ML20090D852: Difference between revisions

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                                                                                                                      ~':'                ~~f         f% l To:             Jates P. O'Reilly QZl Directorate "of Regulatory Operations
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                                                                                                                                                  -(N,, '
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To:
Regien I                                                                                   ,
Jates P. O'Reilly QZl
631 Park Avenue King of Prussia, Fennsylvania                                     19406 From:
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Jersey Central Power 6 Light Company Oyster Creek Nuclear Generating Stati6n Docket #50-219 Forked River, New Jersey                                 08731
Directorate "of Regulatory Operations
- +
Regien I 631 Park Avenue King of Prussia, Fennsylvania 19406 From:
Jersey Central Power 6 Light Company Oyster Creek Nuclear Generating Stati6n Docket #50-219 Forked River, New Jersey 08731


==Subject:==
==Subject:==
 
Abnormal Occurrence Report No. 50-219/74/59 4
'                                      Abnormal Occurrence Report No. 50-219/74/59 4
'Ihe following is a preliminary report being submitte'd in compliance with the Technical Specifications, paragraph 6.6.2.
                                        'Ihe following is a preliminary report being submitte'd in compliance with the Technical Specifications, paragraph 6.6.2.
Preliminary Approval:
Preliminary Approval:
                                                                                      /
/
}_                                                                           ./                     / ccats,       M 11/13/74
}_
,                                                                              J.T.Carrol1[Ir.                             Date
./
,                    cc:   Mr. A. Giambusso i
/ ccats, M 11/13/74 J.T.Carrol1[Ir.
i 11791 8303030239 741113 PDR ADOCK 05000219 S                     PDR COPY SENT REGION '               -2
Date cc:
Mr. A. Giambusso i
i 11791 8303030239 741113 PDR ADOCK 05000219 S
PDR COPY SENT REGION '
-2


