ML18347B178: Difference between revisions
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........ | consumers Power | ||
* Area Code 517 788-0550 April 28, 1978 | -* ,~;r . . . _. . ~'7'".i~.::~--4r**./* | ||
; | -.-"J company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 | ||
* Area Code 517 788-0550 April 28, 1978 _:,,, ..,.,, | |||
<o oo :"'11(}) (/'I_.; c;.-o 7!.@ ::ic: --! c;. :Ji:!. The reverse side describes a reportable occurrence under Technical cation 6.9.2.A.2 for the Palisades Plant. This event was identified by TWX on April 17, 1978. David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement | :" ~* | ||
* PALISADES | ~ *(".: | ||
* 25 26 LICENSE TYPE JO 57 CAT 58 CON'T !TI:!] | CJ 0) | ||
~ '"' | |||
... This is contrary to the requirements of TS 3.10.5.b and the CQIIJ jLow Power Physics Test procedures. | ;:;; | ||
The out-ofmsequence maneuver occurred [£ITJ Jduring sequential rod worth measurements when a faulty position indication C2:I§] 1for CRDM '#.25 (group 1) indicated it was fully withdrawn. | -\ :'4'!!: | ||
When the condi-t m2J 1 tion was detected, a different target rod was selected and the test con-[]]]] | ~ | ||
w@ | .., .. | ||
L::j 10111 L!J L=J | (.;)~, ..: | ||
EIJ]J 1Precautionary statements have been added to the reactor control system IJ:II] Joperating procedure and the yellow engraved tag installed on the control IJJ3] 1room console adjacent to the rod selector switches. 7 B 9 FACILITY IJQ\ STATUS % POWER OTHER STATUS \.:::;J [ill] lliJ@ Io Io I o l@I N/A | :~ | ||
[2IZJ I o I o I o lLJ@ | ~ | ||
"" | |||
i:;o~C:: | |||
;;o_UI | |||
'.:::::J [Q2:) | ~o~ | ||
';f;~~j | |||
' -- | |||
~ | |||
_. | ~rr. | ||
<o oo | |||
:"'11(}) | |||
(/'I_.; | |||
c;.-o s:;!mo ~.: | |||
7!.@ | |||
-f<"I ::ic: | |||
";O --! | |||
-< r>.'.) c;. | |||
C) :Ji:!. | |||
Mr James G Keppler r:n ~ | |||
Office of Inspection and Enforcement <!> '-9 Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LER OUT-OF-SEQUENCE ROD WITHDRAWAL The reverse side describes a reportable occurrence under Technical Specifi-cation 6.9.2.A.2 for the Palisades Plant. This event was identified by TWX on April 17, 1978. | |||
David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement | |||
NRC FORM366 | |||
* PALISADES U.S. NUCLEAR REGULATORY COMMISSION (7-77) | |||
LICENSEE EVENT REPORT CONTROL BLOCK: I 1 | |||
10 6 | |||
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) | |||
~8 IM I I I p I A I LI 1 101 010 I 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 101 411 11 I ll l 101 I 10 7 9 LICENSEE CODE 14 ~5 LICENSE NUMBER | |||
* 25 26 LICENSE TYPE JO 57 CAT 58 CON'T | |||
!TI:!] :~~~~~ ~I o I 5 I o I o I o I 21 5 I 5 IG)I o I 4 11 I 5 I 71 8 I© I o I 4 I 2 I 8 I 7 I 8 10 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ | |||
IDuring Low Power Physics Tests, regulating group 2 rods were withdrawn out-I | |||
!]JI] jof-sequence ... This is contrary to the requirements of TS 3.10.5.b and the CQIIJ jLow Power Physics Test procedures. The out-ofmsequence maneuver occurred | |||
[£ITJ Jduring sequential rod worth measurements when a faulty position indication C2:I§] 1for CRDM '#.25 (group 1) indicated it was fully withdrawn. When the condi-t m2J 1 tion was detected, a different target rod was selected and the test con- | |||
[]]]] tinued. Continuous boration was in progress. | |||
1 I 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE | |||
[ill] | |||
7 8 IRIB I@ | |||
9 10 w@ w@ 1c1R1n1R1v1E1@ w@ | |||
11 12 13 18 19 w@ | |||
20 SEQUENTIAL OCCURRENCE REPORT REVISION r.:;.., LE RIRO CV ENT YEAR REPORT NO. CODE TYPE NO. | |||
'0 REPORT NUMBER I 7I8I . | |||
21 22 l==J 23 101"0191* | |||
24 26 L::j 27 10111 28 29 L!J 30 L=J J1 L2J 32 ACTION FUTURE EFFECT SHUTDOWN r:;::;., ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM ~UB. SUPPLIER MANUFACTURER W@W@ LI.JC§) ~ I ol o Io Io I lli.J@ 1.1U@ LBJ@ I c 14 19 Io l@ | |||
33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ | |||
jThe operators and test engineer failed to realize that selecting a target | |||
!J:II] 1rod with defective position indication might result in improper sequencing.! | |||
EIJ]J 1Precautionary statements have been added to the reactor control system IJ:II] Joperating procedure and the yellow engraved tag installed on the control IJJ3] 1room console adjacent to the rod selector switches. | |||
7 B 9 80 FACILITY IJQ\ METHOD OF STATUS % POWER OTHER STATUS \.:::;J DISCOVERY DISCOVERY DESCRIPTION | |||
[ill] lliJ@ Io Io I o l@I N/A LJU@I Operator Observation 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT r:::;;., | |||
RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @ | |||
[2]TI Lk.J@ UJ@I N/A I 45 N/A 8 9 10 11 44 80 PERSONNEL EXPOSURES ~ | |||
NUMBER r:;::;., TYPE DESCRIPTION | |||
[2IZJ I o I o I o lLJ@ __N_/_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____. | |||
7 8 9 11 12 13 80 PERSONNEL INJURIES Q NUMBER DESCRIPTION~ | |||
~ Io I o I ol@.___N_:./_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____. | |||
7 8 9 11 12 80 LOSS O* OR DAMAGE TO FACILITY 143' TYPE DESCRIPTION '.:::::J | |||
[Q2:) ~@).___N_/A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____. | |||
7 8 9 10 80 PUBLICITY C\ NRC USE ONLY ISSUED(,;\ DESCRIPTION~ | |||
. [ill] lJLJ6~_N...:.../_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __. II IIIIIIII III 7 8 9 10 58 69 80}} |
Revision as of 10:03, 20 October 2019
ML18347B178 | |
Person / Time | |
---|---|
Site: | Palisades |
Issue date: | 04/28/1978 |
From: | Hoffman D Consumers Power Co |
To: | James Keppler NRC/RGN-III |
References | |
LER 1978-000-00 | |
Download: ML18347B178 (2) | |
Text
,")
consumers Power
-* ,~;r . . . _. . ~'7'".i~.::~--4r**./*
-.-"J company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 April 28, 1978 _:,,, ..,.,,
- " ~*
~ *(".:
CJ 0)
~ '"'
-\ :'4'!!:
~
.., ..
