ML20111B392
| ML20111B392 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/30/1996 |
| From: | Thomas K NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20111B393 | List: |
| References | |
| NUDOCS 9605140396 | |
| Download: ML20111B392 (7) | |
Text
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>R MG UNITED STATES NUCLEAR REGULATORY COMMISSION If WASHINGTON, D.C. 20066-4001
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UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 License No. NPF-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Union Electric Company (UE, the licensee) dated September 6,1995, as supplemented by letters dated January 30, 1996, March 27, 1996, and April 2, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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 asundment 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 been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Speci-fications 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:
80 DON OIO 3
- (2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.109 and the Environmental Protection Plan contained in Aspendix B, are hereby incorporated in the license.
The licensee siall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION MsMN Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 30,1996 l
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 109 TO FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 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 areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 9-15*
3/4 9-15 3/4 9-16 3/4 9-16 5-6 5-6 5-7 5-7
- No changes were made to this page. Reissued as an overleaf page.
l
l REFUELING OPERATIONS
>3/4.9.12 SPENT FUEL ASSEMBLY STORAGE l
l LIMITING CONDITION FOR OPERATION l
3.9.12 Spent fuel assemblies stored in Region 2 shall be subject to the l
following conditions:
a.
The combination of initial enrichment and cumulative exposure shall j
l be within the acceptable domain of Figure 3.9-1, and b.
No spent fuel assemblies shall be placed in Region 2, nor shall any storage location be changed in designation from being in Region 1 to l
being in Region 2, while refueling operations are in progress.
APPLICABILITY:
Whenever irradiated fuel assemblies are in the spent fuel pool.
ACTION:
a.
With the requirements of the above specification not satisfied, suspend all other movement of fuel assemblies and crane operations with loads in the fuel storage areas and move the non-complying fuel assemblies to Region 1.
Until these requirements of the above specification are satisfied, boron concentration of the spent fuel pool shall be verified to be greater than or equal to 2000 ppm at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.12 The burnup of each spent fuel assembly stored in Region 2 shall be ascertained by analysis of its burnup history and independently verified, prior to storage in Region 2.
A complete record of such analysis shall be kept for the time period that the spent fuel assembly remains in Region 2 of the spent fuel pool.
l l
CALLAWAY - UNIT 1 3/4 9-15
FIGURE 3.9-1 MINIMUM REQUIRED FUEL ASSEMBLY BURNUP AS A FUNCTION OF INITIAL ENRICMENT TO PERMIT STORAGE IN REGION 2 45000- :" " " " " i " " " " "." " " " " ";" " " " " t " " " " " " " " " " ";" " " " " ~ i 48000- :***
i- *
-i ADOVE THE CURVE l$ ACCEPTABLE 9 35000-
- 4
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i ora /V-5 FUEL-2 g
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- E v 30000-1 j
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x 25000-. ' ' ' ' ' ' ' ' ' ~.
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STANDARD FUEL o
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2 15000- :-
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.r SELOW THE CURVE IS NOT ACCEPTABLE t
5000--.--..
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1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 FUEL ASSEMBLY INITIAL ENRICHMENT, W/O U-235 i
4 i
CALLAWAY - UNIT 1 3/4 9-16 Amendment No. 12,23 "2,109 i
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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 5.00 weight percent U-235.
Fuel with enrichments greater than 4.10 weight percent of U-235 shall contain sufficient integral fuel burnable absorber such that the requirements of Specification 5.6.1.1 are met.
i CONTROL ROD 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 1
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 5.4.1 The Reactor Coolant System is designed and shall be maintained:
In accordance with the Code requirements specified in Section 5.2 of a.
the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and For a temperature of 650*F, except for the pressurizer which is c.
680*F.
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VOLUME 5.4.2 The total volume of the Reactor Coolant System, including pressurizer and surge line, is 12,135 i 100 cubic feet at a nominal T, of 557'F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
1 CALLAWAY - UNIT 1 5-6 Amendment No. 12,23,24,41,54,109
DESIGN FEATURES 1
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
equivalent to less than or equal to 0.95 when flooded with A k,,, ted water, which includes an allowance for uncertainties as a.
unbora described in Section 9.1 of the FSAR. This is based on fresh fuel with the maximum initial enrichment of U-235 in Region 1 and on spent fuel with combination of initial 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, and c.
A maximum reference fuel assembly K. less than or equal to 1.480 at l
68'F for storage in Region 1.
5.6.1.2 The k,,, 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 spent fuel storage pool is designed and shall be uaintained te prevent inadvertent draining of the pool below elevation 2040 feet.
I 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.
CALLAWAY - UNIT 1 5-7 Amendment No. 12,23,54,109 (Next page is 5-9)
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