ML20141E131

Application for Amend to License DPR-50,consisting of Change Request 264,incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits

ML20141E131
Person / Time
Site:	Three Mile Island
Issue date:	05/08/1997
From:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20141E135	List: ML20141E131 ML20141E149
References
6710-97-2139, NUDOCS 9705200342
Download: ML20141E131 (8)

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NUCLEAR h*yl;**,$",*,*og.osen Tel 717-944-7621 6710-97-2139 May 08,1997 1

l U. S. Nuclear Regulatory Commission  ;

Attention: Document Control Desk  !

Washington, DC 20555

Dear Sir:

I

Subject:

Three Mile Island Nuclear Station, Unit 1,(TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request (TSCR) No. 264 Independent Core Reload Design Methodology in accordance with 10 CFR 50.4(b)(1), enclosed is Technical Specification Change Request No. 264.

The purpose of this TSCR is to incorporate additional NRC-approved analytical methods used to determine TMI-l core operating limits. These additional analytical methods have been l previously reviewed and approved by the NRC for use in TMI-l core reload design by NRC l

Safety Evaluation Reports dated February 10,1997 (TR-078), December 19,1996 (TR-087),

February 21,1996 (TR-091), and March 27,1997 (TR-092P). TM1-1 Cycle 12 core reload l

i design and analysis is also utilizing NRC approved Framatome Topical Report BAW-10192 P-A,

! "BWNT Loss-of-Coolant Accident Evaluation Model for Once-Through Steam Generator Plants" (NRC Safety Evaluation Report, dated February 18, 1997). Framatome is revising Topical Report BAW-10179 P-A, " Safety and Methodology for Acceptable Cycle Reload Analyses", currently referenced in TMI-l Technical Specification Section 6.9.5.2, to incorporate BAW-10192 P-A.

Using the standards in 10CFR50.92, GPU Nuclear has concluded that these proposed changes do not constitute a significant hazards consideration, as described in the enclosed analysis performed in accordance with 10CFR50.91(a)(1). Also enclosed is the Certificate of Service for this request certifying service to the chief executives of the township and county in which the 3 facility is located, as well as the designated of11cial of the Commonwealth of Pennsyivania, I Bureau of Radiation Protection.

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. Page 2 of 2 Approval of this TSCR is requested by July 1,1997 since these NRC-approved methods are being utilized to support TMI-l Cycle 12 core reload design activities.

Sincerely, t

J. W. Langenb 1 Vice President and Director, TMI Enclosures  !

JWUDJD/ lab

Enclosures:

(1) TMI-l TSCR No. 264 Safety Evaluation and No Significant Hazards Consideration (2) TMI-l Technical Specifications Revised Page (3) Certificate of Service for TMI-l TSCR No. 264 i 1

l c: Administrator Region I TMI Senior Resident Inspector ,

TMI-l Senior Project Manager t

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METROPOLITAN EDISON COMPANY ,

JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT I . i Operating License No. DPR-50 l Docket No. 50-289  ;

Technical Specification Change Request No. 264 i COMMONWEALTH OF PENNSYLVANIA )  !

) SS:

' COUNTY OF DAUPHIN )  !

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!t This Technical Specification Change Request is submitted in support of Licensee's request to ,

change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit l

1. As a part of this request, proposed replacement pages for Appendix A are also included.

' All statements contained in this submittal have been reviewed, and all such statements made and .

matters set forth therein are true and correct to'the best of my knowledge.

GPU NUCLEAR INC.

t BY:

e President and ctor, TMI +

f Sworn and Subreribed to before me this8th day of May ,1997.

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Notary Public ,

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Linda C. Wmer.

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4 Enclosure 1 TMI-l TSCR 264 Safety Evaluation and No Significant Hazards Consideration i

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& 6710-97-2139 ,

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Enclosure 1 Page 1 of 3 I. TECHNICAL SPECIFICATION CHANGE REOUEST (TSCR) No. 264 i

l GPU Nuclear requests that the following change be made to the existing TMI-l Technical )

Specifications (TS):

A. Replacement Pages:

The following revised paga, provided in Enclosure 2, replaces existing TS page: 6-19

11. REASON FOR CHANGE The purpose of this TSCR is to incorporate additional analytical methods for determining core operating limits, previously reviewed and approved by NRC, to Technical Specification Section 6.9.5.2. These additional analytical methods support GPU Nuclear's in-house core reload design analysis capability.