(.;)~, ..:
- ~
~
""
i:;o~C::
- o_UI
~o~
';f;~~j
' --
~
~rr.
<o oo
- "'11(})
(/'I_.;
c;.-o s:;!mo ~.:
7!.@
-f<"I ::ic:
";O --!
-< r>.'.) c;.
C) :Ji:!.
Mr James G Keppler r:n ~
Office of Inspection and Enforcement <!> '-9 Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LER OUT-OF-SEQUENCE ROD WITHDRAWAL The reverse side describes a reportable occurrence under Technical Specifi-cation 6.9.2.A.2 for the Palisades Plant. This event was identified by TWX on April 17, 1978.
David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement
NRC FORM366
- PALISADES U.S. NUCLEAR REGULATORY COMMISSION (7-77)
LICENSEE EVENT REPORT CONTROL BLOCK: I 1
10 6
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
~8 IM I I I p I A I LI 1 101 010 I 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 101 411 11 I ll l 101 I 10 7 9 LICENSEE CODE 14 ~5 LICENSE NUMBER
- 25 26 LICENSE TYPE JO 57 CAT 58 CON'T
!TI:!] :~~~~~ ~I o I 5 I o I o I o I 21 5 I 5 IG)I o I 4 11 I 5 I 71 8 I© I o I 4 I 2 I 8 I 7 I 8 10 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
IDuring Low Power Physics Tests, regulating group 2 rods were withdrawn out-I
!]JI] jof-sequence ... This is contrary to the requirements of TS 3.10.5.b and the CQIIJ jLow Power Physics Test procedures. The out-ofmsequence maneuver occurred
[£ITJ Jduring sequential rod worth measurements when a faulty position indication C2:I§] 1for CRDM '#.25 (group 1) indicated it was fully withdrawn. When the condi-t m2J 1 tion was detected, a different target rod was selected and the test con-
[]]]] tinued. Continuous boration was in progress.
1 I 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
[ill]
7 8 IRIB I@
9 10 w@ w@ 1c1R1n1R1v1E1@ w@
11 12 13 18 19 w@
20 SEQUENTIAL OCCURRENCE REPORT REVISION r.:;.., LE RIRO CV ENT YEAR REPORT NO. CODE TYPE NO.
'0 REPORT NUMBER I 7I8I .
21 22 l==J 23 101"0191*
24 26 L::j 27 10111 28 29 L!J 30 L=J J1 L2J 32 ACTION FUTURE EFFECT SHUTDOWN r:;::;., ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM ~UB. SUPPLIER MANUFACTURER W@W@ LI.JC§) ~ I ol o Io Io I lli.J@ 1.1U@ LBJ@ I c 14 19 Io l@
33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
jThe operators and test engineer failed to realize that selecting a target
!J:II] 1rod with defective position indication might result in improper sequencing.!
EIJ]J 1Precautionary statements have been added to the reactor control system IJ:II] Joperating procedure and the yellow engraved tag installed on the control IJJ3] 1room console adjacent to the rod selector switches.
7 B 9 80 FACILITY IJQ\ METHOD OF STATUS % POWER OTHER STATUS \.:::;J DISCOVERY DISCOVERY DESCRIPTION
[ill] lliJ@ Io Io I o l@I N/A LJU@I Operator Observation 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT r:::;;.,
RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @
[2]TI Lk.J@ UJ@I N/A I 45 N/A 8 9 10 11 44 80 PERSONNEL EXPOSURES ~
NUMBER r:;::;., TYPE DESCRIPTION
[2IZJ I o I o I o lLJ@ __N_/_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____.
7 8 9 11 12 13 80 PERSONNEL INJURIES Q NUMBER DESCRIPTION~
~ Io I o I ol@.___N_:./_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____.
7 8 9 11 12 80 LOSS O* OR DAMAGE TO FACILITY 143' TYPE DESCRIPTION '.:::::J
[Q2:) ~@).___N_/A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____.
7 8 9 10 80 PUBLICITY C\ NRC USE ONLY ISSUED(,;\ DESCRIPTION~
. [ill] lJLJ6~_N...:.../_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __. II IIIIIIII III 7 8 9 10 58 69 80