ML20127M405

Proposed Tech Specs Re Refueling Cavity Water Level

ML20127M405
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/10/1985
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20127M403	List: B11382, Application for Amend to License DPR-61,revising Tech Specs Re Refueling Cavity Water Level Per Safety Analysis of Cavity Water Level & Seal Redesign.Fee Paid ML20127M405
References
NUDOCS 8505230260
Download: ML20127M405 (2)

Text

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f June 22, 1981 9 3.13 REFUELING i Applicability: Applies to operating limitations during refueling operations.

Ojective: To insure that no incident could occur during refueling operations that would affect public health and safety.

~geci S fication' : A. Radiation levels in the containment and fuel. storage building shall be monitored continuously. ,

B. Core subcritical neutron flux shall be entinuously  !

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 the 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 retur1 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 movement of fuel assemblies or control rods within 37 the reactor pressure vessel. This requirement does not apply if it becomes necessary to return a fuel assembly to the bottom of the reactor nressure vessel 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 system may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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-tiuns 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 boron concentration of the reactor coolant system. Close all enntainment penetrations providing dirtet access from the containment atmosphere to the outside atmosphere wi, thin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

D. During reactor vessel head removal and while loading and unloading fuel from the reactor, the boron concentration l shall be maintained at not less than that required to shut down the core to a k,f 7 - 0.92 (see Specification 3.11).

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\ Jwater. boron concentration ensure the proper shutdown margin.

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Part G allows the control room operator to inform the 3manipular~ operator of any-impending unsafe condition detected ifrom:the main control board indicators during fuel movement.

The. requirement that-at least one1 residual heat. removal pumn L and heat exchanger be in operation ensures that (1) sufficient :

cooling capacity l is available to remove decay heat and main-tain the water in th'e reactor. pressure vessel below 140 F as1

, required'during1the. REFUELING MODE, and-(2), sufficient' coolant

, circulation is maintained _through the reactor core to minimize the effort'of a boron dilution incident and prevent boron 37 stratification.-

.The requirement to have two RHR pumps and heat exchangers operable when there is less than 24 feet of water above the l

reactor pressure vessel flange ensures that '(1) sufficient .

cooling capacity is available to remove decay heat and main-tain water in the reactor pressure vessel below 1400F as required during refueling mode and (2) sufficient coolant circulation is maintained through the reactor / core to minimize

'the'effect of a boron dilution incident and. prevent boron stratification. The Technical. Specification of'24' feet of water above the flange also ensures (3) -sufficient water depth -

for' operator actions in'the event of a cavity. seal failure and (4)~that. sufficient _' water depth is available to remove 99% of the assumed.10% iodine gap activity released from the rupture of an irradiated fuel assembly.

References:

. .(1) FDSA Section'5.2.9 (2) FDSA Section 7.4 1

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