ML14183A052
| ML14183A052 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 08/25/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A053 | List: |
| References | |
| DPR-23-A-102 NUDOCS 8609180410 | |
| Download: ML14183A052 (4) | |
Text
V REGqj UNITED STATES 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. 102 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 September 12, 1985, 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 1; 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 Par 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:
8609180410 86O825 PDR ADOCK 05000261 P
-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. In addition, Facility Operating License DPR-23 is amended as follows:
(A) Delete paragraph 3.J.
- 4. 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: August 25, 1986
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 102 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 3.4-3 3.4-3
Ba s: s A reactor shutdown from power requires removal of core decay heat.
Immediate decay heat removal requirements are normally satisfied by the steam bypass to the condenser. Therefore, core decay heat can be continuously dissipated via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorption.
Normally, the capability to return feedwater flow to the steam generators is provided by operation of the turbine cycle feedwater system.
The twelve main steam safety valves have a total combined rated capability of 1.022 x 10 lbs/hr. The total full power steam flow is 1.011 x 107 lbs/hr.;
therefore, twelve (12) main steam safety valves will be able to relieve the total steam flow if necessary. )
Following a loss of load, which represents the worst transient, steam flows are below the total capacity of the 12 safety valves.
Therefore, over-pressurization of the secondary system is not possi I ble.
In the unlikely event of complete loss of turbine-generator and offsite electrical power to the plant, decay heat removal would continue to be assured by the availability of either the steam-driven auxiliary feedwater pump or one of the two mctor-Lriven auxiliary steam generator feedwater pumps operated from the diesel generators and steam discharge to the atmosphere via the main steam safety valves and atmospneric relief valves.
One motor-driven auxiliary.
feedwater pump can. supply su ficient feedwater for removal of decay heat frcm.
the plant.(2)
The auxiliary feedwater system essential features are those features that provide auxiliary feedwater flow to two out of three steam generators consistent with auxiliary feedwater pump operability.
In order to' provide a high degree of reliability all three auxiliary feedwater pumps wil'.
be operable prior to exceeding 350*F. The minimum amount of water in the condensate storage tank is the amount needed for at least two hours operation at hot standby conditions.
If the outage is more than two hours, deep well or Lake Robinson.water may be used.
An unlimited supply is available from the lake via either leg of the plant Service Water System for an indefinite time period.
3.4-3 Amendment No. 75,102