ML18219C143: Difference between revisions
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{{#Wiki_filter:I e AEC DIST'TIG" FOR PART 50 DQCI'ET ME AXIAL (TEi'PORARY FORi'il)CONTROL NO: FILE: | {{#Wiki_filter:I e AEC DIST'TIG" FOR PART 50 DQCI'ET ME AXIAL (TEi'PORARY FORi'il) | ||
Ltr furnishing suppl to A'bnorma Occurrence AO-50-315/74-09 involving the brea'being closed w1.thout having intermediate range channels in service on 12-18-74.... | CONTROL NO: 210 FILE: | ||
F RO;l Indiana It: Michigan Power oDATE OF DOC DATE REC'D TV,'X RPT OTHER Bridgman, Mich. 49106 R.W. Jur enson 12 4 TO: ORIG CC OTHER SENT AEC PDR Mr. J. G. Keppler 1 signed SENT LOCAL PDR CLASS UNCLA PROPIixIFO INPUT NO CYS REC'D DOC,iET NO: | |||
XX 1 50-315 DESCRIPTION: Ltr furnishing suppl to A'bnorma ENCLOSURES: | |||
Occurrence AO-50-315/74-09 involving the brea rs | |||
'being closed w1.thout having intermediate range channels in service on 12-18-74.... | |||
[ | |||
~WUO qn~N q C' t 1 [ | |||
The following is a supplement to Abnormal Occurrence Number AO-050-315/74-09v Prior to commencing the Rod Drop Time Preoperational Test on December 18, 1974, the Intermediate Range Nuclear Instrumentation was placed in service as required by Technical Specifications Table 3.3-1 Number 5.AA review of previous testing which involved closing reactor trip breakers showed that on December 9, 1974, during Protection System Time Response Testing, the breakers were closed without having Intermediate Range Channels in service.CORRECTIVE ACTIONS TAKEN (1)The Intermediate Range Channels were placed in service on 2345 December 18, 1974.(2)It was determined that the health and safety of the public was not jeopardized since the CRDM Motor Generators were not energized while the Reactor Trip Breakers were closed, thus movement of the Control Rods was impossible. | t<iNLJuwl u~i PLANT NAME: Cook 1 BUTLER (S) | ||
CORRECTIVE STEPS TAKEN TO AVOID RE-OCCURRENCE (1)A change to Surveillance Test Procedure THP 4030 STP.100 was issued which requires Intermediate RangeeChannels to be in operation prior to commencing this test.JAM | FOR ACTIONX'Ii"FOR XIATIO'" DE/ 1~~ | ||
Respectfully, baf cc: J.E.Dol an R.S.Hunter R.M.Kopper G.E.LeMasters G.E.Lien PNSRC R.J.Vollen BPI K.R.-Baker, Resident Inspector | SCHIIENCER (S) ZIE>fANN (S) REGAN (E) | ||
~FO, L L 0 5 0 | W/ Copies W/ Copies W/ Copies W/ Copies CLARK (S) STOLZ (S) DXCKER (E). LEAR (S) | ||
W/ Copies W/ Copies W/ Copies Iif/ Copies PARR (S) VQSALLO (S) KNXGHTON (E) sPEIs (s) | |||
W/ Copies W/ Copies W/ Copies W/ Copies 46llgL (S) PURPLE {S) YOUNGBLOOD (E) | |||
W/+Copies W/ Copies Co ies i1EQ AEC EX'ECH DR 'I REVIEW INTc>x AL DISt DENXON GRIMES I I =.)U 7 I 0 ixI LXC. ASST. | |||
9XGGS (S) | |||
~AT XN BRAITMAN AGC 2 ROOM P-506-A +AIACCARRY GAMMILL GEARIN (S) SALTZMAN AJNZZXNG/STAFF ~XGHT ~TNER ..' GOULBOURNE (S) B. HURT CREASE L@AWLICKI BALLARD KREUTZER (E) | |||
GXAEIBUSSO C8HAO SPANGLER LEE (S) PLANS BOYD CTELLO >UIXGRET (S) MCDONALD MOORE (S) (BWR) KIOUSTON ENUXRO ED (E) CHAPMAN DEXOUNG (S) (PWR) AOVAK MULLER ERVXCE (S) DUBE w/input SKOVHOLT (S) 40SS DXCKER SEEEPPARD (S) E. COUPE GOLLER (S) APPOLITO KNXGEETON SMTER (E) ~D. THOMPSON (Q) | |||