The individual methodology topical reports being added to Technical Specification Section 6.9.5.2, and the corresponding NRC Safety Evaluation Reports (SER) approving each for use at TMI-l are identified below:

Topical ReppR NRC SER TR-078-A, Revision 0,"TMI-l Transient Analyses Using February 10,1997 i

the RETRAN Computer Code" TR-087-A, Revision 0, "TMI-l Core Thermal-Hydraulic December 19,1996 Methodology Using the VIPRE-01 Computer Code" TR-091-A, Revision 0, " Steady State Reactor Physics February 21,1990 Methodology for TMI-1" TR-092P-A, Revision 0, "TMI-l Reload Design and March 27,1997 Setpoint Methodology" These NRC-approved methods are being utilized to support TMI-l Cycle 12 (Fall 1997) core reload design activities.

Technical Specification Section 6.9.5.2 is also editorially revised to relocate the existing note that the current revision level shall be specified in the COLR, such that it applies to the additional Topical Reports, as well as BAW-10179 P-A.

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6710-97-2139  :

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Enclosure 1-Page 2 of 3  :

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! III. SAFETY EVALUATION .IUSTIFYING CIIANGE F

The proposed amendment incorporates additional analytical methods previously reviewed l and approved by the NRC, to Technical Specification Section 6.9.5.2. The GPU Nuclear'-

• i Topical Reports TR-078, TR 087, TR-091, and TR-092P will be utilized by GPU Nuclear '

to perform core reload design analysis for TMI-1.

l The proposed amendment is considered an administrative change since the analytical

! methodologies described in each Topical Report being added to Technical Specification , Section 6.9.5.2 have been previously reviewed and approved by the NRC for use in TMI-l c applications. Implementation of these analytical methodologies for TMI-l is governed by

' the limitations and requirements specified in the individual NRC SERs approving each ,

Topical Report, as referenced above.

4 The editorial change to relocate the existing note indicating that the current revision level .

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i shall be specified in the COLR is made to be consistent with the existing Topical Report BAW-10179 P-A. Revisions to these methodologies will be submitted for review and i

approval by NRC prior to implementation. Upon NRC approval, the TMI-l COLR will be revised to reflect the specific Topical Report revision. This will preclude the need to revise the Technical Specification for each Topical Report revision. This is consistent with present practice.

The existing provisions of Technical Specification Section 6.9.5, Core Operating Limits ,

Report, are not affected by the proposed amendment. TMI-l core operating limits will  ;

continue to be established using NRC-approved methods and criteria. J l

IV. NO SIGNIFICANT IIAZARDS CONSIDERATION l 4

GPU Nuclear has determined that this Technical Specification Change Request poses ao

. significant hazards as defined by 10CFR50.92.

1. Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or the consequences of an accident previously evaluated. The proposed change to reference the analytical methodologies specified in GPU Nuclear Topical Reports TR-078, TR-087, TR-091,  :

and TR-092 use in TMI-l core reload design analysis is considered administrative l l since these Topical Reports have been reviewed and approved by the NRC for use at TMI 1.

Therefore, the proposed change does not involve a significant increase in the

probability of occurrence or the consequences of an accident previously evaluated.

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3 6710-97-2139 .;

Enclosure 1  ;

Page 3 of 3 a

2. . Operation of the facility in accordance with the proposed amendment would not create  ;

the possibility of a new er different kind of accident from any previously evaluated.

The proposed change to reference NRC-approved GPU Nuclear Topical Reports TR- l 078, TR-087, TR-09_l, and TR-092P will continue to ensure that approved methods i and criteria are used to establish core operating limits. j t

Therefore, the proposed change does not create the possibility of a new or different - [

kind of accident from any previously evaluated.  !

3. Operation of the facility in accordance with the proposed amendment would not  ;

involve a significant reduction in a margin of safety. The proposed change to {

reference NRC-approved GPU Nuclear Topical Reports TR-078, TR-087, TR-091, j and TR-092P maintains existing margins of safety since approved methods and criteria  ;

are still used to establish core operating limits.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.  ;

I V. JMPLEMENTATION It is requested that the amendment authorizing this change become effective upon issuance.

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