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{{#Wiki_filter:* *
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* _,,-January 5, 1976 / .... , ... Mr. J. G. Keppler US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT ,'**, . */ .. consumers Power company Transmitted attached is a "License Event Report" for the Palisades Plant . Ralph B. Sewell (Signed) Ralph B. Sewell Nuclear Licensing Administrator CC:, Director of Nuclear Reactor Regulation, USNRC -, . _ . . *---=--.* 111 
consumers
* Power company January 5, 1976
                        /
                                  ...
                              .... ,
Mr. J. G. Keppler US Nuclear Regulatory Commission         ,'**,
799 Roosevelt Road Glen Ellyn, IL 60137
                                                  . */ ..
DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT Transmitted attached is a "License Event Report" for the Palisades Plant .
* Ralph B. Sewell (Signed)
Ralph B. Sewell Nuclear Licensing Administrator CC:, Director of Nuclear Reactor Regulation, USNRC
*                                                                        -,
                                                                        . _.
111
                                                                  .*---=-- .*


** Palisades  
                                                                *IEN~EE                                                      **                Palisades
* [PLEASE PRINT ALL REQUIRED INFORMATION) 1 u:ftle t£J TYPE TYPE 111111111 B 30 I 9 I 9 I 31 32 (lo) EVENT DATE (//)_ REPORT DATE l1l2l2J1l1J5I lol11ol5l7l51 69 74 75 BO lo'2f I When the 'A' cooling tower *pump was removed from service following plant shutdown, the I 1 a s ea @Ifil I water lost to the mixing basin caused the temperature at discharge to be 45. 5 degrees I 7 89 . @El IF.* The delta-Twas 8.4 degrees F which .is above the Tech Spec limit of 5 degrees F. I 1 a s ea folsl I Due to the infrequency of occurrence and the negligible impact on environment, a Tech I 7 8 9 80 lolsl I Spec Change has been requested to permit sJ:tort periods of time (continued on Li'ne 18) I 7 8 9 (I j\ fl'/)
[PLEASE PRINT ALL REQUIRED INFORMATION)
PRME06) /J 'J) . ht>)' BO SYST{M .J J COMPONENT ( '4' CODE CODE COMPO ENT CODE 6UPPUER MANUFACTURER VD.ATON @El I Hf Ff' W I vi Al LI vi ol PI W I BI 21 5 I ol W 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION
* 1 u:ftle TYPE t£J TYPE
{/ 'I) Iola! I The valve closing time is too slow to prevent weir overflow following pump trip. I 7 8 9 80 lolsl *1i Bl 7 f!°ACIUtY . I :u J (;J. 2.) ME1'ff011' OF (:i. 'I J STATUS %
                                                                                                                    ~4  111111111 I 9 I 9 I B                      30    31     32 (lo)                             (//)_
OTHEFI STATUS DISCOVERY DISCOVERY' DESCRIPTION.
EVENT DATE                        REPORT DATE l1l2l2J1l1J5I                       lol11ol5l7l51 69                         74     75                   BO lo'2f I When       the 'A' cooling tower *pump was removed from service following plant shutdown, the I 1   as                                                                                                                                                          ea
*f.Q_j I ol ol 0 I NA I w I Environmental Monitoring Progra.Itl EJ2] 7 8 9 10 12 13 44 45 46 FORM OF.* r1 / 1 1 CONTENT (;i.t,,) L;( 1/ rn OF  
    @Ifil I water       lost to the mixing basin caused the temperature at discharge to be 45. 5 degrees                                                             I 7   89                                                       .                                                                                                   ~
._I ___
    @El   IF.*       The delta-Twas 8.4 degrees F which .is above the Tech Spec limit of 5 degrees F.                                                                 I 1   as                                                                                                                                                          ea folsl I Due       to the infrequency of occurrence and the negligible impact on environment, a Tech                                                               I 7   8 9                                                                                                                                                         80 lolsl I Spec       Change has been requested to permit sJ:tort periods of time (continued on Li'ne 18)                                                           I 7   8 9 (I j\           fl'/)                     ~1.*.r-I                      PRME06)                 /J 'J)             . ht>)'                             BO SYST{M         C~USE                        .J J                     COMPONENT               CO~PoNiNf              ( '4' CODE         CODE                 COMPO ENT CODE                     6UPPUER               MANUFACTURER           VD.ATON
