ML20215E683
| ML20215E683 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/08/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215E684 | List: |
| References | |
| NUDOCS 8706220058 | |
| Download: ML20215E683 (6) | |
Text
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[4 g 'a j, UNITED STATES p
NUCLEAR REGULATORY COMMISSION r,,
WASHINGTON, D C. 20555
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UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. STN 50-483 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 24 License No. NPF-30 i
f 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment filed by Union Electric Company (the licensee) dated March 27, 1987, 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 provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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; i
D.
The issuance of this amendment will not be inimical to the comon
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l 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 t
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-30 is hereby amended to read as follows:
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, (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through' Amendment No.24, and the Environmental Protection Plan contained.in Appendix B, both of which are attached hereto, are hereby incorporated into the license.
UE 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
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David L.
igginton, Acting Project Director Project Directorate III-3 Division of Reactor Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: June 8, 1987
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s ATTACHMENT TO LICENSE AMENDMENT N0. 24 OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 i
Revise. Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by a
the captioned amendment number and contains marginal lines indicating the area of change. The corresponding overleaf page is included to maintain document completeness.
1 REMOVE INSERT 5-6 5-6
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i DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 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 or stainless steel or by vacancies may be made if justified by a cycle-specific reload j
analysis.
Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 1766 grams uranium.
Reload fuel all be similar in physical design to the initial core loading and shall have u maximum enrichment of 4.25 weight percent U-235.
l CONTROL R0D ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control rod
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assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. All control rods shall be hafnium, clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is 'esigned 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 The total volume of the Reactor Coolant System, including pressurizer and surge line, is 12,135 1 100 cubic feet at a nominal T,yg of 557*F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
CALLAWAY - UNIT 1 5-6 Amendment No. J2, 23,24
I DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY
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5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
Ak equivalent to less than or equal to 0.95 when flooded with gff unborated water, which includes a conservative allowance of 2.6%
ak/k for uncertainties as described in.Section 4.3 of the FSAR.
l This is based on new fuel with an enrichment of 4.25 weight percent l
l U-235 in Region 1 and on spent fuel with combination of initial l
enrichment and discharge exposures, shown in Figure 3.9-1, in Region 2, and b.
A nominal 9.24 inch center-to-center distance between fuel assemblies placed in the storage racks.
1 5.6.1.2 The k for new fuel for the first core loading stored dry in the eff spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is de igned and shall be maintained to prevent inadvertent draining of the pool below elevation 2040 feet.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limiteo to no more than 1344 fuei assemblies.
5.7 COMP 0NENT CYCLIC OR TRANSIENT LIMIT
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5.7.1 The components identified in Table 5.7-1 are designed and shall be i
maintained within the cyclic or transient limits of Table 5.7-1.
I CALLAWAY - UNIT 1 5-7 Amendment No. J2, 23-i
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