ML14175A652
| ML14175A652 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/22/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A653 | List: |
| References | |
| DPR-23-A-052 NUDOCS 8011130028 | |
| Download: ML14175A652 (6) | |
Text
O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 0
CAROLINA POWER AND LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. DPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The applications for amendment by Carolina Power and Light Company (the licensee) dated September 19, October 7, and October 17, 1980 comply 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.
8O~ 8o~0
-2
- 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. 52, are hereby incorporated in the license. The licensee 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 NUCL R REGULATORY COMMISSION even. Varga, Chief Operating Reacto Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 22, 1980
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 52 TO FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 3.5-7A 3.5-7A 3.5-10A 3.5-10A 4.1-6A 4.1-6A
Tr. la 3.5-1.(Contiea;d)
EIGINEERED SAFETY Fr.A.TURE SYSTEM INITIATION INSTRUMENT SETTING LIMITS NO.
FUNCTIONAL UNIT CHANNEL ACTION SETTING LIMIT 6
Loss of Power
- a.
480V Emerg. Bus Undervoltage Trip Breaker 328 Volts + 1 volt (Loss of Voltage)
Tiume Delay
.75 +.25 sec.
- b.
480V Emerg. Bus Undervoltage Trip Breaker 412 Volts + 1 volt a
(Degraded Voltage)
Time Delay 10.0 Second Delay + 0.5 secl ro CD C
0
- O
TA"LE 3.5-3 (Continued) 3 1
2 OPERATOR ACTION MINIMUM MINIMUM IF CONDITIONS OF CHANNELS DEGREE OF COLUMN I OR 2 NO.
FUNCTIONAL UNIT OPERABLE REDUNDANCY CANNOT BE MET 3
Loss of Power (a)
(b)
- a.
480V Emerg. Bus 2/Bus 1/Bus Maintain Hot Shutdown Undervoltage (Loss of Voltage)
- b.
480V Emerg. Bus 2/Bus 1/Bus Maintain Hot-Shutdown Undervoltage (Degraded Voltage)
Lji 0
Z (a) During testing and maintenance of one channel may be reduced to 1/Bus.
(b) During testing and maintenance o-f one channel may be reduced to zero.
(c) The reactor may remain critical below the Power Operating Condition with this feature inhibited for the purpose of starting Reactor Coolant Pumps.
TABLE 4.1-1 (Continued)
NO.
CHANNEL DESCRIPTION CHECK CALIBRATE TEST REMARKS 32 Loss oft Power
- a. 480V Emerg. Bus NA R
R Undervoltage (Loss of Voltage)
- b.
480V Emerg. Bus NA R
R Undervoltage (Degraded Voltage)