__ __.I (:1.',p) . LOCATION of RELEASE NA 7 8 9 10 11 ,44 45 PERSONNEL EXPOSURES 80 80
    @El I Hf Ff'           W             I vi Al     LI     vi ol PI               W               I BI   21 5 I ol           W 7   8 9   10             11         12                               17         43           44                   47         48 CAUSE DESCRIPTION {/ 'I)
: 9) rpf DESCRIPTION(.:U)
Iola! I The     valve closing time is too slow to prevent weir overflow following pump trip.                                                                     I 7 8 9                                                                                                                                                             80 lolsl
[ill] I 01 01 01 z .':::--* ___ N_A ____________________
*1i7    89!:--/~~~0:-;-)~~~~~------~------~--,.7~~~}-.,....-------------~~----~~----B~O f!°ACIUtY       .     I :uJ                        (;J. 2.)               ME1'ff011' OF                           (:i. 'I J Bl
-.J 7 8 9 11 12 13 BO PERSONNEL INJURIES NUMBEflQ1!}
                                    ~WER EJ2]
OESCRIPTIDN(lJ}  
7    8 STATUS
'EE] I o I o I ol NA 7 8 9 11 12 13 'I) BO Probable consequ'ences I No effect on public health and safety. 7 8 9 LOSS OR DAMAGE TO FACILITY [YPEfUJ. DESCRIPTION t1 b) E1fil LIJ NA 7 8 9
              *f.Q_j 9                10
* 10 PUBLICITY (3 ')) EE] l Copies of this report are being sent to MI news.media.  
                                  %
*89 ADDITIONAL FACTORS (} I with delta-T above 5 degrees F. (A0-75-27) 7 89 80 80 I 80 1 ___ ,, !°" BO rn 7 osr---------------------------------------------------------8..JO}}
I ol   ol 0     I 12 13 OTHEFI STATUS NA 44 I   w DISCOVERY 45 I Environmental 46 DISCOVERY'DESCRIPTION.
Monitoring Progra.Itl 80 FORM OF.* r1                                     /     1 1                                                             (:1.',p)    .
ACTIVIT~~/ CONTENT         (;i.t,,)             L;(   1/
of rn       Rr~S,EO        OF r~LrS~ ._I___AM_O_u_N.,....T-0-~-~;....CT-IV_ITY_ ___.I                                       LOCATION NA RELEASE 7   8     9                 10     11                                           ,44         45                                                               80 PERSONNEL EXPOSURES NUMBE~ 9)
[ill] I 01 01 01 rpfz .':::--*___
                                        ~    DESCRIPTION(.:U)
N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-.J 7   8 9               11     12     13                                                                                                                         BO PERSONNEL INJURIES NUMBEflQ1!}         OESCRIPTIDN(lJ}
  'EE] I o I o I         ol                     NA 7   8 9               11     ~-----------------------------------------------------~-----------1 12       13 'I)                                                                                                                     BO Probable consequ'ences
  ~      I No effect on public health and safety.
7   8 9                                                                                                                                                         80 LOSS OR DAMAGE TO FACILITY
[YPEfUJ. DESCRIPTION       t1 b)
E1fil LIJ 7 8 9
* 10 NA 80 PUBLICITY     (3 '))
EE] l     Copies of this report are being sent to MI news.media.
I 89                                                                                                                                                            80
* ADDITIONAL FACTORS (}               ~).
  ~      I with delta-T above 5 degrees F.                                       (A0-75-27) 7   89                                                                                                                             1___ ,                       BO rnosr---------------------------------------------------------8..JO 7
                                                                                                                                          !°"}}

Revision as of 08:05, 20 October 2019

Licensee Event Report AO-75-27 - Discharge of Cooling Water to Be 45.5 Degrees F, & Delta-T Above 5oF Limit
ML18353A842
Person / Time
Site: Palisades Entergy icon.png
Issue date: 01/05/1976
From: Sewell R
Consumers Power Co
To: James Keppler
Office of Nuclear Reactor Regulation
References
LER AO 1975-027-00
Download: ML18353A842 (2)
v • d • e


Text

_,,-

consumers

  • Power company January 5, 1976

/

...

