ML14183A145

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Amend 123 to License DPR-23,adding Surveillance Requirements for Testing of molded-case Circuit Breakers Associated W/Auxiliary Feedwater Sys Valve V2-16A & Svc Water Sys Valve VG-16C
ML14183A145
Person / Time
Site: Robinson 
Issue date: 09/05/1989
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML14183A146 List:
References
DPR-23-A-123 NUDOCS 8909120206
Download: ML14183A145 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 123 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 27, 1989, 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:

PDR ADOCK 05000261 P

PDC

-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 123, 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.

FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, 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:

NAME :PA sn Ros J:R (/<:E nsm DATE :8/6 /89

8/ 9/89
8/1(/89
8/ /89 OFFICIAL RECORD COPY

ATTACHMENT TO LICENSE AMENDMENT NO.123 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 is indicated by marginal lines.

Remove Pages Insert Pages 4.1-14 4.1-14

TABLE 4.1-3 (Continued)

FREQUENCIES FOR EQUIPMENT TESTS Maximum Time Check Frequency Between Test

2.

Whenever integrity of a pressure isolation valve listed in Table 3.1-1 cannot be demonstrated, the integrity of the remaining valve in each high pressure line having a leaking valve shall be determined and recorded daily. In addition, the position of the other closed valve located in the high pressure piping shall be recorded daily.

18. Automatic Bus Test thermal and Each refueling shutdown.

NA Transfers magnetic trip elements of a) Auxiliary respective molded Feedwater Header case circuit Discharge Valve breakers.

to Steam Generator A, V2-16A b) Turbine Building, Cooling Water Isolation Valve, V6-16C 905080 8D0500 05000261 4.1-14 Amendment No. 123 PDC