ML18043A338: Difference between revisions

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| issue date = 12/18/1978
| issue date = 12/18/1978
| title = Forwards LER#78-040/01X-1
| title = Forwards LER#78-040/01X-1
| author name = HOFFMAN D P
| author name = Hoffman D
| author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.),
| author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.),
| addressee name = KEPPLER J G
| addressee name = Keppler J
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
| docket = 05000255
| docket = 05000255
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:r----... -* consumers Power company General Offices: 212 West Michigan Avenue, .Jackson, Michigan 49201
{{#Wiki_filter:r----
* Area Code 517 788-0550 December 18, 1978 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roo.sevel t Road Glen Ellyn, IL 60137 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -LER 78-040 On the reverse side is Revision 1 of Licensee Event Re-oort 78-040 which is reportable under Technical Specification 6.9.2.a.(2).
consumers Power company General Offices: 212 West Michigan Avenue, .Jackson, Michigan 49201
David P Hoffman (Signed) David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement REGULATO ,n.v 0nur"vr.1
* Area Code 517 788-0550 December 18, 1978 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roo.sevel t Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR           PALISADES PLANT - LER 78-040 On the reverse side is Revision 1 of Licensee Event Re-oort 78-040 which is reportable under Technical Specification 6.9.2.a.(2).
\ -'I\ i '* v.i 781.221. Od--SC r:-n r b Jt--L COPY  
David P Hoffman (Signed)
David P Hoffman Assistant Nuclear Licensing Administrator CC:   Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement REGULATO,n.v
                                              \ -                 'I\ i 0nur"vr.1 r:-n r
                                                                          '*   v.i -~~    b  Jt--L  COPY 781.221. Od--SC
 
