ML20083R663: Difference between revisions

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irr,Lsd[f 2 @ 4 kving Mece, New York, N Y 10003 February 19, 1974
irr,Lsd[f 2 @ 4 kving Mece, New York, N Y 10003 February 19, 1974
                                ' l'
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                                -                Re:   Indian Point Unit No. 2 AEC Doc;h e t iha . 50-247 Operat.ing License DPR-2f, A.O.-4-2 8               .
Indian Point Unit No. 2 AEC Doc;h e t iha. 50-247 Operat.ing License DPR-2f, A.O.-4-2 8 Mr James P.
Mr   James P. O'Reilly, Director Regulatory Operations, Region I U. S, Atomic Energy Commienion t,31 Park Avenue King of Prussia, Pennsylvania           19406 Dear Mr. O'Reilly; In accorde.nce With the requirements of section 6.12.2a of the Technical Spoo.ifications of Facility Operating License No.
O'Reilly, Director Regulatory Operations, Region I U. S, Atomic Energy Commienion t,31 Park Avenue King of Prussia, Pennsylvania 19406 Dear Mr. O'Reilly; In accorde.nce With the requirements of section 6.12.2a of the Technical Spoo.ifications of Facility Operating License No.
DPR-26, the fol10 wing report is submitted.
DPR-26, the fol10 wing report is submitted.
Periodic survei13ance test PT-M2, " Reactor Coolant Temperature hhalog Channel Functional Tee,b -L\T Overtemperature and T QVer-power", was performed on Februnry 13/16, 1974 with Unit No. 2                                   .
Periodic survei13ance test PT-M2, " Reactor Coolant Temperature hhalog Channel Functional Tee,b -L\\T Overtemperature and T QVer-power", was performed on Februnry 13/16, 1974 with Unit No. 2 in the cold shut.down condition.
in the cold shut.down condition.         The limiting safety systen set-                   e: j t.$ nga of Cha nnhl.a. 11 and IV of the Dvertemperature AT Re&otor                         ?.9 ;
The limiting safety systen set-e: j t.$ nga of Cha nnhl.a. 11 and IV of the Dvertemperature AT Re&otor
Trip circuitry were found to be be10e thht h9 quired by Technical                           ).j:[ .?
?.9 ;
Specification 2.3.).B (4). Channal.; 1 and 111 were f ound to be                               ;
Trip circuitry were found to be be10e thht h9 quired by Technical
Operhting om rently. Channele 11 and IV were recalibrated and                             'QiQ('l tested satisfactorily,                                                                     f Se*
).j:[.?
' Q('l Specification 2.3.).B (4).
Channal.; 1 and 111 were f ound to be Qi Operhting om rently.
Channele 11 and IV were recalibrated and tested satisfactorily, f Se*
Q :-
Q :-
Safety Jwp).iostione of thie discrepancy are considered rJ ight                             "d 9 sinon the reactor was in a cold shutdown condition and the re-                             yC maining' trip circuits would have provided complete reactor pro-                           fii41s tection ogninnt an excecnive flux tilt even if this had not boon                           ,.; M the eace. The maximum error f ound would havn rnaulted in the ac-                       1 -k tual reactor 4T exceeding the limit by 0.30 0 P in achieving an                           U '. f overtomparatt,arnA T trip for channele 11 cud IV.                                         hC kN in an effort. to data.rmine the cause of these deviationr, and pre-viously repor Wd onee of a similar natore, our investigation into this matter as discussed in our letter to Mr. John F,               O ' 7..- a r y dated January 25, 1974 is continuing.
Safety Jwp).iostione of thie discrepancy are considered rJ ight "d 9 sinon the reactor was in a cold shutdown condition and the re-yC maining' trip circuits would have provided complete reactor pro-fii41s
k     ,
,. M tection ogninnt an excecnive flux tilt even if this had not boon the eace.
3 8304040603 740219                                   L\       ,;!
The maximum error f ound would havn rnaulted in the ac-1 -k 0.30 P in achieving an U '. f 0
PDR ADOCK 05000                                       g
tual reactor 4T exceeding the limit by overtomparatt,arnA T trip for channele 11 cud IV.
              =                                                       ,
hC kN in an effort. to data.rmine the cause of these deviationr, and pre-viously repor Wd onee of a similar natore, our investigation into this matter as discussed in our letter to Mr. John F, O ' 7..- a r y dated January 25, 1974 is continuing.
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AEC Docket. No. 50-247
AEC Docket. No. 50-247
_ -                                        . Operating LicenSt) DPP.-26 A,0.-4-2-8                                     ;
. Operating LicenSt) DPP.-26 A,0.-4-2-8
                                                                                                              =
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=T Mr. Anthony Pasano of your office was notified of this occur-
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,2 rence by Mr, Jchri Mahepeace by t.elephone on February 16, 1974,
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Warren R. Cohean, Jr.,dinnager D-                ,
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Latest revision as of 05:06, 14 December 2024

