ML20214Q663

From kanterella
Jump to navigation Jump to search
Amends 108 & 111 to Licenses DPR-24 & DPR-27,respectively, Modifying Tech Specs to Remove Certain Limitations on Repair of Leaking Fuel Rods When Repairs Justified by cycle- Specific Reload Analysis
ML20214Q663
Person / Time
Site: Point Beach  
Issue date: 05/27/1987
From: Diianni D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20214Q665 List:
References
NUDOCS 8706050106
Download: ML20214Q663 (6)


Text

__

/

~%,

UNITED STATES NUCLEAR REGULATORY COMMISSION o

h W ASHINGTON, D. C. 20555

\\...../

1 WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT EEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. DPR-24 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated March 12, 1987, as revised by letters dated April 10 and 24, 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 conformity 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 j

conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 1

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.

j j

B706050106 870527 PDR ADOCK 05000266 P

PDR

. l 2.

Accordingly, the license is arrended by changes to the Technical l

Specifications as indicated in the attachment to this license amendment, and paragraph 3.B 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.108, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective upon issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION b

M, 8

~

Dominic C. Dilanni, Acting Project Director Project Directorate III-3 Division of Reactor Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: May 27, 1987

'o UNITED STATES

~g 8

NUCLEAR REGULATORY COMMISSION c.

WASHINGTON, D. C. 20555 r,

.g

\\...../

i WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACII.ITY OPERATING LICENSE Amendment No. 111 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 March 12, 1987 as revised by letters dated April 10 and 24, 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 Comission; C.

Thereisreasonableassurance(i)thattheactivitiesauthorized-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 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 ha": been satisfied.

y

2-2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating Lisense No.

DPR-27 is hereby amended to read as follow":

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 upon issuance.

FOR THE NUCLEAR REGULATORY COMMISSION wT) '

Dominic C. Dilanni, Acting Project Director Project Directorate III-3 Division of Reactor Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: May 27, 1987 l

i

\\

ATTACHMENT TO LICENSE AMENDMENT NOS.108 AND 111 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 l

DOCKET N05. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the page identified l

below and inserting the enclosed page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.

l l

REMOVE INSERT l

15.5.3-1 15.5.3-1 l

i l

I l

j 15.5.3 REACTOR l

Applicability f

Applies to the reactor core, Reactor Coolant System, and Emergency Core Cooling Systems.

Objective I

To define those design features which are essential in providing for safe system operation.

Specifications i

i A.

Reactor Core 1.

General The uranium fuel is in the form of slightly enriched uranium dioxide pellets. The pellets are encapsulated in Zircaloy-4 tubing to form fuel rods. The reactor core is made up of 121 fuel assemblies. Each fuel assembly nominally contains 179 l

fuel rods.U )

Where safety limits are not violated, limited substitutions of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel, or by vacancies, may be made 4

to replace damaged fuel rods if justified by cycle-specific reload analysis.

I 2.

Standard Cores Standard reactor cores consisting entirely of standard design fuel, contain approximately 48 metric tons of slightly enriched uranium. Standard design fuel assemblics are essentially the same as those contained in the initial cores.U )

\\

l 1

\\

i 15.5.3-1 Unit 1 - Amendment No. 22,28,86, 108 i

Unit 2 - Amendment No. 32,99, 111 r

-,---wy---s ew,.w

,-1--9.-,.-ry-mwg ce-,,-,,-m%=

yrw--t-wg-=i--w-

-pwsw-m


ta--ew-

--7 w-

-- *+ -

-we-

=-eve--w-v--v v-"w-T----

r---y wi-y T"4- - ' *+