                                                                                                  ~JPDATE' REPOR- PREVIOUS REPOR'I' DATE                                                  12/12,.:78 Palisades NRC FORM 366                                                                                                                                U.S. NUCLEAR REGULATORY COMMISSION (7*77)
LICENSEE EVENT REPORT CONTROi. BLOCK:            ._I I
_....__._----''---'--'-..,jj 6
0                  (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION!
CLl2J        I          I PI A I 1 I 1 101 o Io I - I oIo I o Io I o I . Io I o 101 4 I 1 1                                                              J 1 1 1 101                I l
                                                              ~S MJ I 7        8  9      LICENSEE COOE                14                                  LICENSE NUMBER                            25      26      LICENSE TYPE          JO    57 CAT SB    ©s CON'T 0JJ 7        8
                    ~~~;~~    L1.J© I 60              61 Cl 5 I oI o I o 12 I 5 I 5 (VI DOCKET NUMBER                    68    69 1 I l    ! 2 I 81 7 I 8 EVENT DATE                74 I© I 11 2 I 1 I 8 I 7 18 10 75      REPORT DATE              BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES                                    (,°Q)
[§Jl]        I During load reduction in prepa~tion for plant shutdown, the volume control tank was being vented to the waste gas surge tank in order to degas the PCS.                            Leakage from the surge tank resuJ,.ted in a gaseous release without the 15-day holdup time required by TS 3.9.17.                                                                                    Upon discovery VCT venting was stopped.                                            Total activity release was 4.314 curie which
~I                is 5,7 percent of the average annual release rate.                                                                                No hazard to public
                                                                                                                                                                                                  .I r;;"'l01          health or safety resulted.
7          s 9'----------------------------------------------~~~----~----------__J L..2...L!..J                                                                                                                                                                                      80 s~5~~M c.\ cc"ou~i (,':;\ s3:~J.3e(,':;\                          COMPONENT CODE                            COMP.
SUBC.QDE VALVE SUBl=,DDE IIill                              I Ml El~ IX I~ ~~ I                                              A!C    I  CjU      I Mj u1e 121@ ~@
7          8                      9            10            ,,                12              13                                  18          19                20 SEQUENTIAL                              OCCURRENCE            REPORT                        REVISION*
              ~    LEAIRQ CVENTYEAR I 7 I 81                  I      I REPORT NO.
I 0141 01                1.....-1
                                                                                                                              . COOE
: 1. o I l!              ~
TYPE
                                                                                                                                                                                      'to.
              \:.Y  REPORT NUMBER                                                                                                                                          L=l            L::J ACTION TAKEN FUTURE ACTION 21          22 oW:eiJT 23 s~~~~i~N 24              26 HOURS 27
                                                                                                        $) Al.J:~iw~~T 28        29 F~~~B.
30 PRIME COMP.
SUPPLIER 31            32 COMPONENT        0 MANUFACTURE'CJ W@l.x.J@ W@)                                            W              Io 10 Io ft) I                L!J@                l2!J~              ~@              I z I 9 I 91 _, I@
33        34                    35                      36              37                    *o      41                  42      ~          4J              "                  *7 CAUSE DESCRIPTION AND COAREC"rlVE ACTIONS                                @.                                                                      An updated I The cause of this occurrence is still under evaluation.
report will be submitted by January 5, 1979.
1 o:ma          ~9---------------------------------------------------------------------------------_j                                                                                              80  .
METHOD OF
                                                                    . 9THER STATUS @
FACILITY STATUS            '!.POWER                                                          DISCOVERY              A            , .._DISCOVERY DESCRIPTION tJ2'
[ill] I DI@ I 019 10 l@I NtA                                                                    I t...:J@I                  nnuruca1,,or                                    l::::J 7
S AJTIVITY      cd~TENT              !:2 13                                          45          46                                                                            80 l,'"'T;jRELEASEO OF RELEASE
~            LQJ@          ~@13* 01~
                                                        ,<\MOUNT PF AC;pvrry curie
                                                                              .x..e-.ij.)                  I Waste gas s~ 1 <le!S!iJlEL~E ~osphere 1        a    9            10 PERSONNEL EXPOSURES 11 f.:;\
                                                                                            ....I          45  -co stack.                                                                      ao NUMBER        (.;&deg;::;\TYPE        DESCRIPTION CTE]8          9 ol o I o11lLZJ@      ::
rr /A 1~3....._________________~----------..,....--------------------------------...J PERSONNEL INJURl!;S                      r;"'.;\                                                                                                                              50 NUMBER                DESCRIPTION~
i:D:!] lo I ol              ol@)...__N~/_A________________________~--~~~-----------------~
1        a s                11        12                                                                                                                                                      80 LOSS OF OR CAMAGE TO FACILITY                t4J'I TYPE      DESCRIPTIO!\I                    '.;:;;J rr::TIJa      IZ l@):n-_N_/fa_.___________________,,.._,_~~-,--------~----------------__J 1            9          10                                                                                        * *:.}
* ao PUBLICITY                  f.:\                                                                                                                          NRC USE ONLY 1sa\JE!:'c.\ DESC~J'(JON        ~
III1J        U!j~...__.1_1 _A_______________________~----~----~-----~-.l                                                                                          I I I I !! I I I I          I )
;        8  s          10                                                                                                                  '              68    69                            80
                                                                                                                                  --  -~--      -    -    - - - - - --    ~--


