W3P84-1737, Responds to Generic Ltr 83-28,Items 4.2.3 & 4.2 4 Re Life Cycle Testing & Periodic Replacement Requirements for Reactor Trip Breakers.Util Will Provide Program & Schedule to Complete Section Requirements by 841130: Difference between revisions

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I OUISIANA           142 DELARONOE STREET POWER & LIGHT       R o. aox 6008 . NEW OALEANS. LOUIStANA 70174 . (504) 366-2345 EuS$sysSIM June 22, 1984                         W3P84-1737 3-A1.01.04 Q-3-A20.02.02 L.02 Director of Nuclear Reactor Regulation Attention: Mr. G.W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
I OUISIANA 142 DELARONOE STREET POWER & LIGHT R o. aox 6008. NEW OALEANS. LOUIStANA 70174. (504) 366-2345 EuS$sysSIM June 22, 1984 W3P84-1737 3-A1.01.04 Q-3-A20.02.02 L.02 Director of Nuclear Reactor Regulation Attention:
Mr. G.W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555


==SUBJECT:==
==SUBJECT:==
Line 26: Line 27:


==Dear Sir:==
==Dear Sir:==
 
Sections 4.2.3 and 4.2.4 of Generic Letter 83-28 cover life cycle testing and periodic replacement requirements for reactor trip breakers.
Sections 4.2.3 and 4.2.4 of Generic Letter 83-28 cover life cycle testing and periodic replacement requirements for reactor trip breakers.                 In the referenced letter LP&L indicated that the CE Owners Group (CEOG) was developing a program to address these requirements, among others.
In the referenced letter LP&L indicated that the CE Owners Group (CEOG) was developing a program to address these requirements, among others.
The CEOG program currently in place is investigating various options for breaker replacement or enhancement of existing breakers to improve reliability. This program will be discussed with the NRC in a meeting presently scheduled for June 27, 1984.
The CEOG program currently in place is investigating various options for breaker replacement or enhancement of existing breakers to improve reliability. This program will be discussed with the NRC in a meeting presently scheduled for June 27, 1984.
Because the final breaker model and/or design is indeterminate at this point, it is inappropriate to address life cycle teating. LP&L will provide, by November 30, 1984, a program and schedule to complete the Section 4.2.3 and 4.2.4 requirements of Generic Letter 83-28.
Because the final breaker model and/or design is indeterminate at this point, it is inappropriate to address life cycle teating. LP&L will provide, by November 30, 1984, a program and schedule to complete the Section 4.2.3 and 4.2.4 requirements of Generic Letter 83-28.
                  ~
~
Should you have any questions or comments on this matter please contact Mike Meisner at (504) 363-8938.
Should you have any questions or comments on this matter please contact Mike Meisner at (504) 363-8938.
Yours very truly, wM K.W. Cook Nuclear Support & Licensing Manager KWC/MJM/pco cc: E.L. Blake, W.M. Stevenson, J.T. Collins, D.M. Crutchfield,                         g J. Wilson, G.L. Constable, T. Alexion (NRC)                                         glP to 8406280102 840622 PDR ADOcK 05000 A}}
Yours very truly, wM K.W. Cook Nuclear Support & Licensing Manager KWC/MJM/pco cc:
E.L. Blake, W.M. Stevenson, J.T. Collins, D.M. Crutchfield, g
J. Wilson, G.L. Constable, T. Alexion (NRC) glP to 8406280102 840622 PDR ADOcK 05000 A}}

Latest revision as of 11:06, 13 December 2024

Responds to Generic Ltr 83-28,Items 4.2.3 & 4.2 4 Re Life Cycle Testing & Periodic Replacement Requirements for Reactor Trip Breakers.Util Will Provide Program & Schedule to Complete Section Requirements by 841130
ML20092K182
Person / Time
Site: Waterford 
Issue date: 06/22/1984
From: Cook K
LOUISIANA POWER & LIGHT CO.
To: Knighton G
Office of Nuclear Reactor Regulation
References
GL-83-28, W3P84-1737, NUDOCS 8406280102
Download: ML20092K182 (1)
v • d • e


Text

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I OUISIANA 142 DELARONOE STREET POWER & LIGHT R o. aox 6008. NEW OALEANS. LOUIStANA 70174. (504) 366-2345 EuS$sysSIM June 22, 1984 W3P84-1737 3-A1.01.04 Q-3-A20.02.02 L.02 Director of Nuclear Reactor Regulation Attention:

Mr. G.W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

Waterford SES Unit 3 Docket No. 50-382 Generic Letter.83-28, Items 4.2.3 and 4.2.4

REFERENCE:

W3P84-0609 dated March 8, 1084

Dear Sir:

Sections 4.2.3 and 4.2.4 of Generic Letter 83-28 cover life cycle testing and periodic replacement requirements for reactor trip breakers.

In the referenced letter LP&L indicated that the CE Owners Group (CEOG) was developing a program to address these requirements, among others.

The CEOG program currently in place is investigating various options for breaker replacement or enhancement of existing breakers to improve reliability. This program will be discussed with the NRC in a meeting presently scheduled for June 27, 1984.

Because the final breaker model and/or design is indeterminate at this point, it is inappropriate to address life cycle teating. LP&L will provide, by November 30, 1984, a program and schedule to complete the Section 4.2.3 and 4.2.4 requirements of Generic Letter 83-28.

~

Should you have any questions or comments on this matter please contact Mike Meisner at (504) 363-8938.

Yours very truly, wM K.W. Cook Nuclear Support & Licensing Manager KWC/MJM/pco cc:

E.L. Blake, W.M. Stevenson, J.T. Collins, D.M. Crutchfield, g

J. Wilson, G.L. Constable, T. Alexion (NRC) glP to 8406280102 840622 PDR ADOcK 05000 A

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