ML14183A202
| ML14183A202 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/27/1991 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A203 | List: |
| References | |
| DPR-23-A-136 NUDOCS 9110040161 | |
| Download: ML14183A202 (4) | |
Text
REGt0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. R. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPEPATING LICENSE Amendment No. 136 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 September 18, 1991, as supplemented September 18, 1991, and September 23, 1991, complies with the standards and requirements of the Atomic Eneray 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 chanqes 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:
9110040161 910927 PDR ADOCK 05000261 PDR
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 136, 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 11-1 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 27, 1991
ATTACHMENT TO LICENSE AMENDMENT NO. 136 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 marinal lines.
Remove Pages Insert Pages 3.5-15 3.5-15
TABLE 3.5-3 (Continued)
INSTRUMENTATION OPERATING CONDITIONS FOR ENGINEERED SAFETY FEATURES 3
2 OPERATOR ACTION MINIMUM MINIMUM IF CONDITIONS OF CHANNELS DEGREE OF COLUMN I OR 2 NO.
FUNCTIONAL UNIT OPERABLE REDUNDANCY CANNOT BE MET
- 2.
- a.
Manual*
2 0**
Cold Shutdown
- b. High Containment Pressure*
2/set I/set Cold Shutdown (Hi-i Level) t i
- 3.
LOSS OF POWER
- a. 480V Emerg. Bus Undervoltage 2/bus(a)
I/bus(b)
Main Hot Shutdownd)
(Loss of Voltage)
- b.
480V Emerg. Bus Undervoltage 2/bus I/bus Maintain Hot Shutdown(c)
(Degraded Voltage)
- Also initiates a Phase B containment isolation.
- Must actuate two switches simultaneously.
C***
When primary pressure is less than 2000 psig, channels may be blocked.
When primary temperature Is less than 547"F, channels may be blocked.
In this case the 2/3 high steam flow is already in the trip mode.
2 (a) During testing and maintenance of one channel, may be reduced to I/bus.
0 (b) During testing and maintenance of one channel, may be reduced to 0/bus.
(c) The reactor may remain critical below the power operating conditions with this feature inhibited for the purpose of starting reactor coolant pumps.
(d) A one-time-only exception is granted that allows power operation to continue with the actuation C11 circuitry of this Specification declared inoperable due solely to the inability of the surveillance procedure for TS Table 4.1-1, Item 32a and TS 4.6.1.2 to separately assess operability of each of the two channels of the affected circuits.
The duration of this exception is limited to the first outage of sufficient length which allows performance of a surveillance test which adequately tests the affected circuits but not later than Refueling Outage 14.