ML20199L114
| ML20199L114 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/19/1999 |
| From: | Mel Gray NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199L117 | List: |
| References | |
| NUDOCS 9901270130 | |
| Download: ML20199L114 (8) | |
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UNITED STATES g
NUCLEAR RE2ULATORY COMMISSION WASHINGTON, D.C. 30e46 0001
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UNION ELECTRIC COMPANY CALLAWAY PLANT UNIT 1 i
DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.129 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 February 24,1998, as supplemented by letters dated May 27,1998, June 25, 1998, August 25,1998, September 3,1998, November 3,1998, and December 4, 1998, 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 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 i
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 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:
9901270130 990119 PDR ADOCK 05000483 P
PDR l
A i l (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.129 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This amendment is effective as of its date of issuance to be fully implemented no later than December 31,1999, except that the racks in the cask loading pit may be installed at f.- future time after the completion of the next refueling outage. While the spent fuel poi) reracking modification is in progress, both the technical specifications issued through Amendment No.128, and those technical specifications being amended by Amendment No.129 will be applicable.
FOR THE NUCLEAR REGULATORY COMMISSION (di Mel Gray, Project anager Project Directorate IV-2 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 19,1999 i
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i ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.129 TO FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO, 50-483 1
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain verticallines i
indicating the areas of change. The corresponding overleaf paged are also provided to I
maintain document completeness.
REMOVE INSERT 3/4 9-15 3/4 9-15 l
3/4 9-16 3/4 9-16 i
l B 3/4 9-3 B 3/4 9-3 5-6 5-6 5-7 5-7 l
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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 either the Spent Fuel Pool or cask loading pit shall be subject to one of the following conditions:
a.
Spent fuel assemblies regardless of bumup can be placed in Rsgion 1.
b.
Spent fuel assemblies within the 'oumup-enrichment range shown in Figure 3.9-1 for Region 2 fuel shall be placed in Region 2 or 3.
c.
Spent fuel assemblies within the bumup-enrichment range shown in Figure 3.9-1 for Region 3 fuel shall be placed in Region 3.
APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel pool or cask loading pit.
ACTION:
a.
With the requirements of the above specification not satisifed, suspend all other movement of fuel asse.ablies and crane operations with loads in the fuel storage areas and move non-complying fuel assemblies to Regioni. Until the requirements of the above specification are satisifed, 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 Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.12 The bumup of each spent fuel assembly stored in Regions 2 and 3 shall be ascertained by analysis of its burnup history and independently verified prior to storage in Regions 2 or 3. A complete record of such analysis shall be kept for the time period that the spent fuel assembly remains in Regions 2 or 3 of the spent fuel pool or cask loading pit.
CALLAWAY - UNIT 1 3/4 9-15 Amendment No.
FIGURE 3.9-1 MINIMUM REQUIRED FUEL ASSEMBLY BURNUP AS A FUNCTION OF 4
INITIAL ENRICHMENT TO PERMIT STORAGE IN REGIONS 2 AND 3 l
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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)
CALLAWAY - UNIT 1 3/4 9-16 Amendment No. 49:29;6E;469, i
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REFUELiblG OPERATIONS BASES removal capability. With the reactor vessel heat removed and at least 23 feet of water above the reactor vessel flange, a large host sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to coolthe core.
1 3/4 9 9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment purge penetrations will be automatically isolated upon datedion of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
3/4 9.10 and 3/4 9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to reniove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.
3/4 9.12 SPENT FUEL ASSEMBLY STORAGE 1
I The racks for the spent fuel pool and cask loading pit are designed for storage of both l
new fuel and irradiated fuel. Prior to storage of fuel assemblies in either the spent fuel pool or cask loading pit, overall pool storage Regions shall be prepared in accordance with administrative controls. The restrictions placed on fuel assemblies stored in the spent fuel pool and cask loading pit ensure inadvertent criticality will not occur. Region 1 is designed to I
accommodate new fuel with a maximum nominal initial enrichment of 5.0 weight percent U-235, or spent fuel regardless of the discharge fuel bumup. Region 2 and Region 3 are designed to accommodate fuel of various initial enrichments which have accumulated minimum bumups within the acceptable domain according to Figure 3.9-1, in the accompanying LCO.
l 3/4 9.13 EMERGENCY EXHAUST SYSTEM The limitations on the Emergency Exhaust System ensure that all radioactive matcrials released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. Operation of the system with the heaters operating to maintein low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
The OPERAPILITY of this system and the resulting iodine removal capacity are consistent with l
the assumptions of the safety analyses. ANSI N510-1975 will be used as a procedural guide for surveillance testing. ASTM D-3803-1989 will be used as a procedural guide for the laboratory testing of charcoal samples.
CALLAWAY - UNIT 1 B 3/4 9-3 Amendment No. 6t446, l
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES i
5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Zircaloy-4 or Zirlo, except that limited substitution of fuel rods by filler i
rods consisting of Zircaloy-4, stainless steel, or Zirlo may be made if justified by a cycle-specific l
)
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 nominal enrichment of 5.00 weight percent U-235.
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 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.
54 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 l
c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
1 VOLUME 5.4.2 The total volume of the Reactor Coolant System, including pressurizer and surge line, is l
12,135 i 100 cubic feet at a nominal T., of 557'F.
l 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
l i
CALLAWAY - UNIT 1 54 Amendment No. 12,20.24,41,M, 100,110, 4
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l DESIGN FEATURES I
e 5.6 FUEL STORAGE i
CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained:
l a.
With a k,, equivalent to less than or equal to 0.95 when flooded with unborated I
water, which includes an allowance for uncertainties as 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 an acceptable combination of initial enrichment and discharge exposures, shown in Figure 3.9-1 for Region 2 and Region 3, and b.
With a nominal 8.99 inch center-to-center distance between fuel assemblies l
placed in the storage racks, and c.
For fuel with nominal enrichments greater than 4.60 weight percent U-235, the i
combination of enrichment and integral fuel burnable absorbers shall be sufficient so that the requirements of Specification 5.6.1.1.s are met. Integral fuel burnable absorbers are not required for Region 1 rack locations on the periphery of the pool adjacent to a concrete wall.
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.
l DRAINAGE 5.6.2 The fuel storage pool is designed and shaP 's maintained to prevent inadvertent l
draining of the pool below elevation 2040 feet.
CAPACITY I
5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity l
limited to no more than 2363 fuel assemblies. The cask loading pit is designed and shall be l
maintained with a storage capacity limited to no more than 279 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. 12,20,54,102, (Next page is 5-9)
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