ML17173A714: Difference between revisions
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Commonv.Ath *Edison Dresden NLi;l~~wer Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 March 23, 1979 BBS LTR ti 79-251 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report II 79-13/03L-0, Docket. //050-237 is hereby submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2.(b), conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation. | |||
Commonv.Ath *Edison Dresden NLi;l~~wer Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 | |||
(~ | (~ | ||
~teff.nson | ~teff.nson | ||
Line 31: | Line 28: | ||
.* (7. 77.J,____ j .'~ ' . LICENSEE EVENT REPORT | .* (7. 77.J,____ j .'~ ' . LICENSEE EVENT REPORT | ||
. CONT~OLBLOCK: | . CONT~OLBLOCK: | ||
I1* I *I | I1* I *I | ||
* I 1Q !PLEASE PRINT OR n . L L REQUIRED INFORMATION! . | * I 1Q !PLEASE PRINT OR n . L L REQUIRED INFORMATION! . | ||
Line 39: | Line 35: | ||
[I[i]. :~~~~~ L:J©I 0 I 5 Io Io Io 12 13 17 !GI o 12 12 13 17 19 @I o I 3 I 2 I 3 I 1 I 9 IG) 7 8 60 61 DOCKET Ni.JMSER 68 69 EVENT DATE 74 75 REPORT DATE SO EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES {1o) | [I[i]. :~~~~~ L:J©I 0 I 5 Io Io Io 12 13 17 !GI o 12 12 13 17 19 @I o I 3 I 2 I 3 I 1 I 9 IG) 7 8 60 61 DOCKET Ni.JMSER 68 69 EVENT DATE 74 75 REPORT DATE SO EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES {1o) | ||
* I While UJ was shutdown and U2 at steady' power, 2/3 D/G was manually started prior to | * I While UJ was shutdown and U2 at steady' power, 2/3 D/G was manually started prior to | ||
((II] I takin8*32 transformer out of service .. 15 min. later CLG. water pump breaker thermally | |||
. | . ((ill I tripped and auto .. transferred to *redundant power supply. Tr:lp reset manually and re- | ||
[QI[] I turned to original power supply. After 20min. tripped again.* The redundant power | [QI[] I turned to original power supply. After 20min. tripped again.* The redundant power | ||
[]JD I supply was also.. found tripped. Trips reset and ran successfully. Since redundant 02]. ID/G's were available, *safety significance of this incident is minimal. Last trip occurred on 6/30/78 (LERU18-41/Q3L-O) | []JD I supply was also.. found tripped. Trips reset and ran successfully. Since redundant 02]. ID/G's were available, *safety significance of this incident is minimal. Last trip occurred on 6/30/78 (LERU18-41/Q3L-O) | ||
((ill 7 8 9 60 SYSTEM. CAUSE CAUSE COMP. VALVE CODE CODE SUBCOOE . COMPONENT CODE SUBCODE SU BC ODE | |||
[Iill' I El El@ w@ UJ@ Ip I ul MI p Ix Ix I@ L!J@ UJ@ | [Iill' I El El@ w@ UJ@ Ip I ul MI p Ix Ix I@ L!J@ UJ@ | ||
1 a 9 10 11 12 13 . 16 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION | 1 a 9 10 11 12 13 . 16 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION | ||
~ LE A/RO CVENT YEAR REPORT NO. CODE TYPE NO. | ~ LE A/RO CVENT YEAR REPORT NO. CODE TYPE NO. | ||
\!.:J REPORT N.UMBER I I I 7 9 | \!.:J REPORT N.UMBER I I I 7 9 I I I 01 i1. JI. I/I Io I J I ~ l=.l ~ | ||
I I I 01 i1. JI. I/I Io I J I ~ l=.l ~ | |||
21 22 2J 24 26 . 27 28 29 JO 31 J2 ACTION FUTURE EFFECT SHUTDOWN. * (.;'.:;\ ATTACHMENT NPRD-4 PRIME COMP. | 21 22 2J 24 26 . 27 28 29 JO 31 J2 ACTION FUTURE EFFECT SHUTDOWN. * (.;'.:;\ ATTACHMENT NPRD-4 PRIME COMP. | ||
* COMPONENT | * COMPONENT | ||
Line 63: | Line 57: | ||
47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ . | 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ . | ||
QliJ I Cause unknown. Load check and motor bridge and meggar were performed.* No fault .found.I OJJJ I Pump temperature, discharge pressure, and vibration were normal while running. Pump | QliJ I Cause unknown. Load check and motor bridge and meggar were performed.* No fault .found.I OJJJ I Pump temperature, discharge pressure, and vibration were normal while running. Pump | ||
[ | [)))) I has been run 3 times since with no failure. Additional checks will be performed during! | ||
. fIII] I the upcoming biannual insp. I r.tm8 1 9 80 FACILITY . 13Q\ METHOD OF STATUS % POWER OTHER STATUS \.:::;:J DISCOVERY DISCOVERY DESCRIPTION @ | . fIII] I the upcoming biannual insp. I r.tm8 1 9 80 FACILITY . 13Q\ METHOD OF STATUS % POWER OTHER STATUS \.:::;:J DISCOVERY DISCOVERY DESCRIPTION @ | ||
ITTIJ 1 8 lli.J@ I g Bl ol@._I_U_J_s_h_ut_d_own_*_ | ITTIJ 1 8 lli.J@ I g Bl ol@._I_U_J_s_h_ut_d_own_*_ | ||
9 10 12 11 | 9 10 12 11 44 | ||
44 | |||
*Ul@I Operational Event 45 46 80 ACTIVITY CONTENT . ~ | *Ul@I Operational Event 45 46 80 ACTIVITY CONTENT . ~ | ||
RELEASED OF.RELEASE AMOUNT OF ACTIVITY~ LOCATION OF RELEASE @ | RELEASED OF.RELEASE AMOUNT OF ACTIVITY~ LOCATION OF RELEASE @ |
Latest revision as of 17:29, 18 March 2020
ML17173A714 | |
Person / Time | |
---|---|
Site: | Dresden ![]() |
Issue date: | 03/23/1979 |
From: | Stephenson B COMMONWEALTH EDISON CO. |
To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
Shared Package | |
ML17173A715 | List: |
References | |
79-251, NUDOCS 7903270448 | |
Download: ML17173A714 (2) | |
Text
- ,_
-.a.-~~--
Commonv.Ath *Edison Dresden NLi;l~~wer Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 March 23, 1979 BBS LTR ti 79-251 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report II 79-13/03L-0, Docket. //050-237 is hereby submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2.(b), conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
(~
~teff.nson
,,.** ,"* ~- ...* ~,
/ .* . . . / :..c.../"._,r.t/
Station Superintendent Dresden Nuclear Power Station BBS:lcg Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC 7 9 0 3 2 7 0 4L/f
.* (7. 77.J,____ j .'~ ' . LICENSEE EVENT REPORT
. CONT~OLBLOCK:
I1* I *I
- I 1Q !PLEASE PRINT OR n . L L REQUIRED INFORMATION! .