REPOR-PREVIOUS REPOR'I' DATE 12/12,.:78 Palisades NRC FORM 366 (7*77) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROi. BLOCK: ._I _....__._----''---'--'-..,jj 0 (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION!
I 6 CLl2J I MJ I I PI A I 1 I 1 101 o Io I -I o Io I o Io I o I . Io I o 101 4 I 1 1 J 1 1 1 101 I l s 7 8 9 LICENSEE COOE 14 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT SB &#xa9; CON'T L1.J&#xa9; I Cl 5 I o I o I o 12 I 5 I 5 (VI 1 I l ! 2 I 81 7 I 8 I&#xa9; I 11 2 I 1 I 8 I 7 18 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES
(,&deg;Q) [&sect;Jl] I During load reduction in for plant shutdown, the volume 0JJ 7 8 control tank was being vented to the waste gas surge tank in order to degas the PCS. Leakage from the surge tank resuJ,.ted in a gaseous release without the 15-day holdup time required by TS 3.9.17. Upon discovery VCT venting was stopped. Total activity release was 4.314 curie which is 5,7 percent of the average annual release rate. No hazard to public . I r;;"'l01 health or safety resulted.
L..2...L!..J 7 s 9 IIill 7 8 COMPONENT CODE COMP. VALVE c.\ (,':;\ (,':;\ SUBC.QDE SUBl=,DDE I Ml IX I A!C I CjU I Mj u1e 121@ 9 10 ,, 12 13 18 19 20 LEAIRQ CVENTYEAR
\:.Y REPORT I 7 I 81 NUMBER 21 22 SEQUENTIAL OCCURRENCE REPORT REPORT NO. . COOE TYPE I I I 0141 01 1.....-1 1. o I l! 23 24 26 27 28 29 30 L=l 31 ACTION FUTURE TAKEN ACTION oW:eiJT HOURS $)
PRIME COMP. W@l.x.J@ W@) W Io 10 Io ft) I L!J@
33 34 35 36 37 *o 41 42 SUPPLIER 4J 80 REVISION*
'to. L::J 32 COMPONENT MANUFACTURE'CJ 0 I z I 9 I 91 _, I@ " *7 CAUSE DESCRIPTION AND COAREC"rlVE ACTIONS @. I The cause of this occurrence is still under evaluation.
An updated report will be submitted by January 5, 1979. o:m 1 a . 9THER STATUS @ 80 . FACILITY STATUS '!.POWER [ill] I DI@ I 019 10 l@I NtA I 7 S AJTIVITY
!:2 13 l,'"'T;jRELEASEO OF RELEASE ,<\MOUNT PF AC;pvrry . LQJ@ curie .x..e-.ij.)
1 a 9 10 11 I .... PERSONNEL EXPOSURES f.:;\ NUMBER (.;&deg;::;\TYPE DESCRIPTION METHOD OF DISCOVERY A , .._DISCOVERY DESCRIPTION tJ2' t...:J@I nnuruca1,,or l::::J 45 46 I Waste gas 45 -co stack. 80 ao CTE] ol o I o lLZJ@ rr /A 8 9 11 ::
________________
PERSONNEL INJURl!;S r;"'.;\ 50 NUMBER i:D:!] lo I ol
________________________
1 a s 11 12 80 LOSS OF OR CAMAGE TO FACILITY t4J'I TYPE DESCRIPTIO!\I
'.;:;;J rr::TIJ IZ l@):n-_N_/fa_.
__________________
1 a 9 10 * *:.}
* ao PUBLICITY f.:\ 1sa\JE!:'c.\ III1J _______________________
NRC USE ONLY I I I I !! I I I I I ) ; 8 s 10 ' 68 69 80 -----------..
consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
* Area Code 517 788-0550 December 18, 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 78-040 On the reverse side is Revision 1 of Licensee Event Report 78-040 which is reportable under Technical Specification 6.9.2.a.(2).
* Area Code 517 788-0550 December 18, 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 PALISADES PLANT - LER 78-040 On the reverse side is Revision 1 of Licensee Event Report 78-040 which is reportable under Technical Specification 6.9.2.a.(2).
David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement}}
David P Hoffman Assistant Nuclear Licensing Administrator CC:     Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement}}

Latest revision as of 14:06, 3 February 2020

Forwards LER#78-040/01X-1
ML18043A338
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/18/1978
From: Hoffman D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML18043A339 List:
References
NUDOCS 7812210230
Download: ML18043A338 (3)


Text

r----

consumers Power company General Offices: 212 West Michigan Avenue, .Jackson, Michigan 49201

  • Area Code 517 788-0550 December 18, 1978 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roo.sevel t Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LER 78-040 On the reverse side is Revision 1 of Licensee Event Re-oort 78-040 which is reportable under Technical Specification 6.9.2.a.(2).

David P Hoffman (Signed)

David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement REGULATO,n.v

\ - 'I\ i 0nur"vr.1 r:-n r

'* v.i -~~ b Jt--L COPY 781.221. Od--SC

~JPDATE' REPOR- PREVIOUS REPOR'I' DATE 12/12,.:78 Palisades NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7*77)

LICENSEE EVENT REPORT CONTROi. BLOCK: ._I I

_....__._-------'--'-..,jj 6

0 (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION!

