ML14183A238

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Amend 143 to License DPR-23,clarifying Item 44 of TS Table 4.1-1 Which Specifies Min Frequencies for Checks,Calibrs & Tests of Containment Vessel High Range Monitors
ML14183A238
Person / Time
Site: Robinson 
Issue date: 12/10/1992
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML14183A239 List:
References
DPR-23-A-143 NUDOCS 9212220344
Download: ML14183A238 (4)


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 143 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Pages Insert Pages 4.1-9a 4.1-9a 9212220344 921210

-PDR ADOCK 05000261 P

PDR_

TABLE 4.1-1 (Continued)

48.

Reactor Vessel Level Instrumentation System (RVLIS)

M R

N.A.

49.

Incore Thermocouple Temperature Instrumentation M

R N.A.

+

Containment Water Level Monitor -

NUREG-0737 Item II.F.1.5

++

Containment Pressure Monitor -

NUREG-0737 Item II.F.1.4 Containment Hydrogen Monitor -

NUREG-0737 Item II.F.1.6

++++

Containment High-Range Radiation Monitor -

NUREG-0737 Item II.F.1.3 CP&L's letter dated April 28, 1982, S. R. Zimmerman to S. A. Varga, provides an acceptable alternate calibration methodology.

S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Q

At least once per 92 days D

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> S/U Prior to each reactor startup if not performed W

At least once per 7 days in the previous seven (7) days B/W -

At least once per 14 days R

At least once per 18 months M

At least once per 31 days N.A. -

Not applicable O

rt 0

I.Q.

UNITED STATES NUCLEAR REGULATORY COMMISSION o '

WASHINGTON, D.C. 205 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 143 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 June 5, 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 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:

-2 B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 143, 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: December 10, 1992