 '
o UNIT NAME h, is ioni O DATE ,
COMPLETED BY Bilal shrkour .
REPORT MON 111 May, 1981 m 9) ?s9-sn00, Ext.
TELEPIIONE . '
'251-
~
$ c
.2 e ee E
% .a -.
ES LIC'"5 ".
E*
"* C:use & Corrective +
No.
Date g 3g ij j2gy Event 3?
N0
$" Action to
- [3
~
$ j5g Repori* y Prevent Recurrence 6
8 81 05 02 S 0 A NA NA NA NA Reactor power was reduced to approxi-mately 10% to repair FT RCIA1 (reactor coolant flow transmitter).
9 81 05 09 S 0 A NA NA NA NA Reactor power was reduced to approxi-mately 95% due to seal problems on Reactor Coolant Pump 2-1. *
(
10 81 05 12 S 0 A NA NA NA NA Reactor power was reduced to 75% to take Reactor Coolant Pump 2-1 off.
1 11 81 05 12 F 23.8 B NA NP-33-81-32 CB PUMPXX Th,e reactor tripped due to Reactor Coolant Pump 2-2 trip whleh was caused ~
by a protective relay being replaced on Reactor Coolant Pump 2-2 breaker (see Operational Summary for.further deta.ils).
I 2 3 -
4 F: Forced Reason: Method: Exhibit G. Instructions A Etiuipment Failure (Explain) 1-Manual for Preparation of Data S: Schedu!cd B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C.Rcfueling 3 Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 40thm(Explaki4 0161) li-Operator Training & License Examination 4-Continuation F Administ ative 5-Reduction 5 '
G-Operational Le ror (lixplain) Exhibit ! Same Source 6-Other (9/77) Il-Os her ( Explain)
' ' - - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ * ~ ~ *
'__ 1_____
C 1_ _ _ _ _ _: n _ _ _ _
~
__1