PE COLLINS TEDESCO YOUNGBLOOD SMITH (S) ~KLECmR DENISE ~NG REGAN TEETS (S) 6fF. WXTLIAI(fS REG OPR @t AINAS PROJECT LDR WILLIAMS (E) | |||
XLE & REGXON Q} 4ENAROYA WILSON (S) | |||
N= | |||
.R. WILSON IAx STEELE ~VOLDIER HARLESS INGRAM (S) | |||
E):TERN.RL DIS R IBUTIQi~! | |||
(1) (2) (10) -NATIONAL LABS 1"PDR SAN/LA/NY 4.-TXC(ABERNATHY) 1-N. PENNINGTON, RM E-201 G.T. 1 BROOKEiAVEN NAT LAB 51"NSXC(BUCHANAN) 1-CONSULTAEG S 1-G, ULRIKSON, ORNL. | |||
1"ASLB NEWI IARK/BLUE/AGBABIAN 1-AGMED(RUTH GUSSMAN) 1 NEWE.'ON ANDERSON RM B-127 G.T. | |||
Q5"ACRS SENT TO LXC ~ 1-J ~ RUNKLES, RM E-201 Service 1-9-75 ASST'. | |||
G.T. | |||
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=-I,'er4oon PI INDIANA D NIIDNIIDANPDINER DDNIPANYi 5o-3)5 DONALD C COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 | |||
>ig g | |||
- '+ill | |||
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December 30,-1974 U.S. Atomic Energy Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Attention: Mr. J. G. Keppler; Regional Director Gentlemen: | |||
The following is a supplement to Abnormal Occurrence Number AO-050-315/74-09v Prior to commencing the Rod Drop Time Preoperational Test on December 18, 1974, the Intermediate Range Nuclear Instrumentation was placed in service as required by Technical Specifications Table 3.3-1 Number 5. | |||
AA review of previous testing which involved closing reactor trip breakers showed that on December 9, 1974, during Protection System Time Response Testing, the breakers were closed without having Intermediate Range Channels in service. | |||
CORRECTIVE ACTIONS TAKEN (1) The Intermediate Range Channels were placed in service on 2345 December 18, 1974. | |||
(2) It was determined that the health and safety of the public was not jeopardized since the CRDM Motor Generators were not energized while the Reactor Trip Breakers were closed, thus movement of the Control Rods was impossible. | |||
CORRECTIVE STEPS TAKEN TO AVOID RE-OCCURRENCE (1) A change to Surveillance Test Procedure THP 4030 STP.100 was issued which requires Intermediate RangeeChannels to be in operation prior to commencing this test. | |||
JAM 2 l975 | |||
0 | |||
~ ~ K l | |||
U.S. Ato Energy Commission December 30, 1974 Page 2 DATE FULL COMPLIANCE WILL BE ACHIEVED (1) Full compliance has now been achieved (effective 12-18-74). | |||
Respectfully, | |||
.W. Jurg en Plant Man ger baf cc: J.E. Dol an R.S. Hunter R.M. Kopper G.E. LeMasters G.E. Lien PNSRC R.J. Vollen BPI K.R. -Baker, Resident Inspector | |||
I XII LlCENSEE EVENT REPORT six CONTROL OLOCK: (P SE PRINT ALL REQUIRED INFORMlLTION) 1 l R=3O-7g iiii LICENSEE LCENSE EVENT 7 89 yogCg NAME 14 15 LICENSE NUMBER OO OoOOO oo 25 A | |||
26 TYPE 30 31 TYPE | |||
~pi32 REPORT . REPORT | |||
[OD1]t'ONT 7 8 | |||
~FO, 57 58 L | |||
59 L | |||
60 0 5 0 o 3 2 5 61 68 69 L 2. 0 'I 7 4 74 L | |||
75 L 3 > 'I 4-80 I | |||
EVENT DESCRIPTION gag >Uar~C. PEPmPt-M,ACe F ROTC.C.C 4 5YS-EH YIME. QP~VOVSE. | |||
7 8 9 80 7 89 5Ahl e, c o Ip K,E.RS uveRe c.~sar 80 7 | |||
toO] | |||
8 9 T i eozaTe. m~ e AuC.m>P. r.uemuHex Wrgk v4A.S gO> | |||
80 7 8 9 Vlc. F u T.R f b. SPEC'TF'X oAS. | |||
80 QOg 7 89 PNME 80 SYSTEM CAUSE COMPONENT COMPONENT | |||
