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{{#Wiki_filter:.** -*"-* consumers Power company
{{#Wiki_filter:,--~
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s ss10N -'lrof/t i(,c .... "clfo 11 !"-........ clff11 General Offices: 212 West Michigan Avenue, Jackson, Ml (/if*  
                                                                          ~~\'.
';,Code 517 788-0550 August 31, 1976 Mr James G. Keppler Office of Inspection  
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& Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DJCKET 50-255, LICENSE DPR-20 -PALISADES PLANT ER-76-26 -PLANT DISCHARGE TEMPERATURE
                                                                                                  *''I
* Attached is a reportable occurrence which relates to the Palisades Plant. David A. Bixel Assistant Nuclear Licensing Administrator
                                                                                                'f.. /".)'
* SEP 3 1976
f~e'lht1Qt,-
.LICENSEE EVENT REPORT
                                                                  .... ,                             o CE1vr '<----
* Palisades CONTROL BLOCK: ._I
0
[PLEASE PRINT ALL REQUIRED INFORMATION]
                                                                                                                                      'Y consumers                              f*
1 6 LICENSE NUMBER lolol-lolol ololol-lolol 15 25 REPORT LICENSE TYPE 14111111111 26 30 EVENT OATE EVENT TYPE Io I 1 I 31 32 REPORT DATE @I!]coN'T I *I *I 7 8 57 58 ,TY;j* REPORT SOURCE OOCKl;T NUMBER 1015101-1Ol215151 101s111117161 1018131117161 59 60 61 68 69 74 75 80 EVENT DESCRIPTION lol2J !During a test to determine the effect of diverting dilution water flow (to the main I 7 8 9 lol31 I condenser) on 7 8 9 lol41 I rapidly than expected.
:. J Cl.s.             ,;J,.._ ..,,/.         ::-1 Power                                        cu,.11t llEGIJl c:,,oMM              '"""'
* 80 I 80 I Readjustment of the CT pump discharge valve to terminate plant output the level in the cooling tower basin increased more 7 8 9 80 lol5l )this increase resulted in a closed cycle condenser cooling system discharge temper-J 7 8 9 lolsl ature maximum of 6.6&deg;F and a discharge time over the allowable 5&deg;F limit of 7 8 9 35 minutes. ER-7 -2 SYSTEM CAUSE COOE CODE COMPONENT CODE IHIFI l!J lzlzlzlzlzlzJ 7 8 9 10 11 12 17 CAUSE DESCRIPTION PRME COMPONENT SUPPLER L!.J 43 COMPONENT MANUFACTURER I z I 9 I 9 I 91 44 47 VIOLATION LU 48 80 about 80 lol0I jBased on calculations provided by the A-E, a rapid rise in the CT basin level was I 7 8 9 lolsl lnot expected. 7 8 9 The test procedure was revised to accommodate this change and rea-* lsonably good control was achieved. 7 8 9 FACILITY STATUS % POWER OTHER STATUS EE] w I 1 Io I o I NA 7 8 9 . 10 12 13 FORM OF ACTIVITY CONTENT rn RELEASED OF RELEASE AMOUNT OF ACTIVITY wl NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 1010 I 01 UJ 7 8 9 11 12 13 PERS"ONNEL INJURIES NUMBER DESCRIPTION 44 44 METHOD OF DISCOVERY 45 45 NA [ill I 0 I 0 I 0 I NA 7 8 9 11 12 PROBABLE CONSEQUENCES NPDES permit levels were not exceeded. 7 B 9 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Efil L:?J 7 B 9 10 PUBLICITY
company                    . - *.
[I0 None. 7 B 9 NA 46 DISCOVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 I 80 I 80 80 BO BO BO BO BO BO
                                                                  ~*-I
* ADDITIONAL FACTORS 7 B 9 BO [!1fil 7 89 BO}}
                                                                              *~o;, s ss10N -'lrof/t "clfo11 i(,c E~~ ~
General Offices: 212 West Michigan Avenue, Jackson, Ml       (/if* 19~\
clff11    ';,Code 517 788-0550 August 31, 1976 Mr James G. Keppler Office of Inspection & Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DJCKET 50-255, LICENSE DPR                 PALISADES PLANT ER-76                 PLANT DISCHARGE TEMPERATURE
* Attached is a reportable occurrence which relates to the Palisades Plant.
David A. Bixel Assistant Nuclear Licensing Administrator SEP               3 1976
 
