ML20116C372

TS Change Request 220 to License DPR-50,for Relocation of Figure 3.5-2M Re LOCA Limited Max Allowable Linear Heat Rate to COLR

ML20116C372
Person / Time
Site:	Three Mile Island
Issue date:	10/29/1992
From:	Broughton T GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20116C368	List: ML20116C367 ML20116C372 ML20116C376
References
NUDOCS 9211030343
Download: ML20116C372 (5)

Text

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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. OPR-50 Docket No. 50-289 Technical Specification Change Request No. 220 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 1. As a part of this request, proposed replacement pages for Appendix A are also included.

GPU NUCLEAR CORPORATION BY:

Vice PresidMt and Director, TMl-1 Sworn and Subscribed to before me this % % day of Octob4N , 1992.

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Notary Public 61 M t-a ihr wc WmCiliN22%ik l WMPomw#ataAnnuunof tuns 9211030343 921029 9 DR ADOCK 0500 _

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 GPU HUCLEAR CORPORATION LICENSE NO. DPR-50 _

CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No.

220 to Appendix A of the Operating License for lhree Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by depos.t in the United States mail, addrassed as follows:

Mr. Jay H. Kopp, Chairman Mr. Russell L. Sheaffer, Chairman Board of Sup9rvisors of Board of County Commissioners >

Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse 9 Middletown, PA 17057 Harrisburg, PA 17120 Mr. William P. Dornsife, Director PA. Dept. of Environmental Resources Bureau of Radiation Protection P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORPORATION ,

BY: m Vice PresidenF arid Director THI-l DATE:

October 29, 1992

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ENCLOSURE

1. TECHNICAL SPEClflCATION CHANGE RE0 VEST NO. 220 )

GPUN requests that the following changed replacement pages be inserted into the existing Technical Specifications:

Revised Pages: viii, 3-35a, 6-19a and 6-20 Remove figure: 3.5-2M These pages are attached to this ch;nge request,

11. REASON FOR CHANGE This change is requested to modify the THI-1 Technical Specifications to remove figure 3.5-2M, LOCA Limited Maximum Allowable Linear Heat Rate, and incorporate the, limits in the THI-l Core Operating '.imits Report (COLR). The COLR documents the THI-l core operating cycle limits that have been established using NRC-approved methodology, and is consistent with the criteria and results of the THI-l FSAR Safety Analysis. The COLR is submitted to NRC for each reload cycle in acct; dance with the requirements of Technical Specification Section 6.9.5.

Although the LOCA Limited Maximum Allowable Linear lleat Rate (LHR) limits sre not cycle-specific, they are subject to revision due to analysis input changes or changes in fuel assembly design. These LHR limits were revised in Cycle 8 due to changes in the Babcock & Wilcox (B&W) Emergency Core Cooling System (ECCS) analysis models and inputs, and vill require revision for the upcoming Cycle 10 to reflect B&W Mark 09 fuel assembly design changes. Additional future change to these limits may result from ongoing activities related to licensing fuel assemblies above system pressure (BAW -10183P). Moving the LOCA LHD. limits to the COLR will conserve NRC and licensee resources by

, eliminating the need for license amendments for the sole purpose of updating these limits.

The THI-l LOCA Limited Maximum Allowable Linear Heat Rate Limits are generic to 2568 MWt (design) B&W 177-FA, lowered-loop NSSS plants.

Otner B&W plants have relocated these limits or related parameters (such as maximum local linear power density peaking factors) to respective COLR's. The proposed change is also consistent with the proposed B&W Owner's Group Revised Standard Technical Specification provisions for specification of power distribution limits in the C0lR.

III. SAFETY EVALUATION JUSTIFYING CHANGES Technical Specification Page viii is revised to indicate deletion of Figure 3.5-2M.

Technical Specification Sectir 3.5.2.8 is revised to note that limits for power distribution shall be maintained within the acceptable l

4 operating range provided in the Core Operating Limits Report. The  ;

NRC- approved methodology for determining these limits is documented in the following:

BAW-10103, Rev. 3 "ECCS Analysis of B&W's 177-FA lowered loop NSS,"

July 1977.

BAW-1915P-A, "Dounding Analytical Assessment of NUREG-0630 Models on LOCA kw/ft Limits With Use of FLECSET," May 1986.

BAW-10104P-A, Rev. 5, "B&W ECCS Evaluation Model," November 1988.

BAW-10162P-A, " TACO-3 fuel Pin Thermal Analysis Computer Code,"

November 1989.

The LOCA derived power distribution limits are not strictly cycle-specific parameters and are therefore not expected to change with each reload design. However, for consistency and ease of operator use these limits are moved to the Core Operating Limits Report. Any future changes to these limits based on changes to the ECCS evaluation model would necessarily require NRC review and approval. Accordingly, Figure 3.5-2M which specifies the power distribution limits is removed and incorporated into the THI-l Core Operating Limits Report.

Technical Specification Section 3.5.2 BASES is revised to reflect deletion of Figure 3.5-2M.

Technical Specification Section 6.9.5.2 is revised to identify additional references to the analytical methods used to determine the LOCA Limited Maximum Allowable Linear Heat Rate limits. These methods have been previously reviewed and a) proved by the NRC for use at THI-

1. Future limits will continue to )e established using the methodology identified in Technical Specification 6.9.5, unless NRC review and apnroval for a change has_ been obtained. Reference to the new methodology w'll then be included in the Core Operating Limits Report and Technical Specification Section 6.9.5.2.

The specific values of the limits in the Core Operating Limits Report will be modified through the 10 CFR 50.59 process when such values are developed using an NRC-approved methodology consistent with all applicable limits of the safety analyses addressed in the THI-l FSAR.

As currently required by Technical Specification Section 6.9.5.4, any revisions to the Core Operating Limit Report will be provided upon issuance to the NRC for trending information.

IV. NO SIGNIFICANT HAZARDS CONSIDERATIONS GPUN has determined that the Technical Specification Chang Request poses no significant hazards as defined by NRC in 10 CFR 50.92.  ;

1. Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated. The proposed * ,dment relocates the .

LOCA Limited Maximum Allowable Linear Heat Ate limits to the THI-l Core Operating iimits Report in accordance with the intent of NRC Generic Letter 88-16. The proposcd amendment provides continued control- of the values of these limits and assures these values D- M _..re -- - - ' - -- 'F*"= '*w*-* * -e- 4+*N-+ r --- '*-t-- -

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remain consistent with all applicable limits of the safety analyses addressed in the 1MI-l FSAR. The Technical Specifications retain the requirement to maintain the plant within the appropriate bounds of these limits. Therefore, the proposed amendment has no effect on the probability of occurrence or consequences of an accident previously evaluated.

2. Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated. The i proposed amendment relocates the LOCA Limited Maximum Allowable ,

Linear Heat Rate limits to the THI-1 Core Operating Limits Report. The Technical Specifications retain the requirement'to maintain the plant within the appropriate bounds of these limits.

Therefore, the proposed amendment has no effect on the possibility of creating a new or dif ferent kind of accident from any accident previously evaluated.

3. Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a m6rgin of safety. The proposed amendment provides continued control of the values of these limits and assures these values remain consistent will all applicable limits of the safety analyses addressed in the THI-l FSAR. Therefore, it is-concluded that '

operation of the facility in accordance with the proposed ,

amendment does not involve a significant reduction in a margin of safety.

V. JBELLMENTAfl0N It is requested that the amendment authorizing this change become effective _upon issuance. A revised COLR will then be submitted upon issuance in accordance with Technical Specification Section 6.9.5.4.

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