ML20043F021

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Amend 123 to License DPR-28,modifying Tech Spec 5.2.B of Design Features Section to Add to Description of Control Rod Matl to Include Hafnium as Well as Boron Carbide
ML20043F021
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 06/05/1990
From: Wessman R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20043F026 List:
References
NUDOCS 9006140102
Download: ML20043F021 (4)


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't VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAP POWER STfTION APENDMENT TO FACILITY OPFRATING LICENSE Amendment No. 123 i

license No. DPR-28 7

1.-

The Nuclear Regulatory Comission (the Comission'or the MRC) has found that:-

.A.

The application for amendment filed by the Perront Yankee Nuclear Power Corporation (the licensee) dated Febrt.ary 28.-1990 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.CFP Chapter 1; B.

The facility will operate in cor.formity with the application, the -

provisions of the Act, and the rules and regulations of the

.t Commission; C._

There is reesonable assurance: (i)thattheactivitiesauthorizedby this arcndment can be conducted without endangering tbt health and safety of the public, and (ii) that such activities will be-conducted I

ir, compliance with.the Connission's regulations set forth in 10 CFR

-Chapter I; D.

The issuerce 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 thir emendment is in accordance with 10'CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordinply, the license is amended by changes to the Technical Specifica--

tions as indicated ir. the attachment to thit, license amendment, and paracraph 3.B of Facility Operating License No. DPR-?B is hereby amended.to read as follows:

Technicel Specifications 4

The Technical Specifications contained in Appendix A, as ravised through Amendment No.123, are hereby incorporated in the license.

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

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FOR THE NUCLEAR REGliLATORY COMMISSION

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.;o Richard.H. Wessman, Director j

Project Directorate 1 3 Division of Reactor. Projects 1/11.

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Office of Nuclear Reactor Regulation)

Attachment:

Chenpes to the Technical i

Specifications in

'Date of-Issuance:

June 5, 1990 u

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ATTACHMENT TO LICENSE AMENDMENT NO. 123 FAClllTY OPERATING LICFNSE NO. DPD-?B:

DOCKET 110, 50-271 Replace the following page of the Appendix A Technical Specifications with

-the attached page. The revised page is identified by' Amendment number and v

- contains vertical lines indiceting the area of change.-

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Remove Insert 188 188 i

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VYNPS

5.0 DESIGN FEATURES

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5.1 Site The btation is located on the property on the west bank 'of the Connecticut River in the Town of Vernon,

Veridbift, wtgich the Vermont Yankee Nuclear Power Corporation either owns or to which it has perpetual rights and easements. The site plan showing the exclusion area boundary, boundary.for gaseous effluents and boundary for liquid effluents is on Figure 2.2-5 in the FSAR. The minimum distance to the boundary of the exclusion area as defined in'10CFR100.3 is 910 feet..

No.part of'the site shall be sold or leased and no structure shall be-located on the site except structures owned by the Vermont Yankee Nuclear Power Corporation or related utility companies and used in conjunction with normal utility operations.

5.2 Reactor

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A.

The core shall consist of not more than 368 fuel assemblies.

B.

The reactor core shall contain 89 cruciform-shaped control rods. The control material shall be boron carbide powder (B C) or hafnium, or a combination of the two.

4 5.3 Reactor Vessel The reactor vessel shall be as described in Table 4.2-3 of the FSAR. The applicable design codes shall be as described in subsection 4.2 of the FSAR.

5.4 Containment A.

The principal design parameters and applicable design codes for the primary containment shall be as given in Table 5.2.1 of the FSAR.

B.

The secondary containment shall be as described in subsection 5.3 of the FSAR and the applicable codes shall be as-described in Section 12.0 of the FSAR.;

t C.

Penetrations to'the primary containment end piping passing through such penetrations shall'be designed in accordance with standards. set forth in subsection 5.2-of the FSAR.

Amendment No. 83 123 188

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