~D~ ~r. | |||
7 8 9 10 COOS a | |||
COOS | |||
~D 11 12 Zz. zzz COMPONENT COOE 17 . | |||
SUPPUER Z | |||
43 44 zzz,z MANUFACIURER 47 VIOLATION Y | |||
48 CAUSE DESCRIPTION | |||
[OOS] | |||
7 8 9 | |||
~ME FSPOAM SURVEXLLP 4<8 TMY'XD ROT PEgVTRE, ~F Qg8 7 9 M~ Na9IPTe RAQC e zds7e HeJT T ee; ~M VXC,e 80 Q~g t'RE.P E. VX.SX7- SF E. Sv PP LE.HEhhTkL. | |||
7 89 FACILITY METHOO OF | |||
* OISCOVERY OISCOVERY OESCRIPTION Qg c ~oo o vz m SY pe.c. Cepze~NR~VE 7 8 9 10 12 13 44 45 e 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE | |||
[gg z. ~z 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 89 11 12 13 80 PERSONNEL INJURIES 7 | |||
~<<L0Dg~ | |||
89 11 12 67. | |||
80 PROBABLE CONSEQUENCES Q~g )U TeST- %HAT ~ SAFGY QoT )EDPARQLZ&D 7 89 80 LOSS OR DAMAGE TO FACILITY 7 | |||
Q~g 89 g 10 Nh, 80 PUBLICITY 7 89 80 ADDITIONAL FACTORS 7 8 9 80 7 89 NAME: .... I 5-59OL GPO 88 I ~ | |||
80 8 8T | |||
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Revision as of 19:54, 20 October 2019
ML18219C143 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
Issue date: | 12/30/1974 |
From: | Jurgensen R Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co) |
To: | James Keppler US Atomic Energy Commission (AEC) |
References | |
LER 1974-009Y-00 | |
Download: ML18219C143 (7) | |
Text
I e AEC DIST'TIG" FOR PART 50 DQCI'ET ME AXIAL (TEi'PORARY FORi'il)
CONTROL NO: 210 FILE:
F RO;l Indiana It: Michigan Power oDATE OF DOC DATE REC'D TV,'X RPT OTHER Bridgman, Mich. 49106 R.W. Jur enson 12 4 TO: ORIG CC OTHER SENT AEC PDR Mr. J. G. Keppler 1 signed SENT LOCAL PDR CLASS UNCLA PROPIixIFO INPUT NO CYS REC'D DOC,iET NO:
XX 1 50-315 DESCRIPTION: Ltr furnishing suppl to A'bnorma ENCLOSURES:
Occurrence AO-50-315/74-09 involving the brea rs
'being closed w1.thout having intermediate range channels in service on 12-18-74....
[
~WUO qn~N q C' t 1 [
t<iNLJuwl u~i PLANT NAME: Cook 1 BUTLER (S)
FOR ACTIONX'Ii"FOR XIATIO'" DE/ 1~~
SCHIIENCER (S) ZIE>fANN (S) REGAN (E)
W/ Copies W/ Copies W/ Copies W/ Copies CLARK (S) STOLZ (S) DXCKER (E). LEAR (S)
W/ Copies W/ Copies W/ Copies Iif/ Copies PARR (S) VQSALLO (S) KNXGHTON (E) sPEIs (s)
W/ Copies W/ Copies W/ Copies W/ Copies 46llgL (S) PURPLE {S) YOUNGBLOOD (E)
W/+Copies W/ Copies Co ies i1EQ AEC EX'ECH DR 'I REVIEW INTc>x AL DISt DENXON GRIMES I I =.)U 7 I 0 ixI LXC. ASST.
9XGGS (S)
~AT XN BRAITMAN AGC 2 ROOM P-506-A +AIACCARRY GAMMILL GEARIN (S) SALTZMAN AJNZZXNG/STAFF ~XGHT ~TNER ..' GOULBOURNE (S) B. HURT CREASE L@AWLICKI BALLARD KREUTZER (E)
GXAEIBUSSO C8HAO SPANGLER LEE (S) PLANS BOYD CTELLO >UIXGRET (S) MCDONALD MOORE (S) (BWR) KIOUSTON ENUXRO ED (E) CHAPMAN DEXOUNG (S) (PWR) AOVAK MULLER ERVXCE (S) DUBE w/input SKOVHOLT (S) 40SS DXCKER SEEEPPARD (S) E. COUPE GOLLER (S) APPOLITO KNXGEETON SMTER (E) ~D. THOMPSON (Q)
PE COLLINS TEDESCO YOUNGBLOOD SMITH (S) ~KLECmR DENISE ~NG REGAN TEETS (S) 6fF. WXTLIAI(fS REG OPR @t AINAS PROJECT LDR WILLIAMS (E)
XLE & REGXON Q} 4ENAROYA WILSON (S)
N=
.R. WILSON IAx STEELE ~VOLDIER HARLESS INGRAM (S)
E):TERN.RL DIS R IBUTIQi~!
(1) (2) (10) -NATIONAL LABS 1"PDR SAN/LA/NY 4.-TXC(ABERNATHY) 1-N. PENNINGTON, RM E-201 G.T. 1 BROOKEiAVEN NAT LAB 51"NSXC(BUCHANAN) 1-CONSULTAEG S 1-G, ULRIKSON, ORNL.
