ML14183A041
| ML14183A041 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/03/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A042 | List: |
| References | |
| DPR-23-A-099 NUDOCS 8607230100 | |
| Download: ML14183A041 (5) | |
Text
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UNITED STATES 0
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. 99 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 December 11, 1985 as supplemented by letters dated May 1, 1986, June 18, 1986 and June 27, 1986 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:
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-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, 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 Lester S. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
JUL 3 1986
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 3.6-3 3.6-3 3.6-4 3.6-4
3.6.4 Containment Purge and Vent Valves 3.6.4.1 During periods when Containment integrity is required, the Containment Purge Supply and Exhaust Isolation Valves (42") or the Pressure and Vacuum Relief Valves (6") may be opened only for safety related reasons including operational testing and surveillances.
3.6.4.2 When the RCS is greater than 200, the 42" and 6" valves may not be open simultaneously.
3.6.4.3 The 6" and 42" valves will be tested in accordance with the frequency and operability requirements specified in the Robinson plant IST program except that the 42" valves will be tested prior to use if not tested within the previous quarter. Otherwise the 42" valves will not be cycled quarterly only for testing purposes.
Basis The Reactor Coolant System conditions of cold shutdown assure that no steam will be found and hence there would be no pressure buildup in the containment if the Reactor Coolant System ruptures.
The shutdown margins are selected based on the type of activities that are being carried out. The 10% Ak/k shutdown margin during refueling precludes criticality, even though fuel is being moved. When the reactor head is not to be removed, the specified cold shutdown margin of 1% Ak/k precludea criticality.
Regarding internal pressure limitations, the containment design pressure of 42 paig would not be exceeded if the internal pressure before a major loss-of coolant accident were as much as 2 psig. 1' The containment is designed to withstand an internal vacuum of 2.0 pats.
The Containment Purge Supply and Exhaust Isolation Valve may be opened during plant operation when needed for safety related considerations (equipment or personnel) to support plant operations and maintenance activities within the containment vessel. Examples of this need may include the reducing of airborne activity to increase stay-time or eliminate the need for respiratory protective equipment, or reduce ambient temperature during hot months to increase effectiveness of workers and to minimis occupational effects of necessary, non-routine activities in the containment. Although the valves are fully qualified to close under design basis accident conditions, it is intended that the time the valves remain open will be limited.
The Containment Purge Valves must be operable and must close within the time limit specified in the 1T program in order to limit post LOCA thyroid dose and to limit the increase in peak clad temperature due to reduction in containment internal pressure.
The Inboard Purge Supply and Exhaust Isolation Valves are installed so the seal replacement can be performed without removing the valves. This orientation requires that the inboard valves be restricted from exceeding 70" open. This restriction is an antimrotation measure to assure proper valve closure under dynamic conditions, as well a. to limit offtite dose consequences under postulated LOCA conditions.
References (1) FSAR Section 6.2.1 (2) FAR Section 3.8.1.3 3.6-4 Amendment Not 99