ML20235K981
| ML20235K981 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/14/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235K984 | List: |
| References | |
| NUDOCS 8902270328 | |
| Download: ML20235K981 (5) | |
Text
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION ri 4
j WASHINGTON, D. C. 20555
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l UNION ELECTRIC COMPANY CALLAWAY PLANT, UhlT 1 I
DOCKET NO. STN 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No. NPF-30 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for an.m...ent filed by Union Electric Company (UE,thelicensee)datedDecember 16, 1988, 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 Comission;.
C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in conipliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendnient is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-4 graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
8902270328 8902M hDR ADOCK 03 coo 4gg PDC
(2) Technical Specifications and Environment'al Protection Plan The Technical Specifications contained in Appendix A, as. revised.
through Amendment No. 41, 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 J
Protection Plan.
I 3.
This license amendment.is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$V
& John N.Hannon, Director Project Directorate'III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
.Date of Issuance: February 14, 1989 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 41 OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains marginal lines indicating the area of change. The corresponding overleaf.page is provided to maintain document completeness.
REMOVE
. INSERT 5-6 5-6
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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 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 shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.25 weight percent U-235.
CONTROL R0D ASSEMBLIES-5.3.2 The core shall contain 53 full-length and no part-length control rod
- assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. All control rods shall be hafnium, silver-indium-cadmium, or a mixture of both types. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE
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5.4.1 The Reactor Coolant 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.
l 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 Tavg of 557*F.
- 5. 5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
i CALLAWAY - UNIT 1 5-6 Amendment No. J2,23,2A, 41
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DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
A kfff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance of 2.6%
ok/k for uncertainties as described in Section 4.3 of the FSAR..
This is based on new fuel with an enrichment of 4.25 weight percent
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U-235 in Region 1 and on spent fuel with combination of initial enrichment and discharge exposures, shown in Figure 3.9-1, in
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Region 2, and j
b..
A nominal 9.24 inch center-to-center distance between fuel' assemblies placed in the storage racks.
- 5. 6.1. 2 The k,7f for new fuel for the first core loading stored dry in the l
spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is
- assumed, i
DRAINAGE 5.6.2 The spent fuel storage pool is' designed and shall be maintained to prevent inadvertent draining of the pool below elevation 2040 feet.
t CAPACITY 5.6.3-The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1344 fuel assemblies.
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.
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CALLAWAY - UNIT 1 5-7 Amendment No. 72, 23 (Next page is 5-9) i
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