ML20204H272

Proposed Tech Spec Changes,Modifying Item 21 Action Notation & Changing Item 22 Applicable Modes & Action Notation on Table 3.3-1 Re Reactor Trip Breakers

ML20204H272
Person / Time
Site:	Farley
Issue date:	08/01/1986
From:	ALABAMA POWER CO.
To:
Shared Package
ML20204H265	List: ML20204H262 ML20204H272
References
TAC-55354, TAC-55355, NUDOCS 8608080068
Download: ML20204H272 (5)

Text

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ATTACHMENT 1 i

Proposed Changes to Reactor Trip Breaker

, Technical Specifications Unit 1 Revision 4

Page 3/4 3-5 Replace Unit 2 Revision Page 3/4 3-5 Replace d

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g TABLE 3.3-1 (Continued)  :

REACTOR TRIP SYSTEM INSTRUMENTATION i

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"" MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

21. Reactor Trip Breakers 2 1 2 1, 2 1, 14 3*,4*,5* 13

22. Automatic Trip Logic 2 1 2 1, 2 1 3*,4*,5* 13 w

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I gg TABLE 3.3-1 (Continued)  :

REACTOR TRIP SYSTEM INSTRUMENTATION I

-e b) MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

21. Reactor Trip Breakers 2 1 2 1, 2 1, 14 3*,4*,5* 13

22. . Automatic Trip Logic 2 1 2 1, 2 1 3*,4*,5* 13 R.

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ATTACHMENT 2 Significant Hazards Evaluation Pursuant To 10CFR50.92 for the Proposed Changes to the Reactor Trip and Bypass Breaker Technical Specifications in Response to Generic Letter 85-09 Proposed Changes Add Applicable Modes and Action Statements to Table 3.3-1, Items 1, 21 and 22; add Applicable Modes and Table Notation to Table 4.3-1, Items 1, 21 and 22; and add Item 23 to Table 4.3-1 for the Reactor Trip Bypass Breakers.

Background

Item 4.3 of Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events," established the requirement for the automatic actuation of the shunt trip attachment for Westinghouse plants and requested licensees to submit any needed Technical Specification changes.

Westinghouse developed generic design modifications for reactor trip system automatic actuation using shunt coil trip attachments. The major aspects of the Westinghouse generic design for Type DS-416 breakers are applicable to the Farley Nuclear Plant breaker modifications and have been implemented. Since some licensees had responded to Generic Letter 83-28 and had indicated that no technical specification changes were required, the NRC issued Generic Letter 85-09 to request licensees to submit proposed technical specification changes, to provide proposed changes to the Westinghouse Standard Technical Specifications (STS), and to provide guidance for licensees to use in developing their Technical Speci fications. Alabama Power Company therefore proposes changes to the reactor trip breaker technical specifications and the addition of the reactor trip bypass breaker technical specifications for the Farley Nuclear Plant Unit 1 and 2 Technical Specifications in response to Generic Letter 85-09.

Analysis Alabama Power Company has reviewed the requirements of 10CFR50.92 as they relate to the proposed reactor trip and bypass breaker technical specification changes and considers the proposed changes not to involve a significant hazards consideration. In support of this conclusion, the following analysis is provided:

1) The proposed changes will not increase the probability or consequences of an accident previously evaluated because the addition of reactor trip bypass breaker surveillance requirements will provide added assurance that diverse means of effecting a reactor trip exist and will enhance the capability to shutdown the reactor upon demand. Therefore, the probability or consequences of an accident previously evaluated have not been increased.

Attachment 2 Page 2

2) The proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes ensure that a common mode failure will not exist and the reactor will be shutdown when required. Since the ability to shutdown the reactor has been previously analyzed, these proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

3) The proposed changes will not involve a significant reduction in a margin of safety because the proposed changes enhance the ability to shutdown the reactor and therefore enhance the margin of safety associated with a reactor shutdown. The proposed changes conform to NRC accepted practice and therefore do not significantly reduce a margin of safety.

Conclusion Based upon the analysis provided herewith, Alabama Power Company considers the proposed changes to the technical specifications to not involve a significant hazards consideration as defined by 10CFR50.92(c).

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