ML14175A880
| ML14175A880 | |
| Person / Time | |
|---|---|
| Site: | Robinson |
| Issue date: | 08/26/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A881 | List: |
| References | |
| DPR-23-A-093, DPR-23-A-93 NUDOCS 8509060204 | |
| Download: ML14175A880 (5) | |
Text
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'k 4UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 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. 93 License No. DPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power and Light Company (the licensee) dated April 30, 1985, 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:
8509060204 850826 PDR ADOCK 05000261 p
0 0
-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.93, 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 NUCLEAR EGULATORY COMMISSION e v
- arga, Operating Reactors rJ ch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:August 26, 1985
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
93 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 3.5-10 3.5-10 3.5-11 3.5-11
(HBR-22)
TABLE 3.5-1 ENGINEERED SAFETY FEATURE SYSTEM INITIATION INSTRUMENT SETTINC LIMITS NO.
FUNCTIONAL UNIT CHANNEL ACTION SETTING LIMIT
- 1.
High Containment Pressure (HI Level)
Safety Injection*
< 5 psig
- 2.
High Containment Pressure (HI-HI Level)
- a.
Containment Spray**
< 25 psig
- b.
Steam Line Isolation
- 3.
Pressurizer Low Pressure Safety Injection*
> 1700 psig
- 4.
High Differential Pressure Between any Safety Injection*
< 150 psi Steam Line and the Steam Line Header U
- 5.
High Steam Flow in 2/3 Steam Lines***
- a. Safety Injection*
< 40% (at zero load) of
- b. Steam Line Isolation full steam flow
< 40% (at 20% load) of 0
full steam flow
< 110% (at full load) of full steam flow Coincident with Low T or Low Steam
> 541"F Ta Line Pressure avg
- 600 psigiteam line pressure
- 6.
Loss of Power
- a. 480V Emerg. Bus Undervoltage Trip Normal Supply Breaker 328 Volts +/- 10%
(Loss of Voltage) Time Delay
< 1 sec when voltage is reduced to zero 0
(HBR-22)
TABLE 3.5-1 (Continued)
ENGINEERED SAFETY FEATURE SYSTEM INITIATION INSTRUMENT SETTING LIMITS NO.
FUNCTIONAL UNIT CHANNEL ACTION SETTING LIMIT
- 6.
- b.
480V Emerg. Bus Undervoltage Trip Normal Supply Breaker 415 Volts +/- 4 Volts (Cont'd)
(Degraded Voltage) Time Delay 10.0 Second Delay +/-
0.5 sec.
- 7.
Containment Radioactivity High Ventilation Isolation The alarm is set with a method described in the ODCM.
Initiates also containment isolation (Phase A), feedwater line isolation and starting of all containment fans.
Initiates also containment isolation (Phase B).
Derived from equivalent WP measurements.
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