6
[212] Ir IL In IR Is I 2 !(~)lo Io 1- Io lo Io Io Io 1- lo lo 10)1 411 I l I i I i 101 I 10 1 8 9 \..ICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 C' ... )
--:CON.'.:f.----;- ;
[I[i]. :~~~~~ L:J©I 0 I 5 Io Io Io 12 13 17 !GI o 12 12 13 17 19 @I o I 3 I 2 I 3 I 1 I 9 IG) 7 8 60 61 DOCKET Ni.JMSER 68 69 EVENT DATE 74 75 REPORT DATE SO EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES {1o)
- I While UJ was shutdown and U2 at steady' power, 2/3 D/G was manually started prior to
((II] I takin8*32 transformer out of service .. 15 min. later CLG. water pump breaker thermally
. ((ill I tripped and auto .. transferred to *redundant power supply. Tr:lp reset manually and re-
[QI[] I turned to original power supply. After 20min. tripped again.* The redundant power
[]JD I supply was also.. found tripped. Trips reset and ran successfully. Since redundant 02]. ID/G's were available, *safety significance of this incident is minimal. Last trip occurred on 6/30/78 (LERU18-41/Q3L-O)
((ill 7 8 9 60 SYSTEM. CAUSE CAUSE COMP. VALVE CODE CODE SUBCOOE . COMPONENT CODE SUBCODE SU BC ODE
[Iill' I El El@ w@ UJ@ Ip I ul MI p Ix Ix I@ L!J@ UJ@
1 a 9 10 11 12 13 . 16 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION
~ LE A/RO CVENT YEAR REPORT NO. CODE TYPE NO.
\!.:J REPORT N.UMBER I I I 7 9 I I I 01 i1. JI. I/I Io I J I ~ l=.l ~
21 22 2J 24 26 . 27 28 29 JO 31 J2 ACTION FUTURE EFFECT SHUTDOWN. * (.;'.:;\ ATTACHMENT NPRD-4 PRIME COMP.
- COMPONENT
- TAKEN ACTION. ON PLANT .METHOD HOURS ~ SUBMITTED FORM ::;us. SUPPLIER* MANUFACTURER W@W@
JJ 34 W
JS LU JS I 01 37 01 01 °1 L.::..1@
- 40 41
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42
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43 I
. 44 c 1 6 18 13 I@
47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ .
QliJ I Cause unknown. Load check and motor bridge and meggar were performed.* No fault .found.I OJJJ I Pump temperature, discharge pressure, and vibration were normal while running. Pump
[)))) I has been run 3 times since with no failure. Additional checks will be performed during!
. fIII] I the upcoming biannual insp. I r.tm8 1 9 80 FACILITY . 13Q\ METHOD OF STATUS % POWER OTHER STATUS \.:::;:J DISCOVERY DISCOVERY DESCRIPTION @
ITTIJ 1 8 lli.J@ I g Bl ol@._I_U_J_s_h_ut_d_own_*_
9 10 12 11 44
- Ul@I Operational Event 45 46 80 ACTIVITY CONTENT . ~
RELEASED OF.RELEASE AMOUNT OF ACTIVITY~ LOCATION OF RELEASE @
~
1 8
.l.Ll@ W@ I..._N;;.;.;;A.;___ _ _ _ ___.
9 . 10 11 44 r
45 NA 80 PERSONNEL EXPOSURES r.;;:;"\
NUMBER A TYPE DESCRIPTION
. III2J 1 8 lo 9
I al ol0LLl@11 12
.NA
- 1~3~~~~~~~~~~~---~~~~,....-~~~~~~~~~~~~~~~~~~~80 PERSONNEL INJURIES Q
. NUMBER DESCRIPTION~
~lo lo lo l@)~~N~A;_.._.~*~~~~~~~~~~~~~~~~~~~~~~~~--1 1 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY t4j\
TYPE DESCRIPTION '.::.::)
ITliJa 1
Lz_j@ . NA 9 1~o~---~~~~~---~~~~~~~-~-~~~-~~~~--~~-~~~~~~~~-8~0 PUBLICITY Q ISSUEOf,;'";;\ DESCRIPTION~ 7 9032 NRC USE ONL y o lITIJa llLJ61 NA ,
7 O 4 5 .3 .I I I I I I I I I I I I I I:
1 91 ~o~~-~~--~~~~~~~~~~~~--~~~~~-~~--'68 69 80*;
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