ML20217E312
| ML20217E312 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/22/1997 |
| From: | Stone J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217E317 | List: |
| References | |
| NUDOCS 9710060452 | |
| Download: ML20217E312 (7) | |
Text
{{#Wiki_filter:p2 not,g k UNITED STATES g j NUCLEAR RECULATORY COMMISSION 2 WASHINGTON. D.C. 20eeHoot \\...../ WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 110 License No. NPF-42 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated July 3.1997, 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: (1) that the activities authorized by this amendment can be conducted without endangering the healtn 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. 9710060452 970922 PDR ADOCK 05000482 P PDR
1 4 i 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment-to this license amendment i and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby-amended to read as follows: 9 2. Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.110, and the Environmental Protection Plan contained in Appendix B both of which are attached hereto, are 4 hereby incorporated in the license. The Corporation shall operate 1 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 j implemented within 30 days of the date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION I 1 i ames C. Stone. Senior Project Manager 1 Project Directorate IV-2 i-Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical 1'
Specifications Date of Issuance:
September 22, 1997 y
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..---...~ proved applications of fuel rod
- configurations, may be used.
Fuel assem) lies shall be limited to those fuel i
designs that have been analyzed with applicable NRC approved codes and methods
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and shown by test or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative-testing may be placed in non-limiting core regions.
CONTROL ROD ASSEMBLIES E
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 i
142 inches of absorber material. All control rod assemblies 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 C00LAfiT SYSTEM DESIGN PRESSURE MD 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 i 100 cubic feet at a nominal T., of 557 F.
- 5. 5 hETEOR0 LOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
WOLF CREEK - UNIT 1 5-6 Amendment No. 3.15.19.18.51.110
e i DESIGN FEATURES t j 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with: j 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 4.3 of the USAR. This is based on new fuel with an enrichment of 4.45 weight percent U-235 in Region 1 and on spent fuel with combination of initial enrichment and discharge j exposures, shown in Figure 3.9-1, in Region 2, and b. A nominal 9.236 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 spect fuel sto,,a,ge racks shall not exceed 0.98 when aqueous foam moderation is r 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 sterage 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 com>onents identified in Table 5.7-1 are designed and shall be maintained wit 11n the cyclic or transient limits of Table 5.7-1. r WOLF CREEK - UNIT 1 5-7 Amendment No J5,61
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (COLR) (Continued) Nuclear Enthalpy Rise Hot Channel Factor - Fh Specification 3.9.1.b - Refueling Boron Concentration). j, NRC Safety Evaluation Reports dated July 1,1991 " Acceptance for Referencing of Topical Report WCAP-12610, ' VANTAGE + Fuel Assembly Reference Core Report' (TAC NO. 77258)," and September 15, 1994. " Acceptance for Referencing of Topical Report WCAP-12610, Appendix B Addendum 1 ' Extended Burnu) Fuel Desig'n Methodology and ZIRLO Fuel Performance Models' (TAC 90. M86416) (WCAP-12616-P-A) (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor - Fo(Z) The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-hydraulic limits, core thermal-hydraulic limits. ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT. including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report. 6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10. Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated. 6.10.1 The following records shall be retained for at least 5 years: a. Records and logs of unit operation covering time interval at each power level; b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety: c. All REPORTABLE EVENTS: d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; e. Records of changes made to the procedures required by Specification 6.8.1: f. Records of radioactive shipments: g. Records of sealed source and fission detector leak tests and results: and h. Records of annual physical inventory of all sealed source material of record. WOLF CREEK - UNIT 1 6-21b Amendment No. 61-92, 110
_DMIN!sTitATIVE M ROLS A RECORD RETENTION (Continued) 8.10.2 The following records shall be retained for the duration of the Unit Operating License: Records and drawing changes reflecting unit design modifications a. made to systems and equipment described in the Final Safety Analysis Report; b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories; Records of radiation exposure for all individuals entering radiation c. control areas; d. Records of gaseous and liquid radioactive material released to the environs; Records of transient or operational cycles for those Unit components e. identified in Table 5.7-1; f. Records of reactor tests and experiments; g. Records of training and qualification for current members of the Unit Staff; h. Records of in-service inspections performed pursuant to these Technical Specifications; i. Records of Quality Assurance activities required by the QA Manual; j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; k. Records of meetings of the PSRC and the NSRC; 1. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records; m. Records of secondary water sampling and water quality; and a. Records of analysis required by the Radiological Environmental Monitoring Program t..at would perett evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed. c. Records of reviews performed for changes made to the 0FFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. l WOLF CREEK UNIT 1 6-22 Amendment No. 42 i l -, wmm u m n + c = r}}