ML20059D062

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Amends 144 & 148 to Licenses DPR-24 & DPR-27,respectively, Modifying TS Section 15.3.0 Re Control Rod & Power Distribution Limits
ML20059D062
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/03/1994
From: Hansen A
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059D065 List:
References
NUDOCS 9401060389
Download: ML20059D062 (6)


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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 p#

i WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 144 License No. DPR-24 1.

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

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated November 24, 1992, 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 i

Commission; C.

There is reasonabla 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 requirements have been satisfied.

9401060389 940103 PDR ADOCK 05000266 P

PDR

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 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.

144, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 20 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Allen G. Hansen, Project Manager Project Directorate-III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

. acifications Date of issuance: January 3,1994

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UNITED STATES :

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NUCLEAR REGULATORY, COMMISSION.

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WISCONSIN ELECTRIC POWER COMPANY-7 DOCKET N0. 50-301 POINT-BEACH NUCLEAR PLANT. UNIT N0. 2

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t AMENDMENT TO FACILITY OPERATING LICENSE j

Amendment No.148-License No.- DPR.,

J 1.

The Nuclear Regulatory Commission (the Commission) has found thatf A.

The application for amendment by Wisconsin Electric Power CompanyL (the licensee) dated. November 24,.1992,- complies with the-a standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),'and the Commission's rules and regulations set.

,j forth in;10 CFR Chapter I; B.

The facility will operate in conformity with the application, the' I

provisions of the Act, and the rules and regulations' oflthe Commission; i

C.

There is reasonable assurance (i) that the. activities authorized-by this amendment can be conducted without endangering the health'

_l and' safety of the public, and (ii) that such activities will-be a

conducted in compliance with the Commission's regulations -

1

.: t 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 requiremen's have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license 1 amendment, and paragraph 3.B of Facility Operating License No.

DPR-27 is hereby amended to read as follows:

d-B.

Techn'ical Specifications The Technical Specifications contained in'A)pendices A and B, as revised through Amendment No.148, are 1ereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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3.

This license amendment is effective immediately upon issuance.

The Technical Specifications are to be implimented within 20 days from the date of issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION Allen G. Hansen, Project Manager Project Directorate'III-3 Division of Reactor Projects III/IV/V-Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of issuance: January 3,1994 q

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ATTACHMENT TO LitENSE AMENDMENT NOS.144 AND 148 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 l

Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by-amendment number and contains marginal lines indicating the area of change.

REMOVE INSERT 15.3.10-1 15.3.10-1 J

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15.3.10 CONTROL ROD AND POWER DISTRIBUTION LIMITS -

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Applicability-Applies to the operation of the control rods and to core power distribution limits.

Objective i

s To insure (1)' core subtriticality after a reactor trip (2) a limition.

potential reactivity insertions from a hypothetical rod cluster control assembly (RCCA) ejection, and (3) an acceptable core power distribution f

during power operation.

Specification i

- A.

Bank Insertion Limits l.

Wher. the reactor is critical, except for physics tests and control rod exercises, the shutdown banks shall be fully withdrawn.

i 2.

When the reactor is critical, the control banks'shall be inserted no further than the limits shown by the lines on' Figure 15.3.10-1.

Exceptions to the insertion limit are permitted for physics tests and control rod exercises.

3.

The shutdown margin'shall exceed the appifcable value as shown in Figure 15.3.10-2 under all-steady-state operating conditions from 0

350 F to full _ power. An exception to the stuck RCCA component of d

the shutdown margin equirement is permitted fer physics tests.

4.

Except_ for physics tests a shutdown margin of at least 1% ak/F

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shall be maintained when the reactor coolant temperature is less than 350 F.

5.

During any approach to criticality,- except for physics tests, the l.

critical rod position shall not be lower:than the insertion limit.

for zero power. That is, if.the control rods were withdrawn'in normal sequence with no other reactivity change, the reactor would l

not be critical unti.1 the control banks were above the: insertion-limit.

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-(1) Fully withdrawn is defined as a bank demand position equal to or_ greater j

than 225 steps. This definition is applicable to-shutdown and control' banks.

15.3.10 1 Unit 1 - Amendment' No. 49. ISJ44 -

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' Unit 2 -' Amendment ~No..55 97.148 a

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