ML20043C037
| ML20043C037 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 05/25/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043C038 | List: |
| References | |
| NUDOCS 9006010230 | |
| Download: ML20043C037 (7) | |
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g UNITED STATES 3
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CALLAWAY PLANT, UNIT 1 DOCKET NO. STN 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.54-License No. NPF-30 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment filed by Union Electric Company (UE, the licensee) dated December 28, 1989, supplemented by a letter dated March 6, 1990, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and l
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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have l
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-
- graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to -
l read as follows:
L 9006010230 90032" poa noock osooogs3 PDC l
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- 1 (2) 1pchnical Specificatjons_and_Enyj,ronmental Protection, Plan The Technical Specifications contained in Appendix A, as revised through Amendment No,54, 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 John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation 4
Attachment:
Changes to the Technical Specific 6tions Date of Issuance: May 25, 1990 l
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ATTACHMENT TO LICENSE AMENbMENT NO. 54 OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications b*.: moving the pages identified below and inserting the enclosed pages. Tht U :ised pages are identified by the captioned amendment number and contain merginal lines indicating the area of change. Corresponding overleaf pages are provided'to maintain document' completeness,
. REMOVE INSERT B 3/4 9-1 B 3/4 9-1 5-6 5-6 5-7 5-7 i.
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4 3/4.9 REFUELING OPERATIONS BASES m
3/4.9.1 BORON CONCENTRATION (1) the reactor will remain suberitical during CORE i
uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.
The limitation on K of nogreaterthan0.95issufficienttopreventreactorcriticalitydurinlff refueling operations.
The locking closed of the required valves during.
of the filled portions of the Reactor Coolant System flow to the RCS of unborated water by closing flow paths from sources of unborated water.
assumed for the boron dilution incident in the safety analys 3/4.9.2 INSTRUMENTATION redundant monitoring caThe OPERABILITY of the Source Range Neutron condition of the core. pability is available to detect changes in the reactivity 3/4.9.3 DECAY TIME i
The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that has elapsed to allow the radioactive decay of the short-lived fission produ This decay time is consistent with the assumptic7s used in the fuel ha accident radiological consequence and spent fuel pool thermal-hydra 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and will be restricted from leakage to the environment. OPERABI The OPERABILITY and closure restrictions are sufficient to restrict radioactive materi from a fuel element rupture based upon the lack' of containment pressurizatio potential while in the REFUELING MODE.
will be automatically isolated upon detection of high ra containment.
release of radioactive materials from the containment atmo l
environment.
The restriction on the setpoint for GT-RE-22 and GT-RE-33 is based on a fuel handling accident inside the Containment Building with resulting dama i
to one fuel rod and subsequent release of 0.1% of the noble gas gap activit except for 0.3% of the Kr-85 gap activity.
uCi/cc is equivalent to approximately 150 mR/hr submersion dose rate.The 3/4.9.5 COMMUNICATIONS station personnel can be promptly informed of significant facility status or core reactivity conditions during CORE ALTERATIONS.
CALLAWAY - UNIT 1 B 3/4 9-1 Amendment No. /t0',54
p REFUELING OPERATIONS BASES 3/4.9.6 REFUELING MACHINE-
- The OPERABILITY requirements for the refueling machine and auxiliary hoist ensure that:
(1) manipulator cranes will be used for movement of drive rods and fuel' assemblies, (2) each crane has sufficient load capacity to lift a drive-rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL'- SPENT FUEL STORAGF FACILITY f
The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool areas ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in a single fuel assembly, and. (2) any possible distortion of fuel in the storage racks will not result in a critical array. This' assumption is consistent with the activity release assumed in the safety analyses.
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that:
(1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140*F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and c
prevent boron stratification.
The requirement to maintain a 1000 gpm flowrate ensures that there is adequate flow to prevent boron stratification. The RHR flow to the RCS will provide adequate cooling to prevent exceeding 140 F and to allow flowrates which provide additional margin against vortexing at the RHR pump suction while in partial drain operation.
4 The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and at least 23 feet of water above the reactor vessel flange, a large heat 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 cool the core.
3/4.9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment purge penetra-tions will be automatically isolated upon detection 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.
CALLAWAY - UNIT 1 B 3/4 9-2 Amendment No. 42
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' DESIGN FEATURES 1
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly nonnally 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 incher 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 4.45 weight percent U-235.
Fuel with enrichments greater than 3.85 weight percent of U-235 shall contain sufficient integral fuel burnable absorber such that the requirements of Specification 5.6.1.1 are met.
_ CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control rod i
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.
_ DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
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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.
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.
CALLAWAY - UNIT 1 5-6 Amendment No. 72,23.2A,/7,54
DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
'A k equivalent to less than or equal to 0.95 when flooded f
wit 8 unborated 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 combination of initiel 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 i
A maximum reference fuel assembly K= less than or equal to c.
1.455 at 63'F for storage in Region 1.
5.6.1.2 The k,ff 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 maintained to prevent inadvertent dra.ining 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 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. J2,23, 54 (Next page is 5-9)
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