ML20100E407
| ML20100E407 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/09/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20100E411 | List: |
| References | |
| NUDOCS 9602140202 | |
| Download: ML20100E407 (12) | |
Text
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NUCLEAR REGULATORY COMMISSION 2 WASHINGTON, D.C. 30eadHm01 ~s...../ TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.46 License No. NPF-87 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Texas Utilities Electric Company (TV Electric, the licensee) dated December 30, 1994, as supplemented by letters dated July 28, (TXX-95187); September 14, (TXX-95235); and November 29, 1995, (TXX-95299); and January 2, 1996, (TXX-96-003), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, 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 regulations; D. The issuance of this license 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-87 is hereby amended to read as follows: 9602140202 960209 PDR ADOCK 05000445 P PDR
1 ' 4 2. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 46, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. The license amendment is effective as of its date of issuance to be implemented within 30 days. FOR THE NUCLEAR REGULATORY COMMISSION 1 Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 9, 1996
$R*CVq g UNITED STATES y j NUCLEAR REGULATORY COMMISSION %.. j* WASHINGTON, D.C. 30666M1 TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50 446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. NPF-89 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Texas Utilities Electric Company (TV Electric, the licensee) dated December 30, 1994, as supplemented by letters dated July 28, (TXX-95187); September 14, (TXX-95235); and November 29, 1995, (TXX-95299); and January 2, 1996, (TXX-96-003), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulatior.s of the Commission; C. There is reasonable assurance: (1) 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 regulations; D. The issuance of this license 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-89 is hereby amended to read as follows: 1 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 32, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TU Electric shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of its date of issuance to be implemented within 30 days. FOR THE NUCLEAR REGULATORY COMMISSION Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 9,1996
ATTACHMENT TO LICENSE AMENDMENT N05.46 AND 32 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-446 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness. REMOVE INSERT xiv xiv 5-6 5-6 5-7 5-7 5-8 5-9
INDEX BASES SECTION EASE 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARG IN........................................... B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.... B 3/4 10-1 3/4.10.3 PHYSICS TESTS............................................. B 3/4 10-1 3/4.10.4 REACTOR COOLANT L00PS..................................... B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN..................... B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS......................................... B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS........................................ B 3/4 11-1 C0MANCHE PEAK - UNITS 1 AND 2 xiii
INDEX DESIGN FEATURES SECTION E&GE 5.1 SITE 5.1.1 EXCLUSION AREA.............................................. 5-1 5.1.2 LOW POPULATION Z0NE......................................... 5-1 5.1.3 MAPS DEFINING ONRESTRICTED AREAS AND SITE B0UNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS.................... 5-1 FIGURE 5.1-1 EXCLUSION AREA....................................... 5-2 i FIGURE 5.1-2 LOW POPULATION 20NE.................................. 5-3 FIGURE 5.1-3 UNRESTRICTED AREA AND SITE BOUNDARY FOR RADI0 ACTIVE GASE0US AND LIQUID EFFLUENTS......................... 5-4 5.2 CONTAINMENT 5.2.1 CONFIGURATION............................................... 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE............................. 5-5 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES............................................. 5-5 5.3.2 CONTROL R0D ASSEMBLIES...................................... 5-5 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE............................. 5-5 5.4.2 V0LUME...................................................... 5-6 5.5 METEOROLOGICAL TOWER L0 CATION................................. 5-6 5.6 FUEL STORAGE 5.6.1 CRITICALITY................................................. 5-6 i FIGURE 5.6-1 MINIMUM BURNUP VS INITIAL U-235 ENRICHMENT FOR HIGH DENSITY (2/4) SPENT FUEL STORAGE RACKS................ 5-7 5.6.2 DRAINAGE.................................................... 5-8 5.6.3 CAPACITY.................................................... 5-8 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT........................... 5-8 TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.................. 5-9 COMANCHE PEAK - UNITS 1 AND 2 xiv Unit 1 - Amendment No. 46 Unit 2 - Amendment No. 32
DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 50 psig and a temperature of 280*F. 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly 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) may be made if justified by a cycle specific reload analysis. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment not to exceed 3.15 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment not to exceed 5.0 weight percent U-235. l CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80% silver,15% indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing and may include clad surface treatment'for wear mitigation. 5.4 REACTOR COOLANT SYSTEM DES 1GN PRESSURE AND TEMPERATURE 5.4.3 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 2,485 psig, and c. For a temperature of 650'F, except for the pressurizer which is 680*F. CDMANCHE PEAK - UNITS 1 AND 2 5-5 Unit 1 - Amendment No. W,27 Unit 2 - Amendment No. 3,13
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,135 i 100 cubic feet at a nominal T of 589.5*F. m 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The primary meteorological toiver shall be located as shown on Figure 5.1-1. 5.6 FUEL STORAGE 5.6.1 CRITICALITY l 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with: Fuel assemblies having a maximum U-235 enrichment of 5.0 weight a. percent; b. K y s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 4.3 of the FSAR; c. A nominal 16 inch center-to-center distance between fuel assemblies placed in the low density fuel storage racks; d. A nominal 9 inch center to center distance between fuel storage locations in the high density fuel storage racks with storage restrictions specified below; e. All new or partially spent fuel assemblies are allowed unrestricted storage in the low density fuel storage racks and restricted storage in an expanded checkerboard (1 out of 4) pattern in the high density fuel storage racks; and f. New or partially spent fuel assemblies which meet the minimum burnup-initial enrichment requirements of Figure 5.6-1 are allowed restricted storage in a checkerboard (2 out of 4) pattern in the high density fuel storage racks. 5.6.1.2 The new fuel storage racks are designed and shall be maintained with: Fuel assemblies having a maximum U-235 enrichment of 5.0 weight a. percent; 4 b. K u s 0.95 if fully flooded with unborated water, which includes an alTotianceforuncertaintiesasdescribedinSection4.3oftheFSAR; j i alYowanc.98 if moderated by aqueous foam, which includes an K s0 c. e for uncertainties as described in Section 4.3 of the FSAR; and ) d. A nominal 21 inch center to center distance between fuel assemblies 1 placed in the new fuel storage racks. COMANCHE PEAK - UNITS 1 AND 2 5-6 Unit 1 - Amendment No.46 Unit 2 - Amendment No.32
20 4 ) 2 out of 4 / 15 Storage Allowed / 5 f 9 / [ / / 5 10 J / l / 5 / x r / 5 2 out of 4 r/ Storage / Not Aflowed } / 0 2.8 3.0 3.2 3.4 3.6 3.8 4.0 4.2 4.4 4.6 4.8 5.0 INITIAL U5 ENRICHMENT (W/0) FIGURE 5.6 1 MINIMUM BURNUP VS INITIAL U 235 ENRICHMENT FOR HIGH DENSITY (2/4) SPENT FUEL STORAGE RACKS COMANCHE PEAK - UNITS 1 AND 2 57 UNIT 1 Amendment No. 46 UNIT 2 Amendment No. 32
DESIGN FEATURES 5.6.2 DRAINAGE The spent fuel storage pools are designed and shall be maintained to prevent inadvertent draining of the pools below elevation 854 feet. 5.6.3 CAPACITY The two spent fuel storage pools are designed and shall be maintained with a storage capacity limited to no more than 1291 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. COMANCHE PEAK - UNITS 1 AND 2 5-8 Unit 1 - Amendment No. 46 Unit 2 - Amendment No. 32
TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS CYCLIC OR DESIGN CYCLE COMPONENT TRANSIENT LIMIT OR TRANSIENT l Reactor Coolant System 200 heatup cycles at s 100 F/h Heatup cycle - T, from s 200*F and 200 cooldown cycles at to 2 550 F. s 100 F/h. Cooldown cycle - T" from 2 550*F to s 200*F. 200 pressurizer cooldown cycles Pressurizer cooldown cycle at s 200*F/h. temperatures from 2 650*F to s 200*F. l 80 loss of load cycles, without 2 15% of RATED THERMAL POWER to immediate Turbine or Reactor trip. 0% of RATED THERMAL POWER. 40 cycles of loss-of-offsite Loss-of-offsite A.C. electrical A.C. electrical power. ESF Electrical System. 80 cycles of loss of flow in one Loss of only one reactor reactor coolant loop. coolant pump. 400 Reactor trip cycles. 100% to 0% of RATED THERMAL POWER. 4 10 auxiliary spray Spray water temperature differential actuation cycles. > 320*F, but s 625*F. i 200 leak tests. Pressurized to 2 2485 psig. + 10 hydrostatic pressure tests. Pressurized to 2 3107 psig. Secondary Coolant System I steam line break. Break in a > 6-inch steam line. 10 hydrostatic pressure tests. Pressurized to 2 1481 psig. 4 COMANCHE PEAK - UNIT 1 AND 2 5-9 Unit 1 - Amendment No.46 l 4 Unit 2 - Amendment No.32 . m .---ir-- -y = ---}}