ML20206R117

Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement

ML20206R117
Person / Time
Site:	Three Mile Island
Issue date:	05/13/1999
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20206R114	List: ML20206R111 ML20206R117
References
NUDOCS 9905200002
Download: ML20206R117 (8)

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f f-i Enclosure 2 TMI-l License and Technical Specification Revised Pages 9905200002 990513 PDR ADOCK 05000289 P PDR

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f. The Owners have satisfied the applicable provisions of 10 CFR Part 140," Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations;

g. The issuance of this operating license will not be inimical to the common defense and security or to the health and safety of the public;

h. After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of Facility i Operating License No. DPR-50 is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied; and

i. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30,40 and 70, including 10 CFR Section 30.33,40.32,70.23 and 70.31.

2. Facility Operating License No. DPR-50 is hereby issued to the Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company d/b/a GPU Energy and GPU Nuclear, Inc. to read as follows:

a. This license applies to the Three Mile Island Nuclear Station, Unit 1, a pressurized water reactor and associated equipment (the facility), owned by the Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company d/b/a GPU Energy and operated by GPU Nuclear Inc.. The facility is located in Dauphin County, Pennsylvania, and is described in the " Updated Final Safety Analysis Report" as supplemented and amended and the Environmental Report as supplemented and amended.

b. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1) GPU Nuclear, Inc., pursuant to Section 104b of the Act and 10 CFR Part 50, " Licensing of Production and Utilization Facilities," to possess, use, r.nd operate the facility; and Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company d/b/a GPU Energy to pos'sess the facility in accordance with the procedures and limitations set forth in this license; l

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Amendment No.-247 l

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1 (3) Physical Protection The license shall fully implement and maintain in effect all l provisions of the Commission-approved physical security, guard l

training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain safeguards information protected under 10 CFR 73.21, are entitled:

"Three Mile Island, Units 1 and 2, Modified Amended Physical Security Plan," as revised; "Three Mile Island, Units 1 and 2, Security Personnel Training and Qualification Plan," as revised; and "Three Mile Island, Units 1 and 2, Safeguards Contingency Plan," as revised. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. {

(4) Fire Protection GPU Nuclear, Inc. shall implement and maintain in effect all provisions of the Fire Protection Program as described in the UpJ d FSAR for TM-1.

Changes may be made to the Fire Protection Program without prior approval by the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Temporary changes to specific fire protection features which may be necessary to accomplish maintenance or modifications are acceptable provided that interim compensatory measures are implemented. ,

l (5) The licensee shall implement a secondary water chemistry

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monitoring program to inhibit steam generator tube degradation. l' This program shall include:

a. Identification of a sampling schedule for the critical parameters and control points for these parameters;

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b. Identification of the procedures used to measure the values of the critical parameters; Amendment No.-207

c. Identification of process sampling points;

d. Procedure for the recording and management of data;

e. Procedures defining corrective actions of off control point chemistry conditions; and

f. A procedure identifying (1) the authority responsible for the interpretation of the data, and (2) the sequence and timing of administrative events required to initiate corrective action.  ;

(6) lnservice Testing - DELETED i

(7) Aircrafi Movements - DELETED l

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i Amendment No. 207 l

Bases The limitation on power operation with one idle RC pump in each loop has been imposed since the ECCS cooling performance has not been calculated in accordance with the Final Acceptance Criteria requirements specifically for this mode of reactor operation. A time period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed for operation with one idle RC pump in each loop to effect repairs of the idle pump (s) and to return the reactor to an acceptable combination of operating RC pumps. The 24 hcurs for this mode of operation is acceptable since this mode is expected to have considerable margin for the peak cladding temperature limit and since the likelihood of a LOCA within the 24-hour period is considered very remote.

A reactor coolant pump or decay heat removal pump is required to be in operation before the boron concentration is reduced by dilution with makeup water. Either pump will provide mixing which will prevent sudden positive reactivity changes caused by dilute coolant reaching the reactor. One decay heat removal pump will circulate the equivalent of the reactor coolant system volume in one-half hour or less.

The decay heat removal system suction piping is designed for 300 F and 370 psig; thus, the system can remove decay heat when the reactor coolant system is below this temperature (References 1,2, and 3).

Both sia.am generators must be operable before heatup of the Reactor Coolant System to insure system inigrity against leakage under normal and transient conditions. Only one steam generator is required for decay heat removal purposes.

One pressurizer code safety valve is capable of preventing overpressurization when the reactor is not critical since its relieving capacity is greater than that required by the sum of the available heat sources which are pump energy, pressurizer heaters, and reactor decay heat. Both pressurizer code J safety valves are required to be in service prior to criticality to conform to the system design relief capabilities. The code safety valves prevent overpressure for a rod withdrawal or feedwater line break accidents (Reference 4). The pressurizer code safety valve lift set point shall be set at 2500 ,

l psig 11% allowance for error. Surveillance requirements are specified in the Inservice Testing Program. Pressurizer code safety valve setpoint drift of up to 3% is acceptable in accordance with ASME Section XI (Reference 5) and the assumptions of TMI-1 safety analysis.

Referencese j (1) UFSAR, Tables 9.5-1 and 9.5-2 (2) UFSAR, Sections 4.2.5.1 and 9.5 " Decay Heat Removal" (3) UFSAR, Section 4.2.5.4 " Secondary System" (4) UFSAR, Section 4.3.10.4 " System Minimum Operational Components" (5) UFSAR, Section 4.3.7 " Overpressure Protection" 3-2 Amendment No. 47 (12/22n8),457 l

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I Enclosure 3 I

Certificate of Service for TMI-I Technical Specification Change Request No. 275 l

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 GPU NUCLEAR INC. LICENSE NO. DPR-50 CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 275 to the Operating License and 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 Londonderry 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:

Mr. Darryl LeHew, Chairman Ms. Sally S. Klein, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Front & Market Streets Middletown, Pa,17057 Dauphin County Counhouse Harrisburg, PA 17120 Director, Bureau of Radiation Protection PA Dept. of Environmental Resources Rachael Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Attn: Mr. Stan Maingi GPU NUCLEAR INC.

B - b Vice President arfd DiMetor, TMI l

i DATE: E ~ I i -D

METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANI A ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 t

Operating . License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 275 COMMONWEALTH OF PENNSYLVANIA )

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COUNTY OF DAUPHIN )

This Technical Specification Change Request is submitted in support of Licensee's request to change Operating License No. DPR-50 and Appendix A to Operating License for Three Mile Island Nuclear Station, Unit 1. As a part of this request, proposed replacement pages for the License and Appendix A to the License 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.

s GPU NUCLEAR INC.

BY af b Vice Presideri andpirector, TMI Sworn a Subscribed before me this/ day of 42u- ,1999.

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/ Notary Public Notarial Seal

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Suzanne C Miklosik, Notary Public My m bn xhi es oy ,1999 i

Member, Pennsylvania Assocation of Notanes

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