ML18005B036
| ML18005B036 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/31/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18005B037 | List: |
| References | |
| NPF-63-A-012 NUDOCS 8909110212 | |
| Download: ML18005B036 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER 8 LIGHT COMPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 12 License No. NPF-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power
& Light Company (the licensee),
dated April 11,
- 1989, as supplemented June 29,
- 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and
'egulations 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 CoIImIission'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 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 2.C.(2) of Facility Operating License No.
NPF-63 is hereby amended to read as follows:
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(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No. 12, are hereby incorporated into this license.
Carolina Power 5 Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 3l, l989 Elinor G.
- Adensam, Director Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation I
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ATTACHMENT TO LICENSE AMENDMENT NO.
12 FACILITY OPERATING LICENSE NO.
NPF-63 DOCKET NO. '50-400 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Pa es 5-6 5-7 Insert Pa es 5-6 5-7
DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 45.0 psig and a peak air temperature of 380'F.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 157 fuel assemblies with each fuel assembly
-normally containing 264 fuel rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods consisting of Zircaloy-4, stainless
- steel, or by vacancies may be made in fuel assemblies if justified by a cycle"specific evaluation.
Should more than a total of 30 fuel rods or more than 10 fuel rods in any one assembly be replaced per refueling a Special Report describing the number of rods replaced will be submitted to the Commission, pursuant to Specification 6.9.2, within 30 days after cycle startup.
Each fuel rod shall have a nominal active fuel length of 144 inches'he initial core loading shall have a maximum enrichment of 3.5 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.
Fuel with enrichments greater than 4.20 weight percent U-235 shall contain sufficient integral burnable absorbers such that the requirement of Specification 5'.6.1.a.2 is met.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 52 shutdown and control rod assemblies.
The shutdown and rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 80K silver, 15Z indium, and 5X cadmium, or 95K hafnium with the remainder zirconium.
~ All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coo1ant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig,, and c.
.For a temperature of 650'F, except for the pressurizer which is 680'F.
VOLUME 5.4.2 'he total water and steam volume of the Reactor Coolant System is 9410
+ 100 cubic feet at a nominal T
of 588.8'F.
SHEARON HARRIS - UNIT 1 5-6 Amendment No.
$,7,12
DESIGN FEATURES 5.6 FUEL STORAGE CRIT1CALITY 5.6.1.a The spent fuel storage racks are designed and shall be maintained with a k <f less than or equal to 0.95 when flooded with unborated water, which includes an allowance for uncertainties as described in Section 4.3.2.6 of the FSAR.
This is assured by maintaining.'.
A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the PWR storage racks and 6.25 inch center-to-center distance in the BWR storage racks.
2.
The maximum core geometry K
for PWR fuel assemblies less than or equal to 1.470 at 68'F.
5.6.1.b The keff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The new and spent fuel storage pools are designed and shall be main" tained to prevent inadvertent draining of the pools below elevation 277.
CAPACITY 5.6.3 The new and spent fuel storage pools are designed for a storage capacity of 1832 PWR fuel assemblies and a variable number of PWR and BWR storage spaces in 48 interchangeable 7x7 PWR and llxll BWR racks.
These interchangeable racks will be installed as needed.
Any combination of BWR and PWR racks may be used.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The. components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.,
SHEARON HARRIS - UNIT 1 5-7 Amendment No.
12