AO 4-2-8:on 740215,during Reactor Coolant Temp Channel Test, Limiting Safety Sys Setting Read Below Required Tech Spec for Channels II & Iv.Cause Under Investigation
ML20083R663
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 02/19/1974
From: Cobean W
CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20083R668 List:
References
AO-4-2-8, NUDOCS 8304040603
Download: ML20083R663 (2)
v • d • e


Text

'

N x

x

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)tetehw.rw-=. Conschdaied Edfron Company o' New York, Inc.

3,,,

irr,Lsd[f 2 @ 4 kving Mece, New York, N Y 10003 February 19, 1974

' l' Re:

Indian Point Unit No. 2 AEC Doc;h e t iha. 50-247 Operat.ing License DPR-2f, A.O.-4-2 8 Mr James P.

O'Reilly, Director Regulatory Operations, Region I U. S, Atomic Energy Commienion t,31 Park Avenue King of Prussia, Pennsylvania 19406 Dear Mr. O'Reilly; In accorde.nce With the requirements of section 6.12.2a of the Technical Spoo.ifications of Facility Operating License No.

DPR-26, the fol10 wing report is submitted.

Periodic survei13ance test PT-M2, " Reactor Coolant Temperature hhalog Channel Functional Tee,b -L\\T Overtemperature and T QVer-power", was performed on Februnry 13/16, 1974 with Unit No. 2 in the cold shut.down condition.

The limiting safety systen set-e: j t.$ nga of Cha nnhl.a. 11 and IV of the Dvertemperature AT Re&otor

?.9 ;

Trip circuitry were found to be be10e thht h9 quired by Technical

).j:[.?

' Q('l Specification 2.3.).B (4).

Channal.; 1 and 111 were f ound to be Qi Operhting om rently.

Channele 11 and IV were recalibrated and tested satisfactorily, f Se*

Q :-

Safety Jwp).iostione of thie discrepancy are considered rJ ight "d 9 sinon the reactor was in a cold shutdown condition and the re-yC maining' trip circuits would have provided complete reactor pro-fii41s

,. M tection ogninnt an excecnive flux tilt even if this had not boon the eace.

The maximum error f ound would havn rnaulted in the ac-1 -k 0.30 P in achieving an U '. f 0

tual reactor 4T exceeding the limit by overtomparatt,arnA T trip for channele 11 cud IV.

hC kN in an effort. to data.rmine the cause of these deviationr, and pre-viously repor Wd onee of a similar natore, our investigation into this matter as discussed in our letter to Mr. John F, O ' 7..- a r y dated January 25, 1974 is continuing.

k 3

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PDR ADOCK 05000 g

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L. L -

U d

ta..

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O'Reilly Febn dry 19, 1974

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x Est Indian Point Unit No. 2

~

AEC Docket. No. 50-247

. Operating LicenSt) DPP.-26 A,0.-4-2-8

=

=T Mr. Anthony Pasano of your office was notified of this occur-

,2 rence by Mr, Jchri Mahepeace by t.elephone on February 16, 1974,

}

Voly tru)y yours, 3

3

,s h,b.hha.p.. D -.

on(t.,,

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Ifuelear l'ower Generation 1

1 Mr.

ohn P. O' Luis.ry 1

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