ML18153C016

Proposed Tech Spec Re RCS

ML18153C016
Person / Time
Site:	Surry
Issue date:	12/11/1989
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18153C015	List: ML18153C014 ML18153C016
References
NUDOCS 8912200047
Download: ML18153C016 (3)

Text

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.. 0 TS 5.3-3

b. The moderator temperature coefficient in the power operating range is less than or equal to:

1) +3.0 pcm/0 f at less than 50% of rated power, or

2) +3.0 pcm/0 f at 50% of rated power and linearly decreasing to O pcm/0 f at rated power.

c. Capable of being made subcritical in accordance with Specification 3.12.A.3.C.

B. Reactor Coolant System

1. The design of the Reactor Coolant System complies with the code requirements specified in Section 4 of the fSAR.

2. All piping, components, and supporting structures of the Reactor Coolant System are designed to Class 1 seismic requirements, and have been designed to withstand:

a. Primary operating stresses combined with the Operational seismic stresses resulting from a horizontal ground acceleration of 0.07g and a simultaneous vertical ground acceleration of 2/3 the horizontal, with the stresses maintained within code allowable working stresses.

b. Primary operating stresses when combined with the Design Basis Earthquake seismic stresses resulting from a horizontal ground acceleration of 0.15g and a simultaneous vertical ground

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• e ATTACHMENT 2 Significant Hazards Consideration

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• SIGNIFICANT HAZARDS CONSIDERATION e

The proposed change to delete Technical Specification 5.3.A.7 is made to prevent original design information from being interpreted as a limiting condition. The proposed deletion is consistent with Standard Technical Specifications and the intent of Section 2.C of the Operating License. This action does not result in a significant hazards consideration as defined in 10 CFR 50.92.

1. The proposed change does not significantly increase the probability of occurrence or the consequences of an accident previously evaluated. The proposed change to the Technical Specifications only deletes a reference to the quantity of special nuclear material used as neutron flux detectors. The number of detectors, their operation, and the control of their associated special nuclear material remains unchanged. Thus the probability of occurrence of any accident previously evaluated remains unchanged. The total quantity of special nuclear material employed in neutron flux detectors is not considered in, and therefore has no effect on, any accident previously evaluated in the UFSAR. As previously stated, the number of detectors, their operation, and the control of their associated special nuclear material is not affected by the proposed change. Therefore, the consequences of any accident previously evaluated is unaffected.

2. The proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed change does not involve a physical change to the facility or its operating procedures. Also, the quantity of special nuclear material used in neutron flux detectors will remain at only those amounts as required and allowed by the Facility Operating Licenses. Thus, no possibility is created for any accident of a new or different kind.

3. The proposed change does not involve a significant reduction in a margin of safety. No accident analysis or limiting condition of operation assumes a specific quantity of special nuclear material is used in neutron flux detectors.

The number of detectors, their operation, and the control of their associated special nuclear material will not be affected. Accordingly, the safety function of any neutron flux detector will be unaffected by this change and no reduction in a margin of safety will result.