ML14175A801
| ML14175A801 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/04/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A802 | List: |
| References | |
| DPR-23-A-079 NUDOCS 8404240501 | |
| Download: ML14175A801 (5) | |
Text
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0 UNITED STATES S,
oNUCLEAR 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. 7 9 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 January 11, 1983, 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:
8404240501 840404 PDR ADOCK 05000261 P
-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.79, 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 REGULATORY COMMISSION Operating Reactors ranch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 4, 1984
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
79 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 3.6-1 3.6-1 3.6-2a 3.6-2a
3.6 CONTAINMENT SYSTM Analicability Applies to the integrity of reactor containment.
Obective To define the operating status of the reactor containment for plant operation.
Soecification 3.6.1 Containment Integrity
- a.
The containment integrity (as defined in 1.7) shall not be violated unless the reactor is in the cold shutdown condition.
- b.
The containment integrity shall not be violated when the reactor vessel head is removed unless a shutdown margin greater than 10% Ik/k is constantly maintained.
- c.
Positive reactivity changes shall not be made by rod drive mction when the containment incagrity is not intact except for rod drop tests or disconnecting part length rods, in which case the shutdown margin is maintained >1. dk/k.
- d.
Positive reactivity changes shall not be made by boron dilution when the containment integrity is aot intact unless the shutdown margin is maintained >L k/k.
3.6.2 Tternal ?ressure If the interal pressure exceeds I psi or the internal vacuum exceeds 1.0 psi, the condition shall be corrected within eight (3) hours or the 3.6-1 Amendment No. 79
Regarding internal pressure limitations, the containent design pressure of 42 psig would not be exceeded if the internal pressure before a major loss-of-coolant accident were as much as 2 psig.
The containent is designed to withstand an internal vacuum of 2.0 pai. (2)
References (1)
TSAR Section 14.3.4 (2) FSAR Section 3.1.2.3 Amendment No. 79 3.6-2a