ML14183A163
| ML14183A163 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/21/1990 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A164 | List: |
| References | |
| DPR-23-A-127 NUDOCS 9006260070 | |
| Download: ML14183A163 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
127 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 May 25, 1990, 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:
PER ADOCK o00026-1 P
-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 127, 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 Gus C. Lainas, Assistant Director for Region II Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 21, 1990
ATTACHMENT TO LICENSE AMENDMENT NO. 127 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 marginal lines.
Remove Pages Insert Pages 4.1.-7 4.1-7 4.1-7a
TABLE 4.1-1 (Continued)
Channel Description Check Calibrate Test Remarks
- 21. Containment Sump Level N.A.
R N.A.
- 22. Turbine Trip Logic**
N.A.
N.A.
R
- 23. Accumulator Level and Pressure S
R N.A.
- 24. Steam Cenerator Pressure S
R N
- 25. Turbine First Stage Pressure S
R H
- 26. DELETED
- 27. Logic Channel Testing N.A.
N.A.
M(1)
(1) During hot shutdown and power S/U(2) operations. When periods of reactor cold shutdown and refueling extend this interval beyond one month, this test shall be performed prior to startup.
(2) Logic channel testing for nuclear source range channels shall only be required prior to each reactor startup, if not performed within the previous seven (7) days.
- 28. Turbine Overspeed Protection N.A.
R H
4 MTrip Channel (Electrical)
- 29. 4 Kv Frequency N.A.
R R
O Stop valve closure or low EH fluid pressure.
TABLE 4.1-1 (Continued)
Channel Description Check Calibrate Test Remarks
- 30. Reactor Trip Breakers N.A.
.A.
H()
(1) The reactor trip breaker trip actuating device operational test shall verify the operability of the UV trip attachment and the shunt trip attachment, individually.
- 31. Overpressure Protection System N.A.
R M
3 j
PQ