ML14183A301
| ML14183A301 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/17/1995 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A302 | List: |
| References | |
| DPR-23-A-159 NUDOCS 9503230269 | |
| Download: ML14183A301 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 159 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 December 27, 1994, 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:
9503230269 950317; PDR ADOCK 0500026b1 PP PDR
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 159, 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 and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION William H. Bateman, Director Project Directorate II-1 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 17, 1995
ATTACHMENT TO LICENSE AMENDMENT NO. 159 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 4.1-13 4.1-13
-TABLE 4.1-3 (Continued)
FREQUENCI-ES FOR __EaUIPMENT TES Maximum Time Check Frequency Between Test
- 13.
Deleted
- 14.
Fans and Fans functioning.
Once per operating NA associated Laboratory tests cycle.
charcoal and on charcoal must Absolute show a 99% iodine Filters for removal. In-place Residual Heat test must show Removal t 99% removal of Compartments polydispersed DOP (HVE-5a and5b) particles by the HEPA filters and Freon by the charcoal filters.
- 15.
Isolation Seal Functioning Each refueling NA Water System shutdown
- 16.
Overpressure Functioning Each refueling NA Protection shutdown System
- 17.
Primary Coolant Functioning
- 1.
Periodic leakage System check testing (a on each valves (cOvalve listed in Table 3.1-1 shall be accomplished prior to entering reactor operation condition (1) after every time the plant is placed in the cold shutdown condition for refueling, (2) after each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, (3) after maintenance, repair or replacement work is performed.
(a) To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.
Minimum test differential pressure shall not be less than 150 psid.
More than one valve may be tested in parallel. The combined leakage shall not exceed 5.0 gpm. Redundant valves in each line shall not be tested in series.
4.1-13 Amendment No. 159