ML20149M884

Amend 99 to License DPR-61,revising Tech Spec 5.4, Containment, by Deleting Section 5.4.B, Penetrations, Which Refs Design Info Concerning Penetrations & Associated Bases

ML20149M884
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	02/22/1988
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20149M876	List: ML20149M875 ML20149M884 ML20149M885
References
NUDOCS 8802290207
Download: ML20149M884 (4)

Text

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,.* UNITED STATES

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CONNECTICUT YANKEE ATOMIC POWER COMPANY 00CKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. OPR-61 I

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1. The Nuclear Regulatory Comission (the Comtitsic; has found that:

A. The application for amendment by Conn. *..at Yankee Atomic Power Company (the licensee), dated September 9, 1987, complies with the standards and requirements of the Atoolc Energy Act of 1954, as amended (the Act), and the Commission's rules and regulatiens a' 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 (i) 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 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 Commission'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 attachment to this license amendment l and Paragraph 2.C.(2) f Facility Operating License No. DPR-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.99 , are hereby incorporated into the license.

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

3. This license amendment is effective as of the date of its issuance. )

1 FOR THE NUCLEAR REGULATORY COMMISSION P

oh LT F. Stolz, Directo ect Directorate I

{

ision of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: February 22, 1988 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE N0. DPR-61 DOCKET NO. 50-213 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains marginal lines indicating the area of change.

REMOVE INSERT 5-4 5-4 l

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5,4 Containment Applicability:

Applies to those design features of the containment relating to operational and public safety.

Objective:

To describe the sign & ant design features of the reactor containment structure.

Specifications: A. Reactor Containment

1. The reactor containment shall be a steel lined reinforced concrete structure having a net free volume of approximately 2.2x10 6 cubic feet.

2. The materials used in construction shall conform to the codes specified in Table 6.2-4 of the UFSAR.

3. The stress levels in the structure shall not exceed those specified in Section 6.2.1 and Table 6.2-3 of the UFSAR.

l _ Basis:

The containment is designed to lirnit the consequences of any release of radioactive material from the reactor coolant system. The internal pressure used in the design is 40 psig and the ground acceleration in the maximum postulated earthquake is 0.17 g at zero period. The containment design l will withstand wind velocities up to 300 mph and snow or ice loads of 30 psf. However, no snow or ice loads are included in l

combination with internal pressure and seismic loads, because they would reduce the tension in the walls. The containment l l

will also withstand an internal vacuum of approximately 7.5 ~

psi.

However, it is inconceivable tha t such a pressure dif ferential could occur.

Reference:

UFSAR Section 6.2 5-4 Amendment No. 99