Initial is!       . an.-                             1.te of
Initial is!
      .! U. g r t * . u ;             J :' " '               Cecut rc:..:e : O      11/12< >
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  * *T:#i t i n !   *:t'c?                                   Tim of Leport Date:                 11/1 ' J                 Cecurrence:             1106             ,
1.te of O
0YSTEr. Cil fS !ICLF'n CE'T. RATING STATION FOR!:ED 1:I'.TT,, ':EN JERSEY OS731 AlnOTF'.1 CC0urrCnce Report No. S0-219/74/ 59 IDENTIFICATION           Trip of Diesel Cencrator d2 during surveillance testing.
.! U. g r t *. u ;
J :' " '
Cecut rc:..:e :
11/12< >
* *T:#i t i n !
*:t'c?
Tim of Leport Date:
11/1 ' J Cecurrence:
1106 0YSTEr. Cil fS !ICLF'n CE'T. RATING STATION FOR!:ED 1:I'.TT,, ':EN JERSEY OS731 AlnOTF'.1 CC0urrCnce Report No. S0-219/74/ 59 IDENTIFICATION Trip of Diesel Cencrator d2 during surveillance testing.
OF OCCURRENCE:
OF OCCURRENCE:
This event is considered to be an abnormal occurrence as de-fined in the Technical Specifications, paragraph 1.15D.
This event is considered to be an abnormal occurrence as de-fined in the Technical Specifications, paragraph 1.15D.
CONDITIONS PRIOR                 Steady State Power                     Routine Shutdown TO OCCURRENCE:                   !!ot Standi;y                         Operation Cold Shutde::n                         Load Changes During Refueling Shutdown                     Routine Power Operation Routine Startup                   x   Other (Specify)
CONDITIONS PRIOR Steady State Power Routine Shutdown TO OCCURRENCE:
!!ot Standi;y Operation Cold Shutde::n Load Changes During Refueling Shutdown Routine Power Operation Routine Startup x
Other (Specify)
Operation The reactor was shutdown with coolant temperature <212*F.
Operation The reactor was shutdown with coolant temperature <212*F.
DESCRIPTION               At approximately 105S on November 12, 1974, a routine, bi-0F OCCURRENCE:
DESCRIPTION At approximately 105S on November 12, 1974, a routine, bi-0F OCCURRENCE:
weekly 20% load test of the #2 diesel generator was begun, as required by Technical Specification paragraph 4.7. A.1.
weekly 20% load test of the #2 diesel generator was begun, as required by Technical Specification paragraph 4.7. A.1.
At 1106, with the #2 diesel generator loaded to 2000 KW, the unit troubic alarm was received in the. station control room and a normal shutdown sequence was automatically initiated.
At 1106, with the #2 diesel generator loaded to 2000 KW, the unit troubic alarm was received in the. station control room and a normal shutdown sequence was automatically initiated.
Investigation by the operator stationed at the diesel generator revealed that the trouble _ alarm and shutdown were caused by excessive cooling water temperature (200*F) . This high temp-erature condition, in turn, was caused by a failure of the shutters (radiator louvers) to open and admit cooling air as the engine warmed up.
Investigation by the operator stationed at the diesel generator revealed that the trouble _ alarm and shutdown were caused by excessive cooling water temperature (200*F). This high temp-erature condition, in turn, was caused by a failure of the shutters (radiator louvers) to open and admit cooling air as the engine warmed up.
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      !.f r! ";F ' C' J3;i         Pesirn                             Procedure CFLT<         .;E :         "c:a . c:cture                     Unusual Service Ccnditi<n Ins t.,11atien/                   Inc. Envirennental Construction                       Component Failure Operator                     x   Other (Specify)
: p ij t c. *:s. : -::.i~'! O Page :
The cause of failure of the shutters to open is currently under investigaticn.     The louver control temperature switch will be renoved and tested to determine if it failed.
.s..
ANALYSIS OF           Appendix L to the FDSAR contains a probability analysis regard-OCCURRENCE:
!.f r! ";F ' C' J3;i Pesirn Procedure CFLT<
ing the availability of standby cooling systems and includes an analysis of off-site power availability concurrent with a loss of coolant accident. The results indicated that the reliability of available power from off-site sources or from a self-contained unit - only one (1) diesel generator was considered in the analysis - was quite high. Since the station is provided with two (2) separate diesel generator units, having one (1) unit out of service has no effect at all upon the results of the analysis.     In addition, the effects of- single bus operation during a loss of coolant accident was analyzed in Amendment 32
.;E :
;                            to the FDSAR and the unit loading under this condition was found to be within the normal KVA rating of the diesel generator.
"c:a. c:cture Unusual Service Ccnditi<n Ins t.,11atien/
Inc. Envirennental Construction Component Failure Operator x
Other (Specify)
The cause of failure of the shutters to open is currently under investigaticn.
The louver control temperature switch will be renoved and tested to determine if it failed.
ANALYSIS OF Appendix L to the FDSAR contains a probability analysis regard-OCCURRENCE:
ing the availability of standby cooling systems and includes an analysis of off-site power availability concurrent with a loss of coolant accident. The results indicated that the reliability of available power from off-site sources or from a self-contained unit - only one (1) diesel generator was considered in the analysis - was quite high. Since the station is provided with two (2) separate diesel generator units, having one (1) unit out of service has no effect at all upon the results of the analysis.
In addition, the effects of-single bus operation during a loss of coolant accident was analyzed in Amendment 32 to the FDSAR and the unit loading under this condition was found to be within the normal KVA rating of the diesel generator.
Thus, there is no additional safety significance associated with this event beyond that already analyzed.
Thus, there is no additional safety significance associated with this event beyond that already analyzed.
CORRECTIVE             Corrective action will be based upon the findings of the ACTION:
CORRECTIVE Corrective action will be based upon the findings of the ACTION:
investigation.
investigation.
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l'AI Li::'. I .i . .i :                 ' t availchle 1:::til cer.pletion of investigation.
' t availchle 1:::til cer.pletion of investigation.
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Prepared by:                   -forfj At Dcd *         ,A .
Prepared by:
Date: 11/12/74
-forfj At Dcd *,A.
____      ~     _ . . , . . _ , .      _. _ _ . _ - _ - _ _ _ - . _ - . . _ - -}}
Date:
11/12/74
~
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Latest revision as of 13:24, 13 December 2024

