ML19344D160
| ML19344D160 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/15/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19344D161 | List: |
| References | |
| NUDOCS 8003110443 | |
| Download: ML19344D160 (6) | |
Text
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UNITED STATES E"
NUCLEAR REGULATORY COMMISSION o
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E WASHING TON, D. C. 20555
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET N0. 50-331 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, Central Iowa Power Cooperative, and Corn Belt Power Cooperative (the licensee) dated January 2,1980 complies with the standards and requirenents of the Atonic Energy Act of 1954, as anended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity 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 anendment 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; ard 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-49 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 57, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
t 8003110 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: February 15, 1980 4
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ATTACHMENT TO LICENSE AMENDMENT N0. 57 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3.9-4 3.9-4 3.9-9/3.9-10 3.9-9/3.9-10 4
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT B.
Cy W titoring B.
Core Monitoring During core alterations two Prior to making any alterations SRM's shall be operable one to the core, the SRM's shall be in the core quadrant where fuel functionally tested and checked or control rods are being moved, for neutron response. There-and one in an adjacent quadrant, after, while required to be operable, except as specified in 3 and the SRM's will be checked daily for 4 below.
For an SRM to be response.
considered operable, the follow-ing conditions shall be satisfied:
Prior to spiral unloading or re-i loading the SRM's shall be function-l.
The SRM shall be inserted to the ally tested. Prior to spiral un-normal operating level. (Use of loading, the SRM's shall also be special movable, dunking type checked for neutron response.
detectors during initial fuel loading and major core alterations in place of normal detectors is permissible as long as the detec-tor is connected to the normal SRM circuit).
2.
The SRM shall have a minimum of 3 cps with all rods fully in-serted in the core.
3.
Prior to spiral unloading, the SRM's shall be proven operable as stated above, however, during spiral unloading the count rate may drop below 3 cps.
4.
Prior to spiral reload, two diagonally adjacent fuel assemblies, which have previously accumulated exposure in the reactor, will be loaded into their previous core positions next i
to each of the 4 SRM's to obtain the required 3 cps.
Until these eight assemblies have been loaded, the 3 cps C.
Spent Fuel Pool Water Level requirement is not necessary.
Whenever irradiated fuel is stored in the spent fuel pool, the water C.
Spent Fuel Pool Water Level level shall be recorded daily.
' Whenever irradiated fuel is stored in the spent fuel pool, the pool water level shall be maintained at or above a level
. of 36 feet.
3.9-4 e
4 Amendment No.
57 c
DAEC-1 normally available during refueling operations.
In order to withdraw more than one control rod, it is nece sary to bypass the refuleing interlock on each withdrawn control rod which prevents more than one control rod from being withdrawn at a time.
The requirement that the fuel assemblies in the cell con-trolled by the control rod be removed from the reactor core be-fore the interlock can be bypassed ensures that withdrawal of another control rod does not result in inadvertent criticality.
Each control rod provides primary reactivity control for the fuel assemblies in the cell associated with that control rod.
Thus, removal of an entire cell (fuel assemblies plus control rod) results in a lower reactivity potential of the core.
The requirements for SRM operability during these core altera-tions assure sufficient core monitoring.
2.
Core Monitoring The SRM's are provided to monitor the core during periods of station shutdown and to guide the operator during refueling operations and station startup.
Requiring two operable SRM's in or adjacent to any core quadrant where fuel or control rods are being moved assures adequate monitoring of that 3.9-9
I DAEC-1 quadrant during such alterations. The requirement of 3 counts per second provides assurance that neutron flux is being monitored and insures that startup is conducted only if the source range flux level is above the minimum assumed in the control rod drop accident.
During spiral unloading, it is not necessary to maintain 3 cps because core alterations will involve only reactivity removal and will not result in criticality.
The loading of diagonally adjacent bundles around the SRM's before attaining the 3 cps is permissible because these bundles were in a subcritical configuration when they were removed and therefore they will remain subcritical when placed back in their previous position.
3.
Spent fuel Pool Water Level To assure that there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established. The minimum water level above the top of the fuel is established to provide adequate shielding and is well above the level to assure adequate cooling.
' Amendment No. 57 3.9-10
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