ML20149G775
| ML20149G775 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/03/1988 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149G778 | List: |
| References | |
| NUDOCS 8802180406 | |
| Download: ML20149G775 (6) | |
Text
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+f UNITED STATES NUCLEAR REGULATORY COMMISSION g
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.s WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 License No. OPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by Wisconsin Electric Power Company (thelicensee)datedOctober 13, 1987 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 Commissf3n; 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 i
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 Conmission's regulations and all applicable requirements have l
been satisfied.
r 8802180406 880203 PDR ADDCK 05000266 P
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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 3.8 of Facility Operating License No.
DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.111, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective imediately upon issuance. The Technical Specifications are to be implemented within 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Kenneth E. Perkins, Director Project Directorate III-3 Division of Reactor Projects
Attachment:
Changes to the Technical Specificationt Date of Issuance:
February 3, 1988
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UNITED STATES 8
,e NUCLEAR REGULATORY COMMISSION g
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WISCONSINELECTRICPOWERCOMPAJN DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. DPR-27 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated October 13, 1987 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense ar.d security or to the health and safety of the public; i
and E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachn'ent to this license amendment, and paragraph 3.B of Facility Operating License No.
OPR-27 is hereby amended to read as follows:
B.
, Technical Spe_cifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 114, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is "Nectivo imediately upon issuance. The Technical Specifications t.c. to be implemented within 20 days from the j
date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION 1
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Kenneth E. Perkins, Director 1
Project Directorate III-3 l
Division of Reactor Projects l
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 3, 1988 f
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ATTACHMENT TO LICENSE AMENDMENT NOS.111 AND 114 l
TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 E
DOCKET NOS. 50-266 AND 50-301 i
Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by anendirent number and contains marginal lines indicating the area of change.
REMOVE INSERT 15.5.3-2
'15.5.3-2 i
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Transition Cores l
The transition cores are defined as being any core loading pattern consisting of standard and 0FA 14x14 fuel assemblies. Use of 0FA demonstration assemblies in cores of standard design fuel does not constitute a transition core.
The initial transition reactor core contains approximately 47 metric tons of uranium in the form of g
slightly enriched uranium dioxide pellets.
4.
The average reload region enrichment of the initial transition l
core is a nominal 3.20 weight percent of U-235.
5.
The transition reload fuel will be similar in design to the initial core standard fuel.
6.
Burnable poison rods are incorporated for reactivity and/or power distribution control. The burnable poison rods consist of borated pyrex glass clad with stainless steel.54) l 7.
There are 33 full length RCC assemblies in the reactor core.
l The full-length RCC assemblies contain a 142 inch length of silver-indium-cadmium all'y clad with the stainless steel.
l B.
l.
The design of the Reactor Coolant System complies with the code requirements.(6) 2.
All high pressure piping, components of the Reactor Coolant System and their supporting structures are designed to Class I requirements, and have been designed to withstand:
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The design seismic ground acceleration 0.069, acting in jy the horizontal and 0.04g acting in the vertical planes
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allowable working stresses.
simultaneously, with stresses maintained within code I
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Unit 1 - Amendment No. 22,26,86, 111 Unit 2 - Amendment No. 32,H 114 15.5.3-2 f
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