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=Text=
=Text=
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........ _ .... -.-"J consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
consumers Power
* Area Code 517 788-0550 April 28, 1978 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -LER-78 -OUT-OF-SEQUENCE ROD WITHDRAWAL CJ ;:;; -\ ""  
                                  -*                                                      ,~;r  . . . _. . ~'7'".i~.::~--4r**./*
;;o_UI s:;!mo -f<"I ";O -< C) r:n <!> _:,,, 0) :'4'!!: -' -r>.'.) '-9 .. :" ,.,, *(".: '"'  
                                                                                                            -.-"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 NRC FORM366 (7-77) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: I 10 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 7 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 9 LICENSEE CODE 14 LICENSE NUMBER
                                                                                                                  ~                    *(".:
* 25 26 LICENSE TYPE JO 57 CAT 58 CON'T !TI:!] 7 8 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&#xa9; I o I 4 I 2 I 8 I 7 I 8 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
CJ                  0)
I During Low Power Physics Tests, regulating group 2 rods were withdrawn out-I !]JI] jof-sequence  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 [&#xa3;ITJ Jduring sequential rod worth measurements when a faulty position indication C2:I&sect;] 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-[]]]] 1 tinued. Continuous boration was in progress. 7 8 9 SYSTEM CAUSE CAUSE COMP. CODE CODE SUBCODE COMPONENT CODE SUBCODE [ill] IRIB I@ w@ w@ 1c1R1n1R1v1E1@
                                                                                                                  ~
w@ 7 8 9 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT REPORT NO. CODE TYPE VALVE SUBCODE w@ 20 r.:;.., LE RIRO CV ENT YEAR '0 REPORT I 7 I 8 I . NUMBER 21 22 l==J 101"0191*
                                                                                                                                  .., ..
L::j 10111 L!J L=J 23 24 26 2 7 28 29 30 J 1 REVISION NO. L2J 32 I 80 ACTION FUTURE EFFECT SHUTDOWN r:;::;., ATTACHMENT NPRD-4 PRIME COMP. TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUPPLIER COMPONENT MANUFACTURER W@W@ LI.JC&sect;) I ol o Io Io I lli.J@ 1.1U@ LBJ@ 33 34 35 36 3 7 40 41 42 43 I c 14 19 Io l@ CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ 44 47 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 FACILITY IJQ\ STATUS % POWER OTHER STATUS \.:::;J [ill] lliJ@ Io Io I o l@I N/A METHOD OF DISCOVERY DISCOVERY DESCRIPTION LJU@I Operator Observation 8 9 10 12 13 44 ACTIVITY CONTENT r:::;;., RELEASED OF RELEASE AMOUNT OF ACTIVITY [2]TI Lk.J@ UJ@I N/A I 8 9 10 11 44 45 46 LOCATION OF RELEASE @ N/A 45 PERSONNEL EXPOSURES 80 80 80 NUMBER r:;::;., TYPE DESCRIPTION
:~
[2IZJ I o I o I o lLJ@ __ N_/_A _____________________
                                                                                              ~
____. 7 8 9 11 12 13 PERSONNEL INJURIES Q 80 NUMBER Io I o I ol@.___N_:./_A
                                                                                              ""
_______________________
i:;o~C::
___. 7 8 9 11 12 80 LOSS O* OR DAMAGE TO FACILITY 143' TYPE DESCRIPTION  
                                                                                          ;;o_UI
'.:::::J [Q2:)
                                                                                          ~o~
__________________________
                                                                                          ';f;~~j
___. 7 8 9 10 80 PUBLICITY C\ ISSUED(,;\ . [ill]
                                                                                                                  ' --
____________________
                                                                                                                      ~
_. I I I I I I I I I I I I I NRC USE ONLY 7 8 9 10 58 69 80}}
                                                                                                                                  ~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&#xa9; 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
[&#xa3;ITJ Jduring sequential rod worth measurements when a faulty position indication C2:I&sect;] 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&sect;)           ~            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

License Event Report LER-78-000-00 Re Out-of-Sequence Rod Withdrawal
ML18347B178
Person / Time
Site: Palisades Entergy icon.png
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

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consumers Power

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-.-"J company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

  • Area Code 517 788-0550 April 28, 1978 _:,,, ..,.,,
" ~*

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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