ML20211E178
| ML20211E178 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  (DPR-072) |
| Issue date: | 10/14/1986 |
| 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 | |
| ML20211E182 | List: |
| References | |
| DPR-72-A-092 NUDOCS 8610220373 | |
| Download: ML20211E178 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D. C. 20555 5
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF-KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINOLE ELECTRIC COOPERATIVE, INC._
CITY OF TALLAHASSEE DOCKET N0. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICEhSE Amendment No. 92 License No. DPR-72 k
1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated December 10, 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; 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 l
been satisfied, fhR10220373 e61014 ADOCK 05000302 p
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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 Operating 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. 92, are hereby incorporated in the license. Florida Power Corporation 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 oh tolz, Director '
PWR Project Directorate
- ision of PWR Licensi
-B
Attachment:
Changes to the Technical
(
Specifications Date of Issuance: October 14, 1986
o ATTACHMENT TO LICENSE AMENDMENT N0.92 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET N0. 50-302 Replace.the following pages of the Appendix "A" Technical Specifications with the attached pasas. 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.
Remove Insert 5-4 5-4 5-5 5-5 i
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l DESIGN FEATURES 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 281*F.
5.3 nr wToR cone 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 essre loading shall have a maximum enrichment of 2.83 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.0 (nominal) weight percent U-235.
l QMtTROL RODS 5.3.2 The reactor core shall contain 60 safety and regulating and 8 axial power shaping (APSR) control rods. The safety and regulating control rods shall contain a nominal 134 inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing. The APSRs shall contain a nominal 63 inches of absorber material at their lower ends. The absorber material for the APSRs shall be 100% Iconel.
L.
CRYSTAL RIVER - UNIT 3 5-4 Amendment N0. M, M, 77, 77,92
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DESIGN FEATURES 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
In accordance with the code requirements specified in Section 4.1.2 of the a.
FSAR, with allowance for normal degradation pursuant to applicable Surveillance Requirements.
b.
For a pressure of 2500 psig, and c.
For a temperature of 650*F, except for the pressurizer and pressurizer surge line, which is 670*F.
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 525'F.
5.5 METEORLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The dry storage racks and the spent fuel storage racks in pool *B" are designed 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 inch center-to-center distance between fuel assemblies placed in the storage racks.
All of these rack designs ensure a keff equivalent to 1 0.95 with the storage pool filled with unborated water.
The keff of I 0.95 includes a conservative allowance of >1t AK/x for uncertainties.
In addition, fuel stored in pool
'A' shall have a U-235 loading of I 46.14 grams of U-235 per axial centimeter of fuel assembly (I an enrichment of 3.5 weight percent U-235). Fuel stored in the dry storage racks and pool *B' shall have a U-235 loading of 1 52.73 (nominal) grams of U-235 per axial centimeter of fuel assembly (I an enrichment of 4.0 (nominal) weight percent U-235).
DRAINAGE 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.
CRYSTAL RIVER - UNIT 3 5-5 Amendment No. M, 77, 92
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DESIGN FEATURES CAPACITY The spent fuel storage pool is designed and shall be mainttined with a storage capacity limited to no more than 1153 fuel assemblies and 5.6.3 6 failed fuel containers.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT _
The component!s identified in Table 5.7-1 are designed and shall be
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5.7.1 maintained within the cyclic or transient limit of Table 5.7-1.
Amendment No. 36 5-6 CRYSTAL RIVER - Unit 3 b
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