ML20195E620

Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions

ML20195E620
Person / Time
Site:	Three Mile Island
Issue date:	06/04/1999
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20195E331	List: ML20195E328 ML20195E334 ML20195E620
References
NUDOCS 9906140025
Download: ML20195E620 (5)

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Enclosure 2

~ TMI-1 Technical Specifications Revised Pages i

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.99061'40025 990604 PDR ADOCK 05000289 4 9 PDR ,

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' 3.4.2.2. Operation of the means for decay heat removal may be suspended pro $ided the core outlet temperature is mairdained below saturation temperature.

3.4.2.3 The number of means for decay heat removal required to be operable per 3.4.2.1 may be reduced to one provided that the Reactor is in a Refueling Shutdown condition with the Fuel Transfer Canal water level greater than or equal to 23 feet above the reactor vessel flange.

3A2.4 Specification 3.4.2.1 does not apply when either of the following conditions exist:

a. Decay heat generation is less than 188 KW with the RCS full.

b. Decay heat generation is less than 100 KW with the RCS drained down for maintenance.

3.4.2.5 . With less than the above required loops OPERABLE, immediat'ely initiate corrective action to return the required loops to OPERABLE status as soon as possible.

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3-26a l

Amendment No. iii,123, i33, . l l

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n When the RCS is below 250oF, a single DHR stnng, or single OTSG and its associated emergency feedwater flqwpath capable of supporting natural circulation is sufficient to provide removal of decay heat at all times followmg the cooldown to 250oF. He Decay Heat Removal String redundancy required by TS 3.4.2.1 is actueved with independent active wrycrets capable ofmaintauung the RCS subcooled. A single DHR flow

- path with Madant active hym=6 is sufficient to meet the requirements of TS 3.4.2.1.a and 3.4.2.1.b.

He requirement to maintam two OPERABLE means of decay heat removal ensures that a single active failure does not result in a complete loss of decay heat remosal capability. The requirement to keep a system in operation as rhy to maintain the system subcooled at the core outlet provides the guidance to ensure l that steam conditions wluch could inhibit com cooling do not occur.

. With the reactor vessel head removed and 23 feet of water above the reactor vessel flange, a large heat sink is available for core cooling. In this condition, only one DHR loop is required to be Operable

. because the volume of water above the reactor vessel flange provides a large heat sink which would allow sufficient time to recover active decay heat removal means.

Following extensive outages or major core offloading, the decay heat generation being removed from the Reactor Vessel is so low that ambient losses are sufficient to maintain core cooling and no other means of heat removal is required. The system is passive and requires no redundant or diverse backup l system. Decay heat generation was calculated in accordance with ANSI 5.1 - 1979. l

- An unlimited emergency feedwater supply is available from the river via either of the two motor-driven reactor building emergency cooling water pumps for an indefinite period of time.

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The requirements of Technical Specification 3.4.1.1 assure that before the reactor is heated to above 250oF, adequate auxiliary feedwater capability is available. One turbine driven pump full capacity (920 gpm) and the two half-capacity motor-driven pumps (460 gpm each) are specified. However, only one half-capacity motor-driven pump is necessary to supply auxiliary feedwater flow to the steam generators in the onset of a small break loss-of-coolant accident.

- REFERENCES (1) UFSAR, Table 6.1 ECCS " Single Failure Analysis" l

'(2) . UFSAR,9.5 - Decay Heat Removal System 3-26c Amendment No. 78, !!9,125,133, ISE

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i Enclosure 3 '

Cenificate of Service for  !

TM1-1 Technical Specification Change Request No. 265 l

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION u' IN THE MATTER OF GPU NUCLEAR, Inc.

DOCKET NO. 50-289 LICENSE NO. DPR-50 CERTIFICATE OF SERVICE' This is to certify that a copy of Technical Specification Change Request No. 265 to Appendix

, A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderiy Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of

- Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:

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Mr. Darryl LeHew, Chairman Ms. Sally S. Klein, Chairman Board of Supervisors of Board ofCounty Commissioners I Londonderry Township of Dauphin County . I R.D. #1, Geyers Church Road Dauphin County Courthouse I Middletown, PA 17057 Harrisburg, PA 17120 3 Director, Bureau of Radiation Protection PA Department of Environmental Resources

- Rachel Carson State Office Building P.O. Box 8469 .

Harrisburg, PA 17105-8469 ATTN: Mr. Stan T. Maingi GPU NUCLEAR, Inc.

BY: sti M pe President and grector, TMI s

DATE: 6,/Y. .[. 99 l

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