ML20100A331
| ML20100A331 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/08/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Florida Power Corp, City of Alachua, FL, City of Bushnell, FL, City of Gainesville, FL, City of Kissimmee, FL, City of Leesburg, FL, City of New Smyrna Beach, FL, Utilities Commission, City of New Smyrna Beach, FL, City of Ocala, FL, City of Orlando, FL, Orlando Utilities Commission, Sebring Utilities Commission, Seminole Electric Cooperative, City of Tallahassee, FL |
| Shared Package | |
| ML20100A339 | List: |
| References | |
| DPR-72-A-072 NUDOCS 8412030540 | |
| Download: ML20100A331 (5) | |
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UNITED STATES I
h, NUCLEAR REGULATORY COMMISSION D
E WASHINGTON, D. C. 20555
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES CO MISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMISSION AND THE CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINGLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENE Amendment No. 72 Licente No. DPR-72 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated February 24, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the the provisions of the Act, and the rules.and regulations of the Comission; 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 Comission'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 Comissio:i's regulations and all applicable requirements have been satisfied.
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. 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 Operatino License No. DPR-72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices.
A and B, as revised through Amendment No. 72, are hereby incorporated in the license.
Florida Power Corpcration shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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J n Stolz, hief erftingReactorsBranchNo.4 M sion of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 8, 1984
i ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the. enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Pages 5 5-5 i
4 i
l DESIGN FEATURES l
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' DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 55 psig and a temperature of 2310F.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 177 fuel assemblies with each fuel assembly containing 208 fuel rods clad with Zircaloy - 4. Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 2253 grams uranium. The initial core loading shall have a maximum enrichment of 2.33 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 3.50 weight percent U-235.
'1 CONTROL RODS 5.3.2 The reactor core shall contain 61 safety and regulating and 3 axial power shaping (ASPR) control rods. The safety and regulating control rods shall contain a nominal
.134 inches of absorber material. The APSR's shall contain a nominal 36 inches of absorber material at their lower ends. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmiurn. All control rods shall be clad with stainless steel tubing.
CRYSTAL RIVER - UNIT 3 5-4 Amendment No. Jp, Jp, 72
DESIGN FEATURES 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 4.1.2 of' the -
FSAR, with. allowance for normal degradation pursuant to applicable Surveillance Requirements, b.
For a pressure of 2500 psig, and c.
For a tempe sture of 6500F, except for the pressurizer and pressurizer surge
-line, which is 6700F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,180 1 200 cubic feet at a nominal Tavg of 5250F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The ineteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1, The new fuel storage racks and spent fuel storage racks in pool "B" are designed l
and shall be maintained with a nominal 21-1/8 inch center-to-center distance between fuel assemblies placed in the storage racks. The high density spent fuel storage racks in pool "A" are designed and shall be maintained with a nominal 10.5 l
inch center-to-center distance between fuel assemblies placed in the storage racks.
All of these rack designs ensure a keff equivalent tos0.95 with the storage pool filled with unborated water. The keff ofs0.95 includes a conservative allowance of >1% ak/k for uncertainties. In addition, fuel in the new and spent fuel storage racks shall have a U-235 loading of $ 6.14 grams of U-235 per axial centimeter of 4
fuel assembly (san enrichment of 3.5 weight percent U-235).
DRAINAGE l
5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 138 feet 4 inches, i
4 CRYSTAL RIVER - UNIT 3 5-5 Amendment No. M, 72 t
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DESIGN FEATURES CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maint:.ined with a storage capacity limited to no more than 1153 fuel assemblies and 6 failed fuel containers.
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 :yclic or transient limit of Table 5.7-1.
l CRYSTAL RIVER - Unit 3 5-6 Amendment No. 36 l
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