ML20203D212

Proposed Tech Specs Deleting Max Fuel Rod U Weight Limit of 1,766 G

ML20203D212
Person / Time
Site:	Farley
Issue date:	04/18/1986
From:	ALABAMA POWER CO.
To:
Shared Package
ML20203D210	List: ML20203D206 ML20203D212
References
TAC-61266, NUDOCS 8604220060
Download: ML20203D212 (5)

Text

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ATTACHMENT 1 1

Proposed Changed Pages Unit 2 Revision Page 5-6 Replace l

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l 8604220060 860418 PLR ADCCK 05000364 P PDR

i DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy -4. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment of 3.2 weight percent U-E35.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.3 weight percent U-235.

CONTROL R0D ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length and no part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be ruintained:

a. In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation

. pursuant to the appiicable Surveillance Requirements,

b. For a pressure of 2485 psig, and

c. For a temperature of 650*F, except for the pressurizer which-is 680'F.

VOLUME 5.4.2 The total water and steam volume af the reactor coolant system is 9723 + 100 cubic feet at a nominal T avg of 525'F.

5.E METEOROLOGICAL TOWER LOC'ATION 5.5.1 The reteorological tower shall be located as shown on Figure 5.1-1.

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I ATTACHMENT 2 i-Significant Hazards Evaluation Pursuant to 10 CFR 50.92 i for the Proposed Design Features Section of the

! Technical Specifications l

l Proposed Change .

1 The proposed change to Design Features Section 5.3.1 of the Technical Specification deletes the maximum fuel rod uranium weight limit of 1,766 grams. The purpose of the change is to permit the use of fuel  ;

assemblies with fuel rod uranium weights over the limit and also to '

reflect the relative insensitivity of the safety analyses to this l

parameter.

Background

The proposed change of Technical Specification Design Features Section 5.3.1 is the only reference to fuel rod uranium weight in the Technical Speci fi cati ons. The amount that the maximum rod weight in an assembly  ;

exceeds the limit is approximately 1 percent. i i.

The deletion of this maximum uranium weight has no safety significance  ;

in that the actual uranium weight has no bearing on the power limits, -

power operating level, or decay heat rate. Although a number of areas in the safety analyses are indirectly affected by fuel uranium weight, ,

the areas of safety significance have their own limits which are reflected in the safety analysis report and plant Technical

Specifications. Technical Specification limits on power and power ,

distribution control the fission rate and, hence, the rate of decay heat

p roduction. The composition of the fuel is very closely monitored to 4 l assure acceptable fuel performance for such things as thermal conductivity, swelling, densification, etc. The important fuel i l parameters have been considered and are addressed in the Reload Safety Evaluation process.

l Other Design Basis Events were examined to assess the ef fects of possible changes in fuel rod uranium weight. Fuel rod uranium weight will only change as result of a specific change in the physical design, which is addressed in the Reload Safety Evaluation, or within the manufacturing tolerances, in which case the changes in fuel rod uranium weight are relatively insignificant and are accounted for in the safety analyses. Changes in nuclear design resulting f rom fuel rod uranium weight changes are controlled as discussed at ve. For these changes,  ;

the effect on new and spent fuel criticality and fuel handling analyses

• remain bounded by the existing analyses and Technical Specification  ;

Design Feature limits. Fuel-handling equipment and procedures are nnt l af fected by these weight changes. Seismic /LOCA analyses contain l l sufficient conservatism to bound these weight changes. Other accident i analyses are not affected by fuel rod uranium weight as a direct (

parameter, and the existing analyses remain bounding.

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ATTACHMENT 2 Page 2 Analysis Alabama Power Company has reviewed the requirements of 10CFR50.92 as they relate to the proposed change to Design Features Section 5.3.1 and considers the proposed change to not involve a significant hazards consideration. In support of this conclusion the following analysis is provided:

1. The proposed change will not significantly increase the probability or consequences of an accident previously evaluated because variation in fuel rod uranium weight that can occur even without a Technical Specification limit is small based on other fuel design constraints, e.g., rod diameter, gap size, UOg density and active fuel length. All of these provide some limit on the variation in fuel rod uranium weight. The current safety analyses are not based directly on fuel rod uranium weight, but rather on design parameters such as power and fuel dimensions. These parameters are either not affected at all by fuel rod uranium weight, or are only slightly affected. However, a review of design parameters which may be affected indicates that a change in fuel weight does not cause other design parameters to exceed the values assumed in the various safety analyses, or to cause acceptance criteria to be exceeded. The ef fects are not significant with respect to measured nuclear parameters (power, power distribution, nuclear coefficients),

i.e., they remain within their Technical Specification limits. Thus the proposed change is deemed not to involve a significant increase in the probability or consequences of a previously evaluated accident.

2. The proposed change will not create the possibility of a new or diff erent kind of accident f rom any accident previously evaluated. All of the fuel contained in the fuel rod is similar to and designed to function similar to previous fuel.

Thus the creation of a new, different kind of accident f rom any previously evaluaced accident is not considered a possi bili ty.

3. The proposed change will not involve a reductior. in a mrgin of safety because the margin of safety is maintained by adherence to other fuel related Technical Specification limits and the FSAR design bases. The deletion of fuel rod uranium weight limits in Technical Specifications Design Features Section 5.3.1 does not directly affect any safety system or the safety limits and therefore does not affect the plant margin to safety.

ATTACHMENT 2 Page 3 Conclusion Based on the analysis provided herewith, Alabama Power Company has determined that the proposed Technical Specification change will not significantly increase the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. Theref ore, Alabara Power Company has determined that the proposed change meets the requirenents of 10CFR50.92 and does not involve a significant hazards consideration.