ML20076E700

Proposed Change 107 Revising Tech Spec Figure 3.6.1 Re Reactor Vessel Pressure Temp Limitations for Operation Through 1.330E8 Mwh(T)

ML20076E700
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	05/26/1983
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20076E697	List: ML20076E695 ML20076E700
References
NUDOCS 8306010248
Download: ML20076E700 (3)

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8306010248 830526 PDR ADOCK 05000271 PDR p

r 4

VYNPS hases i

3.6 & 4.6 REACTOR COOLANT SYSTEM A. Pressure and Temperature Limitations t

i All components in the Reactor Coolant System are designed to withstand the ef fects of cyclic loads due to system temperature and pressure changes. These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations. The various categories of load cycles used for design purposes are provided in i Section 4.2 of the FSAR. During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximun specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

During heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from compressive at t t.e inner wall to tensile at the outer wall. These thermal induced compressive stresses tend to z

alleviate the tensile stresses induced by the internal pressure. Therefore, a pressure-temperature curve based on steady state conditions (i.e. , no thermal stresses) represents a lower bound of all similar curves f or finite heatup rates when t he inner wall of the vessel is treated as the governing locations.

1 1

The heatup analysis also covers the determination of pressure-temperature limitations for the case in which the l

outer wall of the vessel becomes the controlling location. The thermal gradients established during heatup produce tensile stresses at the outer wall of the vessel. These stresses are additive to the pressure induced tensile st resses which are already present. The thermal induced stresses at the outer wall of the vessel are tensile and are de;:endent on both the rate of heatup and the time along the heatup ramp; therefore, a lower bound curve similar to that described for the heatup of the inner wall cannot be defined. Subsequently, for the cases 4

in which the outer wall of the vessel becomes the stress controlling location, each heatup rate of interest must be analyzed on an individual basis.

In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures should be within 500F ot each other prior to startup of an idle loop.

The reactor vessel materials have been tested to determine their initial nil-ductility transition temperature maximum. An additional margin of 200F has been added in order to estimate reference i

0

(NDTT) of 40 F temperature, RThDT. Reactor operation and resultant f ast neutron (E ?>l Mev) irradiation will cause an increase in the RTNDT. Therefore, an adjusted reference temperature can be predicted using current industry practices (GE SIL No. 14, Supplement No. 1) based on recent GE surveillance data. The pressure / temperature 8limit curve, MWH(t),

l Figure 3.6.1, includes predicted adjustments for this shif t in RTNDT for operation through 1.330x10 j as well as adjustments f or possible errors in the pressure and temperature sensing instruments.

117 l

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