ML14183A289
| ML14183A289 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 01/05/1995 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A290 | List: |
| References | |
| DPR-23-A-156 NUDOCS 9501110405 | |
| Download: ML14183A289 (6) | |
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. 156 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 July 28, 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:
9501110405 950105 PDR ADOCK 05000261 P
PER
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 156, 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 illiam H. B an, 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:
January 5, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 156 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 5.3-1 5.3-1 5.4-1 5.4-1 5.4-2 5.4-2
5.3 REACTOR
.0 5.3.1 REACTOR CORE 5.3.1.1 The reactor core contains approximately 68 metric tons of uranium in the form of natural or slightly enriched uranium dioxide pellets. The pellets are encapsulated in Zircaloy-4 tubing to form fuel rods which are all pre-pressurized. The reactor core is made up of 157 fuel assemblies. Each fuel assembly contains 204 fuel rod.locations occupied by rods consisting of natural or slightly enriched uranium pellets, solid inert materials, or a combination of the aforementioned.('
5.3.1.2 Deleted 5.3.1.3 Reload fuel will be similar in physical design to the initial core. The enrichment of reload fuel will be no more than 4.95 + 0.05 (nominal 4.95) weight percent of U-235.
5.3.1.4 Deleted 5.3.1.5 There are 45 full-length RCC assemblies in the reactor core. The full-length RCC assemblies contain 144-inch segments of silver indium-cadmium alloy clad with stainless steel.(')
5.3.1.6 Deleted 5.3.2 REACTOR COOLANT SYSTEM 5.3.2.1 The design of the Reactor Coolant System complies with the code requirements.(3) 5.3-1 Amendment No. 104,112,12,15(
5.4 FUEL STORE 5.4.1 SPENT FUEL PIT The new and spent fuel pit structures are designed to withstand the anticipated earthquake loadings as Class I structures. The spent fuel )pit has a stainless steel liner to ensure against loss of water.'
5.4.2 CRITICALITY 5.4.2.1 NEW FUEL STORAGE RACKS Due to the new fuel storage rack design, a nominal 21-inch center-to-center distance is maintained between fuel assemblies.
To permit storage of fuel with a maximum assembly axial plane enrichment of 4.95 + 0.05 (nominal 4.95) weight percent U-235, additional separation is maintained by use of the storage rack securedlocation restrictions below12" in order to establish a geometry which ensures that keff is less than 0.95 assuming that new fuel storage racks are flooded with unborated water and which assures that keff is less than 0.98 in an optimum moderation event.
The secured location restrictions provide fuel storage locations which are secured to prevent fuel storage in those locations.
Secured Location Restrictions:
C4,5,6,7,8,9 / D4,5,8,9 / E4,5,8,9 / F1,4,5,8,9 / G1,4,5.8,9 H1,4,5,6,7,8,9 / J1 / K1 5.4-1 Amendment No. $1,112,129,156
.5.4.2.2 SPENT FU STORAGE PIT A combination of nominal assembly spacing, neutron absorber material between the assemblies, and restrictions on fuel design, integral burnable absorber content, reconstitution, and storage, is required to assure that keff is maintained less than 0.95 when the spent fuel storage pit is flooded with unborated water based on a maximum assembly planar enrichment of 4.95 + 0.05 (4.95 nominal) weight percent U 5.
Fuel assemblies with maximum planar enrichments greater than F55 + 0.05 (4.55 nominal) weight percent U235 have requirements for minimum integral burnable absorber content. (2 5.4.3 BORON CONCENTRATION - SPENT FUEL STORAGE PIT The spent fuel storage pit is filled with borated water at a concentration of greater than or equal to 1500 ppm during refueling operations or new fuel movement in the spent fuel storage pit. This minimum boron concentration ensures subcriticality under worst case design events.
5.4.4 STORAGE CAPACITY - SPENT FUEL STORAGE PIT The spent fuel storage pit provides a storage location for 544 fuel assemblies.
Reference (1) FSAR Section 9.1 (2) EMF-94-113, "H. B. Robinson New and Spent Fuel Criticality Analysis,"
July 1994, Siemens Power Corporation.
5.4-2 Amendment No. 112,11%,156