ML20211K983
| ML20211K983 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/09/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Nebraska Public Power District (NPPD) |
| Shared Package | |
| ML20211K989 | List: |
| References | |
| DPR-46-A-106 NUDOCS 8612150244 | |
| Download: ML20211K983 (7) | |
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UNITED STATES E
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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NEBP.ASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 106 License: No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated September 17, 1986 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, 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 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 Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
8612150244 861209
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. (2) Technical Specification The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 106, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0 I SION jf4 Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 9, 1986
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ATTACHMENT TO LICENSE AMENDMENT NO.106 FACILITY OPERATING LICENSE NO. OPR-46 DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indiciated by marginal lines.
Pages 210 212f 214b 217 i
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11 FUEL RODS 4.11 FUEL RODS Applicability Applicability The Limiting Conditions for Operation The Surveillance Requirements apply associated with the fuel rods apply t to the parameters which monitor the those parameters which monitor the fuel fuel rod operating conditions.
rod operating conditions.
Objective Objective The Objective of the Limiting Condi-The Objective of the Surveillance tions for Operation is to assure the Requirements is to specify the type performance of the feel rods.
and frequency of surveillance to be Specifications applied to the fuel rods.
A.
Average Planar Linear Heat Specifications Generation Rate (APLHGR)
During steady state power opera-A.
Average Planar Linear Heat tion, the APLHGR for each type of Generation Rate (APLHGR) fuel as a function of average planar exposure shall not exceed The APLHGR for each type of fuel the limiting value shown in Figure as a function of average planar 3.11-1 for two recirculation loop exposure shall be determined operation. For single-loop oper-daily during reactor operation ation the values in these curves at 3 25% rated thermal power.
are reduced by 0.84 for 7x7 fuel; 0.86 for 8x8 fuel; 0.77 for 8x8R, l
P8x8R, and BP8x8R fuel. If at any time during steady' state operation it is determined by normal surveillance that the'11miting value for APLHGR is being exceeded action shall be initiated within 15 minutes to restore operation to within the prescribed limits.
If the APLHGR is not returned to within the prescribed limits within two (2) hours, the reactor shall be brought to the i
Cold Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corres-i ponding action shall continue until the prescribed limits are again being met.
B.
Linear Heat Generation Rate (LHGR) l B.
Linear Heat Generation Rate (LHGR)
The LHGR as a function of core l
During steady state power opera-height shall be checked daily tion, the linear heat generation during reactor operation at 3 25%
rate (LHGR) of any rod in any fuel rated thermal power, assembly at any axial location shall not exceed the maximum allow-l able LHGR as calculated by the following equation:
max 5 LHGR (0
max (
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d l
G KW/ft.
=
d (AP/P) max " Maximum power spiking penalty =
N Amendment No. 55, 95, 106
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( based on tested measured scrom time os defined in Reference 9)
Figure 3.11-2e P8x 8R 8 BP8 x 8R Fuel (BOC to EOC-lOOO mwd /ST) 1 212 f Am:ndment No. 93, 106
3.11 Bases:
(Cont'd)
The K factor curves shown in Figure 3.11-3 were developed generically g
which are applicable to all BWR/2, BWR/3, and BWR/4 reactors. The K factorswerederivedusingtheflowcontrollinecorrespondingtorabed thermal power at rated core flow as described in Reference 1.
The K, factors shown in Figure 3.11-3, are conservative for Cooper opera-tion Because the operating limit MCPR's are greater than the original 1.20 operating limit MCPR used for the generic derivation of K.
g References for Bases 3.11 1.
Licensing Topical Report, General Electric Boiling Water Reactor, Generic Reload Fuel Application. (NEDE-240ll-P), (most current approved submittal).
2.
" Supplemental Reload Licensing Submittal for Cooper Nuclear Station Unit 1," (applicable reload document).
3-8. Deleted l
9.
Letter (with attachment), R. H. Buckholz (GE) to P. S. Check (NRC),
" Response to NRC Request for Information on ODYN Computer Model,"
September 5, 1980.
-214b-Amendment No. 79, pg, 97, 106
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.i 5.0 MAJOR DESIGN FEATURES 5.1 Site Features The Cooper Nuclear Station site is located in Nemaha County, Nebraska, on the west bank of the Missouri River, at river mile 532.5.
This part of the river is referred to by the Corps of Engineers as the Lower Brownville Bend.
t Site coordinates are approximately 40' 21' north latitude and 95* 38' I
west longitude. The site consists of 1351 acres of land owned by Nebraska Public Power District. About 205 acres of this property is located in Atchison County, Missouri, opposite'the Nebraska portion of the station site.
The land area upon which the station is constructed is crossed by the Missouri River on the east and is bounded by privately owned property on the north, south, and west. At the west site boundary, a county road and Burlington Northern Railroad spur pass the site.
The reactor (center line) is located approximately 3600 feet from the nearest property boundary. No part of the present property shall be sold or leased by the applicant which would reduce the minimum distance from the reactor to the nearest site boundary to less than 3600 feet without prior '
approval.
The protected area is formed by a seven foot chain link fence which surrounds the site buildings.
5.2 Reactor A.
The core shall consist of not more than 548 fuel assemblies in any combination of 7x7 (49 fuel rods) and 8x8 (63 fuel rods) and 8x8R/P8x8R/BP8x8R (62 fuel rods).
l B.
The core shall contain 137 cruciform-shaped control rods. The control material shall be boron carbide powder (B C) compacted to approximately 4
70% theoretical density, except for the Hybrid I control rods which contain approximately 15% hafnium.
5.3 Reactor Vessel The reactor vessel shall be as described in Section IV-20 of the SAR. The applicable design shall be as described in this section of the SAR.
5.4 Containment A.
The principal design parameters for the primary containment shall be as given in Table V-2-1 of the SAR.
The applicable design shall be as des-cribed in Section XII-2.3 of the SAR.
B.
The secondary containment shall be as described in Section V-3.0 of the SAR.
C.
Penetrations to the primary containment and piping passing through such l
Amandment No. 57, $@, 9), 106
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