CLl2J I I PI A I 1 I 1 101 o Io I - I oIo I o Io I o I . Io I o 101 4 I 1 1 J 1 1 1 101 I l

~S MJ I 7 8 9 LICENSEE COOE 14 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT SB ©s CON'T 0JJ 7 8

~~~;~~ L1.J© I 60 61 Cl 5 I oI o I o 12 I 5 I 5 (VI DOCKET NUMBER 68 69 1 I l  ! 2 I 81 7 I 8 EVENT DATE 74 I© I 11 2 I 1 I 8 I 7 18 10 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (,°Q)

[§Jl] I During load reduction in prepa~tion for plant shutdown, the volume control tank was being vented to the waste gas surge tank in order to degas the PCS. Leakage from the surge tank resuJ,.ted in a gaseous release without the 15-day holdup time required by TS 3.9.17. Upon discovery VCT venting was stopped. Total activity release was 4.314 curie which

~I is 5,7 percent of the average annual release rate. No hazard to public

.I r;;"'l01 health or safety resulted.

7 s 9'----------------------------------------------~~~----~----------__J L..2...L!..J 80 s~5~~M c.\ cc"ou~i (,':;\ s3:~J.3e(,':;\ COMPONENT CODE COMP.

SUBC.QDE VALVE SUBl=,DDE IIill I Ml El~ IX I~ ~~ I A!C I CjU I Mj u1e 121@ ~@

7 8 9 10 ,, 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION*

~ LEAIRQ CVENTYEAR I 7 I 81 I I REPORT NO.

I 0141 01 1.....-1

. COOE

1. o I l! ~

TYPE

'to.

\:.Y REPORT NUMBER L=l L::J ACTION TAKEN FUTURE ACTION 21 22 oW:eiJT 23 s~~~~i~N 24 26 HOURS 27

$) Al.J:~iw~~T 28 29 F~~~B.

30 PRIME COMP.

SUPPLIER 31 32 COMPONENT 0 MANUFACTURE'CJ W@l.x.J@ W@) W Io 10 Io ft) I L!J@ l2!J~ ~@ I z I 9 I 91 _, I@

33 34 35 36 37 *o 41 42 ~ 4J " *7 CAUSE DESCRIPTION AND COAREC"rlVE ACTIONS @. An updated I The cause of this occurrence is still under evaluation.

report will be submitted by January 5, 1979.

1 o:ma ~9---------------------------------------------------------------------------------_j 80 .

METHOD OF

. 9THER STATUS @

FACILITY STATUS '!.POWER DISCOVERY A , .._DISCOVERY DESCRIPTION tJ2'

[ill] I DI@ I 019 10 l@I NtA I t...:J@I nnuruca1,,or l::::J 7

S AJTIVITY cd~TENT  !:2 13 45 46 80 l,'"'T;jRELEASEO OF RELEASE

~ LQJ@ ~@13* 01~

,<\MOUNT PF AC;pvrry curie

.x..e-.ij.) I Waste gas s~ 1 <le!S!iJlEL~E ~osphere 1 a 9 10 PERSONNEL EXPOSURES 11 f.:;\

....I 45 -co stack. ao NUMBER (.;°::;\TYPE DESCRIPTION CTE]8 9 ol o I o11lLZJ@  ::

rr /A 1~3....._________________~----------..,....--------------------------------...J PERSONNEL INJURl!;S r;"'.;\ 50 NUMBER DESCRIPTION~

i:D:!] lo I ol ol@)...__N~/_A________________________~--~~~-----------------~

1 a s 11 12 80 LOSS OF OR CAMAGE TO FACILITY t4J'I TYPE DESCRIPTIO!\I '.;:;;J rr::TIJa IZ l@):n-_N_/fa_.___________________,,.._,_~~-,--------~----------------__J 1 9 10 * *:.}

  • ao PUBLICITY f.:\ NRC USE ONLY 1sa\JE!:'c.\ DESC~J'(JON ~

III1J U!j~...__.1_1 _A_______________________~----~----~-----~-.l I I I I !! I I I I I )

8 s 10 ' 68 69 80

-- -~-- - - - - - - - -- ~--

consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

  • Area Code 517 788-0550 December 18, 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 PALISADES PLANT - LER 78-040 On the reverse side is Revision 1 of Licensee Event Report 78-040 which is reportable under Technical Specification 6.9.2.a.(2).

David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement