ML14183A244

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Amend 145 to License DPR-23,adding Requirement to Calibr AFW Flow Instrumentation at Refueling Outages & Deleting Requirement for Separate Functional Test on Refueling Outage Interval
ML14183A244
Person / Time
Site: Robinson 
Issue date: 03/12/1993
From: Jeffrey Mitchell
Office of Nuclear Reactor Regulation
To:
Shared Package
ML14183A245 List:
References
DPR-23-A-145 NUDOCS 9303160176
Download: ML14183A244 (4)


Text

tpkREGU UN SUNITED STATES a1 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. 145 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 November 20, 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:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

, are hereby incorporated in the license.

Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

9303160176 930312 pDR ADOCK 50oO0261 PDR

0

-2

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 Jocelyn A. Mitchell, Acting 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: March 12, 1993

0~

0 ATTACHMENT TO LICENSE AMENDMENT NO. 14 5 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 4.1-8 4.1-8

TABLE 4.1-1 (Continued)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Description Check Calibration Test Remarks

32.

Loss of Power

a.

480 Emerg. Bus N.A.

R R

Undervoltage (Loss of Voltage)

b.

480 Emerg. Bus N.A.

R R

Undervoltage (Degraded Voltage)

33.

Auxiliary Feedwater Flow****

M R

N.A.

Indication

34.

Reactor Coolant System**

M R

N.A.

Subcooling Monitor

35.

PORV Position Indicator***

N.A.

N.A.

R

36.

PORV Blocking Valve***

N.A.

N.A.

R Position Indicator

37.

Safety Relief Valve Position***

N.A.

N.A.

R Indicator

38.

Noble Gas Effluent Monitors*****

D R

Q

a.

Main Steam Line Instrument for Detection of Inadequate Core Cooling - NUREG 0578 Item 2.1.3.b.

Direct Indication of Power Operated Relief Valve and Safety Valve Position - NUREG 0578 Item 2.1.3.a.

Auxiliary Feedwater Flow Indication to Steam Generator - NUREG 0578 Item 2.1.7.b.

Noble Gas Effluent Monitors -

NUREG-0737 Item II.F.1.1.

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