ML14183A084
| ML14183A084 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/30/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A085 | List: |
| References | |
| DPR-23-A-111 NUDOCS 8701120050 | |
| Download: ML14183A084 (5) | |
Text
SREG UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER AND LIGHT COMPANY DOCKET NO. 50-?61 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. ?
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 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 August 28, 1986, and application dated September 9, 1986 as supplemented by letter dated November 25, 1986 comply 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 CFP Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and reaulations 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 reauirements have been satisfied.
- 2. Accordinaly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-23 is hereby amended to read as follows:
9701120050 861230 PDR ADOCK 05000261 P-R
-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 111, 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 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 3Q, 1986
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 111 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 3.3-4 3.3-4 6.13-1 6.13-1
(HBR-37) valves, are not subject to the requirements of this specification.
Power or air supply may be restored to any valve referenced in 3.3.1.1.g. and 3.3.1.1.h. for the purpose of-Valve testing or maintenance providing no more than one valve has power restored and provided that testing and maintenance is completed and power removed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except. for accumulator isolation valves (MOV 865 A,B,&C) which will have this time period limited to four hours.
3.3-4 Amendment No.
07, 111
(HBR-38) 6.13 AIGH RADIATION AREA 6.13.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20:
- a.
Each High Radiation Area in which the intensity of radiation is greater than 100 mr/hr, but equal to or less than 1000mr/hr when measured at 18 inches from a source within the area, shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Work Permit.
Any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation exposure rate.
- b.
Each High Radiation Area in which the intensity of radiation is greater than 1000 mr/hr when measured at 18 inches from a source within the area shall be subject to the provisions of 6.13.1(a) above. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or the Radiation Control Foreman.
6.13-1 Amendment No. 70,111