ML20134M347

Clarification of Proposed Rev to Tech Spec 3.13.C(1) Re Refueling,Ensuring That Assumptions & Initial Conditions of Reactor Cavity Seal Failure Safety Analysis Met.Fuel Assembly Return Location Clarified as Reactor Core

ML20134M347
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/31/1985
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20134M345	List: B11656, Forwards Clarification of Proposed Rev to Tech Spec 3.13.C(1) Re Refueling Submitted w/850510 Ltr.Revised Page Clarifies That Fuel Returns to Reactor Core,Not Literally to Bottom of Reactor Pressure Vessel ML20134M347
References
NUDOCS 8509040094
Download: ML20134M347 (2)

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i Docket No. 50-213 4

ATTACHMENT 1 Clarification of Proposed Revision to Technical Specifications l

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850904U094 850028 PDR ADOCK 05000213 P

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August,1985 i -

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June 22, 1981 3.13 REFUELING Applicability:

Applies to operating limitations during refueling operations.

To insure that no incident could occur during refueling Objective :

operations that would affect public health and safety.

Specification:

A.

Radiation levels in the containment and fuel storage building shall be monitored continuously.

B.

Core subcritical neutron flux shall be continuously monitored by at least two neutron monitors, each with continuous visual and audible indication available, whenever core geometry is being changed. When core geometry is not being changed, at least one neutron flux monitor shall be in service.

C.

(1) Whenever the water level in th'e refueling cavity is less than 24 feet above the flange of the reactor l

pressure vessel, two residual heat removal loops shall be OPERABLE. With less than the required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.

Also, with less than the required depth of water described above, suspend all operations involving 37 movement of fuel assemblies or control rods within the reactor pressure vessel. This require =ent does not apoly if it becomes necessarv to return a fuel assembly to the reactor core in response to the applicable emergency procedure covering decreasing cavity level.

(2) At least one RHR pump and heat exchanger shall be in operation except that the residual heat removal syste= may be removed from operation for up to I hour per.8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during performance of core altera-tions in the vicinity of the reactor pressure vessel hot legs. With less than one residual heat removal pump and heat exchanger in operation except as described above, suspend all operation involving any increase in reactor decay heat load or a reduc-tion in baron concentrat'on of the reacter coolant system. Close all contain=ent penetrations providing direct access from the containment a.mcsphere to the outside at=osphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

i D.

During reac.cr vessel head removal and while leadin; and unloading fuel from the reactor, the boron concentration shall be maintained at not less than that required to shut down the core to a k,ff - 0.92 (see Specification 3.11).

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