ML20196H528

Forwards LAR 279 to License DPR-50,reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG

ML20196H528
Person / Time
Site:	Three Mile Island
Issue date:	12/03/1998
From:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20196H532	List: ML20196H528 ML20196H536 ML20196H975
References
1920-98-20669, NUDOCS 9812090095
Download: ML20196H528 (2)

Text

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i l GPU Nuclear. inc.

( Route 441 South +

NUCLEAR Post 0ffice Box 480 Middletown. PA 17057-0480 l Tel 717M7621 l December 03, 1998 ,

1920-98-20669 l

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i U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 l

Gentlemen:  !

Subject:

Three Mile Island Nuclear Station, Unit I (TM1-1)

Operating License No. DPR-50  ;

Docket No. 50-289 Technical Specification Change Request No. 279 - Core Protection Safety Limit l

In accordance with 10CFR50.4 (b)(1), enclosed is Technical Specification Change Request ,

(TSCR) No. 279. l The purpose of this TSCR is to revise the TMI-l Technical Specification Core Protection Safety Limit Figure 2.1-1 and Core Protection Safety . Bases Figure 2.1-3 to reflect the decrease in reactor coolant system flow resulting from a revised analysis to allow operation of TMI-I with 20 percent average level of steam generator tubes plugged per steam generator.

3 Using the standards in 10CFR 50.92, GPU Nuclear has concluded that these proposed changes do l not constitute a significant hazards consideration, as described in the enclosed analysis performed j in accordance with 10 CFR 50.91 (a)(1). Also enclosed is the Certificate of Service for this i request certifying service to the chief executives of the township and county in which the facility is {

located, as well as the designated official of the Commonwealth of Pennsylvania, Bureau of i Radiation Protection.

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_ l I- 9812090095 981203 l PDR ADOCK 05000289 j PDR p _

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• - 1940-98-20669

'- l Page 2 If any additional information is needed, please contact Mr. David J. Distel, Corporate Regulatory l

Affairs, at (973) 316-7955. '

Sincerely, 41Id/ Nd&

l. ames W. Lange a :h Vice President a irector, TM1 i

DJD I 1

Enclosures:

(1) TMI-l TSCR No. 279, Safety Evaluation, No Significant Hazards Consideration, Technical Specification Revised Pages (2) Certificate of Service for TMI-l TSCR No. 279 cc: Administrator, Region I TM1 Senior Resident Inspector TMI-1 Senior Project Manager File No. 98195 i

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