                                                      .LICENSEE EVENT REPORT
* Palisades CONTROL BLOCK:       ._I__.,_..___.__,___,_~I                              [PLEASE PRINT ALL REQUIRED INFORMATION]
1                       6 LICENSE              EVENT LICENSE NUMBER                                 TYPE                TYPE lolol-lolol ololol-lolol                             14111111111                 Io I 1 I 15                                            25    26                    30    31 32 REPORT    REPORT REPORT DATE
                                  ,TY;j*  SOURCE            OOCKl;T NUMBER                        EVENT OATE
    @I!]coN'T I *I *I                       ~        1015101-1Ol215151                     101s111117161                   1018131117161 75                  80 7    8          57    58        59       60     61                               68   69                       74 EVENT DESCRIPTION lol2J !During a test to determine the effect of diverting dilution water flow (to the main                                                   I 7   8 9                                                                                                                                     80 lol31 Icondenser)           on plant output the level in the cooling tower basin increased more 80 I
7   8 9 lol41 Irapidly        than expected.
* Readjustment of the CT pump discharge valve to terminate                                             I 7   8 9                                                                                                                                     80 lol5l )this increase resulted in a closed cycle condenser cooling system discharge temper-J 7   8 9                                                                                                                                     80 lolsl   ature maximum of 6.6&deg;F and a discharge time                                 over the allowable 5&deg;F limit                   of about 7   8 9 35 minutes.               ER-7 -2                         PRME                                                                    80 SYSTEM       CAUSE                                       COMPONENT            COMPONENT COOE       CODE             COMPONENT CODE             SUPPLER            MANUFACTURER          VIOLATION
  ~      IHIFI l!J                   lzlzlzlzlzlzJ                   L!.J           I z I 9 I 9 I 91           LU 7    8 9    10          11        12                      17        43          44               47         48 CAUSE DESCRIPTION lol0I jBased on calculations provided by the A-E, a rapid rise in the CT basin level was                                                       I 7   8 9                                                                                                                                     80 lolsl lnot expected.                 The test procedure was revised to accommodate this change and rea-                                       I 7    8 9                                                                                                                                    80
  ~ lsonably good control was achieved.                                                                                                         I
* 7     8 9                                                                                                                                     80 FACILITY                                                       METHOD OF STATUS             % POWER               OTHER STATUS         DISCOVERY                      DISCOVERY DESCRIPTION EE]
7    8 w
9 I 1 Io I o12I
                            . 10                 13 NA 44
                                                                                  ~
45      46 NA 80 FORM OF ACTIVITY       CONTENT 7
rn   8 RELEASED
                ~
9 OF RELEASE wl 10 11 AMOUNT OF ACTIVITY NA 44        45 LOCATION OF RELEASE NA BO PERSONNEL EXPOSURES NUMBER           TYPE     DESCRIPTION
  ~ 1010             I 01 UJ                                                   NA 7     8 9             11 12         13                                                                                                     BO PERS"ONNEL INJURIES NUMBER           DESCRIPTION
[ill I 0 I 0 I 0 I                                                           NA 7     8 9             11 12                                                                                                                 BO PROBABLE CONSEQUENCES
  ~ ~one; NPDES permit levels                           were not exceeded.
7 B 9                                                                                                                                         BO LOSS OR DAMAGE TO FACILITY TYPE       DESCRIPTION EfilB 9L:?J 7                 10 NA BO PUBLICITY
[I0 None.
7     B 9                                                                                                                                     BO ADDITIONAL FACTORS
* ~B 9!;--------L~----------------------------------------------------~
7                                                                                                                                            BO
[!1fil 7     89                                                                                                                                     BO}}