1"ASLB NEWI IARK/BLUE/AGBABIAN 1-AGMED(RUTH GUSSMAN) 1 NEWE.'ON ANDERSON RM B-127 G.T.
Q5"ACRS SENT TO LXC ~ 1-J ~ RUNKLES, RM E-201 Service 1-9-75 ASST'.
G.T.
N W ~ f I
'
I
~ ~
n,~
il
i t
=-<<I'
=-I,'er4oon PI INDIANA D NIIDNIIDANPDINER DDNIPANYi 5o-3)5 DONALD C COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106
>ig g
- '+ill
)
December 30,-1974 U.S. Atomic Energy Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Attention: Mr. J. G. Keppler; Regional Director Gentlemen:
The following is a supplement to Abnormal Occurrence Number AO-050-315/74-09v Prior to commencing the Rod Drop Time Preoperational Test on December 18, 1974, the Intermediate Range Nuclear Instrumentation was placed in service as required by Technical Specifications Table 3.3-1 Number 5.
AA review of previous testing which involved closing reactor trip breakers showed that on December 9, 1974, during Protection System Time Response Testing, the breakers were closed without having Intermediate Range Channels in service.
CORRECTIVE ACTIONS TAKEN (1) The Intermediate Range Channels were placed in service on 2345 December 18, 1974.
(2) It was determined that the health and safety of the public was not jeopardized since the CRDM Motor Generators were not energized while the Reactor Trip Breakers were closed, thus movement of the Control Rods was impossible.
CORRECTIVE STEPS TAKEN TO AVOID RE-OCCURRENCE (1) A change to Surveillance Test Procedure THP 4030 STP.100 was issued which requires Intermediate RangeeChannels to be in operation prior to commencing this test.
JAM 2 l975
0
~ ~ K l
U.S. Ato Energy Commission December 30, 1974 Page 2 DATE FULL COMPLIANCE WILL BE ACHIEVED (1) Full compliance has now been achieved (effective 12-18-74).
Respectfully,
.W. Jurg en Plant Man ger baf cc: J.E. Dol an R.S. Hunter R.M. Kopper G.E. LeMasters G.E. Lien PNSRC R.J. Vollen BPI K.R. -Baker, Resident Inspector
I XII LlCENSEE EVENT REPORT six CONTROL OLOCK: (P SE PRINT ALL REQUIRED INFORMlLTION) 1 l R=3O-7g iiii LICENSEE LCENSE EVENT 7 89 yogCg NAME 14 15 LICENSE NUMBER OO OoOOO oo 25 A
26 TYPE 30 31 TYPE
~pi32 REPORT . REPORT
[OD1]t'ONT 7 8
~FO, 57 58 L
59 L
60 0 5 0 o 3 2 5 61 68 69 L 2. 0 'I 7 4 74 L
75 L 3 > 'I 4-80 I
EVENT DESCRIPTION gag >Uar~C. PEPmPt-M,ACe F ROTC.C.C 4 5YS-EH YIME. QP~VOVSE.
7 8 9 80 7 89 5Ahl e, c o Ip K,E.RS uveRe c.~sar 80 7
toO]
8 9 T i eozaTe. m~ e AuC.m>P. r.uemuHex Wrgk v4A.S gO>
80 7 8 9 Vlc. F u T.R f b. SPEC'TF'X oAS.
80 QOg 7 89 PNME 80 SYSTEM CAUSE COMPONENT COMPONENT
~D~ ~r.
7 8 9 10 COOS a
COOS
~D 11 12 Zz. zzz COMPONENT COOE 17 .
SUPPUER Z
43 44 zzz,z MANUFACIURER 47 VIOLATION Y
48 CAUSE DESCRIPTION
[OOS]
7 8 9
~ME FSPOAM SURVEXLLP 4<8 TMY'XD ROT PEgVTRE, ~F Qg8 7 9 M~ Na9IPTe RAQC e zds7e HeJT T ee; ~M VXC,e 80 Q~g t'RE.P E. VX.SX7- SF E. Sv PP LE.HEhhTkL.
7 89 FACILITY METHOO OF
- OISCOVERY OISCOVERY OESCRIPTION Qg c ~oo o vz m SY pe.c. Cepze~NR~VE 7 8 9 10 12 13 44 45 e 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE
[gg z. ~z 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 89 11 12 13 80 PERSONNEL INJURIES 7
~<<L0Dg~
89 11 12 67.
80 PROBABLE CONSEQUENCES Q~g )U TeST- %HAT ~ SAFGY QoT )EDPARQLZ&D 7 89 80 LOSS OR DAMAGE TO FACILITY 7
Q~g 89 g 10 Nh, 80 PUBLICITY 7 89 80 ADDITIONAL FACTORS 7 8 9 80 7 89 NAME: .... I 5-59OL GPO 88 I ~
80 8 8T
I 4l h 4 I f
T
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