ML14183A038
| ML14183A038 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/06/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A039 | List: |
| References | |
| DPR-23-A-098 NUDOCS 8605150181 | |
| Download: ML14183A038 (5) | |
Text
S REGU UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAPOLTNA POWER AND LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. ?
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 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, 1985, as supplemented November 11, 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 I;
- 9. 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 paraqraph 3.B of Facility Operating License No. DPR-23 is hereby amended to read as follows:
860515018 860506 ADOCK 05000261 P
p
-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 98, 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 (As'ILester S. Rubenstein, Director
-lr7 PWR Pro'ect Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: May 6, 1986
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
98 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 2.1-3 2.1-3 2.1-4 2.1-4
g(HBR-27) are set to preclude bulk boiling at the vessel exit. An arbitrary upper safety limit of 118% thermal power is shown. This limit is based on the high flux trip including all uncertainties.
Radial power peaking factors consistent with the limit on FAH given in Specification 3.10.2.1 have been employed in the generation of the curves in Figure 2.1-1. An additional heat flux factor of 1.03 has been included to account for fuel manufacturing tolerances and in-reactor densification of the fuel.
The safety limit curves given in Figure 2.1-1 are based on a minimum RCS flow of 97.3 x 106 lbm/hr. These curves would not be applicable in the case of a loss of flow transient. The evaluation of such an event would be based upon the analysis presented in Section 15.3 of the FSAR.
The Reactor Control and Protection System is designed to prevent any anticipated combination of transient conditions for Reactor Coolant System temperature, pressure, and thermal power level that would result in a DNB ratio of less than 1.17(2) based on steady state nominal operating power levels less than or equal to 100%, steady state nominal operating Reactor Coolant System average temperatures less than or equal to 575.4'F, and a steady state nominal operating pressure of 2235 psig.
Allowances are made in initial conditions assumed for transient analyses for steady state errors of
+2% in power, +4*F in Reactor Coolant System average temperature, and +/-30 psi in pressure. The combined steady state errors result in the DNB ratio at the start of a transient being 10 percent less than the value at nominal full power operating conditions.
References (1) XN-NF-711(P)
Rev.
0, "KbN Addendum for 26 Inch Spacer."
(2) FSAR Section 15.
2.1-3 Amendment No.
F7, 98
0404 a4.0HIGH PLUX TAIP AT 118% OF jRATED P01YER tooo0 o
$00BN OF *30 A Figur e.1*
44 wso 520 8004
-I1 20 to0 s0 so 100 PERCENT OF 2300 MWT COpt pnOTSCTION BDOUNDARIES FOR
- -LOOP OPERATION Figure 9.1-1 NOTE:
BASED ON A XEHIMUM RCS FLOW OF 97.3 x 10b6 lbm/hr 2.1-4 Amendment No. 07, 98