ML20129H326
| ML20129H326 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/25/1996 |
| From: | Wharton L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20129H318 | List: |
| References | |
| NUDOCS 9610310233 | |
| Download: ML20129H326 (5) | |
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UNITED STATES e
S NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20555-0001
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OMAHA._PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE j
Amendment No.178 License No. DPR-40 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Omaha Public Power District (the licensee) dated July 15, 1996, as supplemented by letters dated September 3, 1996, October 22, 1996, October 24, 1996, and application dated August 23, 1996, 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 1
Chapter I; B.
The facility will operate in conformity 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 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 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 Comission's regulations and all applicable requirements have been satisfied, i
9610310233 961025 PDR ADOCK 05000285 P
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4 i 2.
Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.
4 DPR-40 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 178, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$$paht0pfin L. Raynard Wharton, Project Manager Project Directorate IV-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 25, 1996
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9 ATTACHMENT TO LICENSE AMENDMENT NO. 178 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 4-3 4-3 5-17a 5-17a
a i
4.0 DESIGN FEATURES 4.3 Fuclear Steam Sunoly System (Continued) 4.3.1 Reor Coolant System (Continued) i The reactor coolant system is designed and constructed in accordance with the ASME 1
Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Vessels including all addenda through the winter of 1967 and the Code for Pressure Piping USAS 4
j-B31.1. The reactor coolant system is designed for a pressure of 2500 psia and a temperature of 650'F except for the pressurizer which has a design temperature of 700*F.
'Ihe volume of the reactor coolant system is approximately 6,616 cubic feet, l
4 4.3.2 Reactor Core and Control I
j The reactor shall contain 133 fuel assemblies. Each assembly shall consist of a matrix of zircaloy or ZIRLO' fuel rods with an initial composition of natural, depleted, or i
i slightly enriched uranium dioxide (UO) as fuel material. Limited substitutions of 4
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zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved l
applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests 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 nonlimiting core regions.
i The reactor core shall contain 49 control element assemblies (CEAs). The control material shall be silver indium cadmium, boron carbide, or hafnium metal as approved by the NRC.
4.3.3 Emereency Core Cooline i
Emergency core cooling is provided by the Safety Injection System which consists of i
various subsystems, each with internal redundancy. Included in the Safety Injection System are four safety injection tanks, three high-pressure and two low-pressure safety injection pumps, a safety injection and refueling water storage tank, and interconnecting piping as shown in USAR Section 6.
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i 4-3 Amendment No. 5,20,60,1"),178
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4 5.0 ADMINISTRATIVE CONTROLS i
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5.9.5 Core Ooerating Limits Reoort i
a.
Core Operating Limits shall be established and documented in the Core Operating Limits Report (COLR) before each reload cycle or any remaining part of a reload I
- cycle, b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC as follows:
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1.
OPPD-NA-8301-P-A, " Reload Core Analysis Methodology
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Overview" (Imt NRC approved revision as stated in the COLR).
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OPPD-NA-8302-P-A, "Neutronics Design Methods and Verification" (Latest NRC approved revision as stated in the COLR).
3.
OPPD-NA-8303-P-A, " Transient and Accident Methods and Verification" (Latest NRC approved revision as stated in the q
COLR).
4.
WCAP-12610-P-A," VANTAGE + Fuel Assembly Report," April l
1995 (Westinghouse Proprietary) as approved in the Safety
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Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No.178 to Facility Operating License No. DPR-40, Omaha Public Power District, Fort Calhoun Station Unit No.1, 1
Docket No. 50-285, dated October 25,1996.
5.
WCAP-13027-P, " Westinghouse ECCS Evaluation Model for Analysis of CE-NSSS," July 1991 (Westinghouse Proprietary) as i
approved in the Safety Evaluation by the Office of Nuclear Reactor Regulation dated March 26, 1992, and as applied in OPPD submittal to the NRC (LIC-96-0130) dated September 3,1996, and 1
as approved in the Safety Evaluation by the Office of Nuclear i
Reactor Regulation Related to Amendment No.178 to Facility Operating License No. DPR-40, Omaha Public Power District, Fort Calhoun Station Unit No.1, Docket No. 50 285, dated 1
October 25,1996.
a c.
'Ihe core operating limits shall be determined so that all applicable limits of the safety analysis are met. The Core Operating Limits Report, including any mid-i cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Region IV Administrator and Senior Resident Inspector.
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5-17a Amendment No.141,1M,157,178 s-.
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