Latest revision as of 15:08, 2 February 2020

Licensee Event Report ER-76-26 - Plant Discharge Temperature Increased More Rapidly than Expected
ML18352A320
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/31/1976
From: Bixel D
Consumers Power Co
To: James Keppler
NRC/RGN-III
References
LER 1976-026-00
Download: ML18352A320 (2)
v • d • e


Text

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  • ~o;, s ss10N -'lrof/t "clfo11 i(,c E~~ ~

General Offices: 212 West Michigan Avenue, Jackson, Ml (/if* 19~\

clff11 ';,Code 517 788-0550 August 31, 1976 Mr James G. Keppler Office of Inspection & Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DJCKET 50-255, LICENSE DPR PALISADES PLANT ER-76 PLANT DISCHARGE TEMPERATURE

  • Attached is a reportable occurrence which relates to the Palisades Plant.

David A. Bixel Assistant Nuclear Licensing Administrator SEP 3 1976

.LICENSEE EVENT REPORT

  • Palisades CONTROL BLOCK: ._I__.,_..___.__,___,_~I [PLEASE PRINT ALL REQUIRED INFORMATION]

1 6 LICENSE EVENT LICENSE NUMBER TYPE TYPE lolol-lolol ololol-lolol 14111111111 Io I 1 I 15 25 26 30 31 32 REPORT REPORT REPORT DATE

,TY;j* SOURCE OOCKl;T NUMBER EVENT OATE

@I!]coN'T I *I *I ~ 1015101-1Ol215151 101s111117161 1018131117161 75 80 7 8 57 58 59 60 61 68 69 74 EVENT DESCRIPTION lol2J !During a test to determine the effect of diverting dilution water flow (to the main I 7 8 9 80 lol31 Icondenser) on plant output the level in the cooling tower basin increased more 80 I

7 8 9 lol41 Irapidly than expected.

  • Readjustment of the CT pump discharge valve to terminate I 7 8 9 80 lol5l )this increase resulted in a closed cycle condenser cooling system discharge temper-J 7 8 9 80 lolsl ature maximum of 6.6°F and a discharge time over the allowable 5°F limit of about 7 8 9 35 minutes. ER-7 -2 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT COOE CODE COMPONENT CODE SUPPLER MANUFACTURER VIOLATION

~ IHIFI l!J lzlzlzlzlzlzJ L!.J I z I 9 I 9 I 91 LU 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION lol0I jBased on calculations provided by the A-E, a rapid rise in the CT basin level was I 7 8 9 80 lolsl lnot expected. The test procedure was revised to accommodate this change and rea- I 7 8 9 80

~ lsonably good control was achieved. I

  • 7 8 9 80 FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EE]

7 8 w

9 I 1 Io I o12I

. 10 13 NA 44

~

45 46 NA 80 FORM OF ACTIVITY CONTENT 7

rn 8 RELEASED

~

9 OF RELEASE wl 10 11 AMOUNT OF ACTIVITY NA 44 45 LOCATION OF RELEASE NA BO PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~ 1010 I 01 UJ NA 7 8 9 11 12 13 BO PERS"ONNEL INJURIES NUMBER DESCRIPTION

[ill I 0 I 0 I 0 I NA 7 8 9 11 12 BO PROBABLE CONSEQUENCES

~ ~one; NPDES permit levels were not exceeded.

7 B 9 BO LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION EfilB 9L:?J 7 10 NA BO PUBLICITY

[I0 None.

7 B 9 BO ADDITIONAL FACTORS

  • ~B 9!;--------L~----------------------------------------------------~

7 BO

[!1fil 7 89 BO

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