ML20214P935
| ML20214P935 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/22/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214P936 | List: |
| References | |
| NUDOCS 8706040175 | |
| Download: ML20214P935 (7) | |
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UNITED STATES E.,
NUCLEAR REGULATORY COMMISSION 7,
5
' :l 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 Amendment No. 23 License No. NPF-30 t
i 1.
The Nuclear Regulatory Comission (the Comission) has found that:
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A.
The application for amendment filed by Union Electric Company (the I
licensee) dated December 19, 1986 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized I
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 comon 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 Comission's regulations and all applicable requirements have been satisfied, t
i 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:
8706040175 870522
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PDR ADOCK 05000483 P
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 23, 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 David L. Wigg nton, Acting Project Director Project Directorate III-3 Division of Reactor Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: May 22, 1987
ATTACHMENT TO LICENSE AMENDMENT N0.23 OPERATING LICENSE NO. NPF-30 DOCKET N0. 50-483 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. The corresponding overleaf pages are included to maintain document completeness.
REMOVE INSERT 3/4 9-16 3/4 9-16 5-6 5-6 5-7 5-7 y
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REFUELING OPERATIONS 3/4.9.12 SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.12 Spent fuel assemblies stored in Region 2 shall be subject to the following conditions:
a.
The combination of initial enrichment and cumulative exposure shall 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 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.
CALLAWAY - UNIT 1 3/4 9-15
Above the curve is acceptable for Storage in Region 2 36000
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- w 1.5 2.0 3.0 4.0 FUEL ASSEMBLY INITIAL ENRICHMENT, W/O U-235 FIGURE 3.9-1 MINIMUM REQUIRED FUEL ASSEMBLY BURNUP AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2 i
CALLAW AY - UNIT 1 3/4 9-16 Amendment No. JZ,23
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assenblies with each fuel assembly containing 264 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 1766 grams uranium. The initial core loading shall have a maximum enrichment of 3.10 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.25 weight l
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, 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:
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 + 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
DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 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 eff unborated water, which includes a conservative allowance of 2.6%
ak/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 l
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.
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 designed 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 limited to no more than 1344 fuel assemblies.
5.7 COMP 0NENT 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 Amendnent No. 72, 23
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