Preliminary AO-50-219/74-59:on 741112,during Load Test, Diesel Generator 2 Trouble Alarm Received.Cause Under Investigation
ML20090D852
Person / Time
Site: Oyster Creek
Issue date: 11/13/1974
From: Carroll J
JERSEY CENTRAL POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
AO-50-219-74-59, NUDOCS 8303030259
Download: ML20090D852 (4)
v • d • e


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To:

Jates P. O'Reilly QZl

-(N,, '

Directorate "of Regulatory Operations

- +

Regien I 631 Park Avenue King of Prussia, Fennsylvania 19406 From:

Jersey Central Power 6 Light Company Oyster Creek Nuclear Generating Stati6n Docket #50-219 Forked River, New Jersey 08731

Subject:

Abnormal Occurrence Report No. 50-219/74/59 4

'Ihe following is a preliminary report being submitte'd in compliance with the Technical Specifications, paragraph 6.6.2.

Preliminary Approval:

/

}_

./

/ ccats, M 11/13/74 J.T.Carrol1[Ir.

Date cc:

Mr. A. Giambusso i

i 11791 8303030239 741113 PDR ADOCK 05000219 S

PDR COPY SENT REGION '

-2

Initial is!

. an.-

1.te of O

.! U. g r t *. u ;

J :' " '

Cecut rc:..:e :

11/12< >

  • *T:#i t i n !
  • t'c?

Tim of Leport Date:

11/1 ' J Cecurrence:

1106 0YSTEr. Cil fS !ICLF'n CE'T. RATING STATION FOR!:ED 1:I'.TT,, ':EN JERSEY OS731 AlnOTF'.1 CC0urrCnce Report No. S0-219/74/ 59 IDENTIFICATION Trip of Diesel Cencrator d2 during surveillance testing.

OF OCCURRENCE:

This event is considered to be an abnormal occurrence as de-fined in the Technical Specifications, paragraph 1.15D.

CONDITIONS PRIOR Steady State Power Routine Shutdown TO OCCURRENCE:

!!ot Standi;y Operation Cold Shutde::n Load Changes During Refueling Shutdown Routine Power Operation Routine Startup x

Other (Specify)

Operation The reactor was shutdown with coolant temperature <212*F.

DESCRIPTION At approximately 105S on November 12, 1974, a routine, bi-0F OCCURRENCE:

weekly 20% load test of the #2 diesel generator was begun, as required by Technical Specification paragraph 4.7. A.1.

At 1106, with the #2 diesel generator loaded to 2000 KW, the unit troubic alarm was received in the. station control room and a normal shutdown sequence was automatically initiated.

Investigation by the operator stationed at the diesel generator revealed that the trouble _ alarm and shutdown were caused by excessive cooling water temperature (200*F). This high temp-erature condition, in turn, was caused by a failure of the shutters (radiator louvers) to open and admit cooling air as the engine warmed up.

a' N

lb,~

Ce:u:

p ij t c. *:s. : -::.i~'! O Page :

.s..

!.f r! ";F ' C' J3;i Pesirn Procedure CFLT<

.;E :

"c:a. c:cture Unusual Service Ccnditi<n Ins t.,11atien/

Inc. Envirennental Construction Component Failure Operator x

Other (Specify)

The cause of failure of the shutters to open is currently under investigaticn.

The louver control temperature switch will be renoved and tested to determine if it failed.

ANALYSIS OF Appendix L to the FDSAR contains a probability analysis regard-OCCURRENCE:

ing the availability of standby cooling systems and includes an analysis of off-site power availability concurrent with a loss of coolant accident. The results indicated that the reliability of available power from off-site sources or from a self-contained unit - only one (1) diesel generator was considered in the analysis - was quite high. Since the station is provided with two (2) separate diesel generator units, having one (1) unit out of service has no effect at all upon the results of the analysis.

In addition, the effects of-single bus operation during a loss of coolant accident was analyzed in Amendment 32 to the FDSAR and the unit loading under this condition was found to be within the normal KVA rating of the diesel generator.

Thus, there is no additional safety significance associated with this event beyond that already analyzed.

CORRECTIVE Corrective action will be based upon the findings of the ACTION:

investigation.

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Page._>

<g,

' t availchle 1:::til cer.pletion of investigation.

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Prepared by:

-forfj At Dcd *,A.

Date:

11/12/74

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