ML20028G875
| ML20028G875 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/28/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028G876 | List: |
| References | |
| NUDOCS 9009050300 | |
| Download: ML20028G875 (4) | |
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UNITED STATES NUCL8 EAR REGULATORY COMMISSION t
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IOWA ELECTRIC LIGHT AND POWER COMPANY CEMIKAL IDWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 b
DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 168 License No. DPR-49
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1 1.
The Nuclear Regulatory Comission (the Comission) has found that:
L A.
The application for amendment by Iowa Electric Light and Power L
Company, et al., dated June 19, 1990 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 Chapter _I, B.
The facility will operate in conformity with the application, the l
provisions of the Act.shd the rules and regulations of the l
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 j
conducted in compliance with the Comission'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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
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9009050300 900828 PDR ADOCK 05000331 1
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(2) Technical Specific iiens The Technical Specifications contained in Appendix A, as revised through Amendment No.168, 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 the date of issuance and shall be impicmented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y
John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV,'Y and Special Projects Office of Nuclear Reactor Regulation p
Attachment:
Changes to the Technical Specifications Date of. issuance: August 28, 1990 l
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^r ATTACHMENT TO LICENSE AMENDMENT NO. 168 L
FACILITY OPERATING LICENSE N0. DPR '
DOCKET NO. 50-331 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.
Pages 1.1-1 b
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SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 4
1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY Aeolicabilitv:
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Applies to the inter-related Applies to trip settings of the variables associated with fuel instruments and devices which are provided to prevent the thermal behavior, reactor system safety limits from being exceeded.
Ob.iective:
Ob.iectivy To define the level of the To establish limits which ensure process variables at which the integrity of the fuel automatic protective action is
- cladding, initiated to prevent the fuel-cladding integrity safety limits from being exceeded.
Soecifications:
Specifications:
The limiting safety system below:gs shall be as specified settin A.
Reactor presstre > 785 osia and A.
Neutron Flux Trios Core Flow > 10% of Rated 1.
APRM High Flux Scram When In Run The existence of a minimum Mod' critical power ratio (MCPR) less l
than 1.07 for two recirculation The APRM scram trip setpoint I
loop operation [1.10 for SINGLE LOOP OPERATION (SLO)] shall shall be as shown on Figure constitute violation of the fuel 2.1-1 and shall be:
cladding integrity safety limit.
S 5 (0.58W + 62)
B.
Core Thermal Power limit with a maximum setpoint of 120%
(Reactor PreM Mr.2 5 231._ psia er rated power at 100% rated Core Flow 2 10% of Rated recirculation flow or greater for two recirculation loop When the reactor pressure is 5 operation and 785 psig or core flow is less than or equal to 10% of rated, 5 < (0.58W + 58.5) the core thermal power shall not exceed 25 percent of rated for SLO.
thermal power.
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' Amendment No. J20,J M,168 1 1-1
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