ML14183A310

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Amend 163 to License DPR-23,revising TS Section 4.4.3.f.g & H to Allow Pahr Sys STI to Be Changed from 12 Month Interval to Refueling Outage Interval
ML14183A310
Person / Time
Site: Robinson 
Issue date: 04/19/1995
From: Matthews D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML14183A311 List:
References
DPR-23-A-163 NUDOCS 9504240299
Download: ML14183A310 (4)


Text

p REG1J UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 License No. DPR-23

1.

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

A.

The application for amendment by Carolina Power & Light Company (the licensee), dated April 13, 1995, as supplemented April 18, 1995, 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 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 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.

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-23 is hereby amended to read as follows:

9504240299 950419 PDR ADOCK 05000261 P

PDR

-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.163, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate II-1 Division of Reactor Projects -

I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 19, 1995

ATTACHMENT TO LICENSE AMENDMENT NO. 163 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.

Remove Page Insert Page 4.4-5 4.4-5

repairs are no: comp et n-0g days tne actor shalfl be shut down and deprsurized ntil repars are efected and the acceplance criterion in :. abcve is satis'ied.

f.

Tests of the recirculation heat removal system shall be conducted on a refueling interval.

g.

The emergency core cooling system sump suction line penetration will be leak tested on a refueling interval.

n. The bellows expansion joints and the suction line between the expansion joints and the valve will be visually inspected on a refueling interval.

4.4.4 Operational Surveillance Program 4.4.4.1 Inspection of Surveillance Tendons The first of two surveillance tendons will be removed from its embedded location and inspected after five years of operation and the second tendon will be removed and inspected after 25 years of operation.

4.4.4.2 Containment Structural Test

a. The containment structure will be pressurized to the design pressure, P. (42 psig) three and 20 years after operation. The test may coincide with the in-service inspection shutdown occurring closest to that interval.

4.4-5 Amendment No. 163