ML20092J182
| ML20092J182 | |
| Person / Time | |
|---|---|
| Site: | Crane  (DPR-50-A-196) |
| Issue date: | 09/19/1995 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20092J185 | List: |
| References | |
| NUDOCS 9509220007 | |
| Download: ML20092J182 (6) | |
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-d UNITED STATES l
j NUCLEAR REGULATORY COMMISSION g.
WASHINGTON, D.C. m
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l METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY j
PENNSYLVANIA ELECTRIC COMPANY l
GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.196 License No. DPR '
1.
The Nuclear Regul tory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated August 11, 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 i
requirements have been satisfied.
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9509220007 950919 PDR ADOCK 05000289 P
y
. 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 Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.196, 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 Phillip. 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:
September 19, 1995 3
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ATTACHMENT TO LICENSE AMENDMENT NO.196 i
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FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 i
i Replace the following pages of the Appendix A, Technical Specifications, with the. attached pages. The revised pages are identified by amendment number and contains a vertical line indicating the area of change.
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TABLE OF CONTENTS Section Eagt i
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2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 2.1 Saferv Limita. Panetor Core 2-1 2,2 Rafarv I imita. Paarvar Sveram Pra==are 2-4 2.3 I i=itiaa Rafarv Svetam Settinen. Protaction instrumentation 2-5 i
3 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 General Action Requirements 3-1
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i 3.1 Reactor Coolant System 3-la 3.1.1 Operational Components 3-la i
3.1.2 Pressurization, Heatup and Cooldown Limitations 3-3 3.1.3 Minimum Conditions for Criticality 34 3.1.4 Reactor Coolant System Activity 3-8 j
3.1.5 Chemistry 3-10 3.1.6 Leakage 3-12 j
3.1.7 Moderator Temperature Coefficient of Reactivity 3-16 1
3.1.8 Single Loop Restrictions 3-17 l
l 3.1.9 Low Power Physics Testing Restrictions 3-18 j
3.1.10 Control Rod Operation 3-18a i
3.1.11 Reactor Internal Vent Valves 3-18c 3.1.12 Pressurizer Power Operated Relief Valve (PORV) and Block Valve 3-18d 3.1.13 Reactor Coolant System Vents 3-18f I
j 3.2 Deleted 3-19 l
3.3 Fmaroency Core Cooline. Panctor Buildine Fmareency Cooline nad Paaetor Buildine Sorav Sverama 3-21 3.4 Dg;av Heat Removal Canability 3-25 l
3.4.1 Reactor Coolant System Temperature Greater than 250*F 3-25 j
3.4.2 Reactor Coolant System Temperature 250'F or Less 3-26 3.5 In<trumantation Sv='ame 3-27 3.5.1 Operational Safety Instrumentation 3-27 3.5.2 Control Rod Group and Power Distribution Limits 3-33 3.5.3 Engineered Safeguards Protection System Actuation Setpoints 3-37 i
3.5.4 Incore Instrumentation 3-38 3.5.5 Accident Monitoring instrumentation 3-40a l
3.5.6 Deleted 3-40f 3.6 Reactor Building 3-41 j
3.7 Umt Electrical Power System 3-42 3.8 Fuel loading and Refueling 3-44 3.9 Deleted 3-46 3.10 Miscellaneous Radioactive Materials Sources 3-46 3.11 Handling of Irradiated Fuel 3-55 3.12 Reactor Building Polar Crane 3-57 3.13 Caraadary Sv=*am Activity 3-58 l
3.14 E100d 3-59 3.14.1 Periodic Inspection of the Dikes Around TMI 3-59 3.14.2 Flood Condition for Placing the Unit in Hot Standby 340 3.15 Air Tramtmant Sverame 341 3.15.1 Emergency Control Room Air, Treatment System 341 3.15.2 Reactor Building Purge Air Treatment System 342a 3.15 3 Auxiliary and Fuel Handling Building Air Treatment System 3-62c 3.15.4 Fuel Handling Building ESF Air Treatment System 3-62e ii Amendment No. 59, 72, 78, 97, 98, !!9, 122, 136, 149, 167, 182,196
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3.2 MAKEUP AND PURIFICATION AND CHEMICAL ADDITION SYSTEMS DELETED-1 i
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3-19 l
Amendment No. 43, 50, 98, 157,196
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Amendment No. 50, 152, 157, 168,196 i
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