.... ,

Mr. J. G. Keppler US Nuclear Regulatory Commission ,'**,

799 Roosevelt Road Glen Ellyn, IL 60137

. */ ..

DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT Transmitted attached is a "License Event Report" for the Palisades Plant .

  • Ralph B. Sewell (Signed)

Ralph B. Sewell Nuclear Licensing Administrator CC:, Director of Nuclear Reactor Regulation, USNRC

  • -,

. _.

111

.*---=-- .*

  • IEN~EE ** Palisades

[PLEASE PRINT ALL REQUIRED INFORMATION)

  • 1 u:ftle TYPE t£J TYPE

~4 111111111 I 9 I 9 I B 30 31 32 (lo) (//)_

EVENT DATE REPORT DATE l1l2l2J1l1J5I lol11ol5l7l51 69 74 75 BO lo'2f I When the 'A' cooling tower *pump was removed from service following plant shutdown, the I 1 as ea

@Ifil I water lost to the mixing basin caused the temperature at discharge to be 45. 5 degrees I 7 89 . ~

@El IF.* The delta-Twas 8.4 degrees F which .is above the Tech Spec limit of 5 degrees F. I 1 as ea folsl I Due to the infrequency of occurrence and the negligible impact on environment, a Tech I 7 8 9 80 lolsl I Spec Change has been requested to permit sJ:tort periods of time (continued on Li'ne 18) I 7 8 9 (I j\ fl'/) ~1.*.r-I PRME06) /J 'J) . ht>)' BO SYST{M C~USE .J J COMPONENT CO~PoNiNf ( '4' CODE CODE COMPO ENT CODE 6UPPUER MANUFACTURER VD.ATON

@El I Hf Ff' W I vi Al LI vi ol PI W I BI 21 5 I ol W 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION {/ 'I)

Iola! I The valve closing time is too slow to prevent weir overflow following pump trip. I 7 8 9 80 lolsl

  • 1i7 89!:--/~~~0:-;-)~~~~~------~------~--,.7~~~}-.,....-------------~~----~~----B~O f!°ACIUtY . I :uJ (;J. 2.) ME1'ff011' OF (:i. 'I J Bl

~WER EJ2]

7 8 STATUS

  • f.Q_j 9 10

%

I ol ol 0 I 12 13 OTHEFI STATUS NA 44 I w DISCOVERY 45 I Environmental 46 DISCOVERY'DESCRIPTION.

Monitoring Progra.Itl 80 FORM OF.* r1 / 1 1 (:1.',p) .

ACTIVIT~~/ CONTENT (;i.t,,) L;( 1/

of rn Rr~S,EO OF r~LrS~ ._I___AM_O_u_N.,....T-0-~-~;....CT-IV_ITY_ ___.I LOCATION NA RELEASE 7 8 9 10 11 ,44 45 80 PERSONNEL EXPOSURES NUMBE~ 9)

[ill] I 01 01 01 rpfz .':::--*___

~ DESCRIPTION(.:U)

N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-.J 7 8 9 11 12 13 BO PERSONNEL INJURIES NUMBEflQ1!} OESCRIPTIDN(lJ}

'EE] I o I o I ol NA 7 8 9 11 ~-----------------------------------------------------~-----------1 12 13 'I) BO Probable consequ'ences

~ I No effect on public health and safety.

7 8 9 80 LOSS OR DAMAGE TO FACILITY

[YPEfUJ. DESCRIPTION t1 b)

E1fil LIJ 7 8 9

  • 10 NA 80 PUBLICITY (3 '))

EE] l Copies of this report are being sent to MI news.media.

I 89 80

  • ADDITIONAL FACTORS (} ~).

~ I with delta-T above 5 degrees F. (A0-75-27) 7 89 1___ , BO rnosr---------------------------------------------------------8..JO 7

!°"

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