ML20086R693
| ML20086R693 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/24/1995 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20086R696 | List: |
| References | |
| NUDOCS 9507310246 | |
| Download: ML20086R693 (4) | |
Text
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' UNITF.D STATES 3
NUCLEAR REGULATORY COMMISSION f
WASHINGTON. D.C. 2066H001
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION f
DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.194 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated June 1, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 (1) 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 conducted in compliance with the Commission'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 Commission's regulations and all applicable v
requirements have been satisfied.
9507310246 950724 PDR ADOCK 05000289 P
2.
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:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.194, 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.
FOR THE NUCLEAR REGULATORY COMMISSION y
Phillip F'. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 24,1995
I ATTACHMENT TO LICENSE AMENDMENT NO.194 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following page of the Appendix A, Technical Specifications, with the attached page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Remove Insert 5-4 5-4 l
l l
5.3 REACTOR Aonlicability l
' Applies to the design features of the reactor core and reactor coolant system.
QMective 1
To' define the significant design features of the reactor core and reactor coolant system.
i Soecification 5.3.1 REACTOR CORE j
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.
Fuel rods shall. be clad with zircaloy, ZIRLO, or BWFC zirconium-based M4 or M5 alloy materials and contain an initial composition of natural i
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 applications 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 i
comply with all fuel safety design bases. A limited number of lead i
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 TMI-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.
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5.3.1.3 The core average and individual batch enrichments for the present cycle are described in TMI-1 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 TMI-l FSAR Chapter 3.
The CRA and APSRA design data are also described in the UFSAR.
5.3.1.5 The TMI-1 core may contain burnable poison rod assemblies (BPRA) and gadolinia-urania integral burnable poison fuel pellets as described in TMI-1 UFSAR Chapter 3.
5.3.1.6 Reload fuel assemblies and rods shall conform to design and evaluation data described in the UFSAR.
Enrichment shall not exceed I
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 No. J2p, Jig, J59, J57, J79,175, W3',194 t
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