ML20064J112
| ML20064J112 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/14/1994 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20064J116 | List: |
| References | |
| GL-90-002, DPR-50-A-183 NUDOCS 9403210019 | |
| Download: ML20064J112 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET N0. 50-289 THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.183 License No. DPR-50 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee), dated August 26, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9403210019 940315 PDR ADOCK 05000289 P
PDR l
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of facility Operating License No.
DPR-50 is hereby amended to read as follows:
i (2)
Technical Specifiqalions The Technical Specifications contained in Appendix A, as revised through Amendment No.183, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION I
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John F. Stolz, Director Project Directorate I-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
March 15, 1994
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ATTACHMENT TO LICEh1S(JMENOMENT N0.183 FACILITY OPERATIRG_ LICENSE NO. OPR-1Q DD_CKET NO. 50-289 Replace the fol'owing pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Etmays Insert 5-4 5-4 5-5 5-5
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S.3 REACTOR
[policabilit_y l
Applies to the design features of the reactor core and reactor coolant i
system.
Obiective To define the significant design features of the reactor core and reactor coolant system.
Specification 5.3.1 REACTOR CORE 5.3.1.1 A fuel assembly normally contains 208 fuel rods arranged in a 15 by 15 lattice.
The reactor shall contain 177 fuel assemblies.
Each assembly shall consist of a matrix of zircaloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide.as fuel material.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applicatiors of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases.
A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions. The details of the fuel assembly design are described in THI-l UFSAR Chapter 3.
5.3.1.2 The reactor core shall approximate a right circular cylinder with an equivalent diameter of 128.9 inches.
The active fuel height is defined in THI-l UFSAR Chapter 3.
5.3.1.3 The core average and individual batch enrichments for the present cycle are described in TMI-l UFSAR Chapter 3.
- 5. 3.1. 4 The control rod assemblies (CRA) and axial power shaping rod assemblies (APSRA) are distributed in the reactor core as shown in THI-1 FSAR Chapter 3.
The CRA and APSRA design data are also described in the UFSAR.
5.3.1.5 The THI-l core may contain burnable poison rod assemblies (BPRA) and gadolinia-urania integral burnable poison fuel pellets as described in TMI-l UFSAR Chapter 3.
5.3.1.6 Reload fuel assemblies and rods shall conform to design and evaluation data described in the UFSAR. 2 richment shall not exceed a nominal 5.0 weight percent of U 5.3.2 REACTOR COOLANT SYSTEM 5.3.2.1 The reactor coolant system shall be designed and constructed in accordance with code requirements.
(Refer to UFSAR Chapter 4 for details of design and operation.)
5-4 Amendment 126, WE, la, ifr7, IM, pa,183,
5.3.2.2 The reactor coolant system and any connected auxiliary systems exposed to the reactor coolant conditions of temperature and pressure, shall be designed for a pressure of 2,500 psig and a temperature of 650*F.
The pressurizer and pressurizer surge line shall be designed for a temperature of 670*F.
5.3.2.3 The reactor coolant system volume shall be less than 12,200 cubic feet.
1 5-5 AmendmentNo.1/,If,183,
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