ML20004G023
| ML20004G023 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/19/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004G021 | List: |
| References | |
| NUDOCS 8106260500 | |
| Download: ML20004G023 (3) | |
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7590-0, UNITED STATE 5 iiUCLEAR REGUi.ATORY C0idi4ISSI0ii DOCKET NO. 50-369 ARKAt:St.C 90'.1ER A!!D LIGHT C0;tPAf Y NOTICE OF ISsilANCE OF AMENDMENT TO FACILITY ODERATING LICENSE The~U.-S. Nuclear Regulatory Commission (the Commission)-has issued
' Amendment No. 24 to Facility Operating License No. NPF-6, issued to the Arkansas Power and i.jit Company, which revised the license and the Technical Specifications for operation of Arkansas Nuclear One, Unit No. 2 (the facility)-
at steady state reactor core power levels not in excess of 2815 megawatts
-thermal, in accordance with the provisions of the license and the Technical Specifications. However, the' facility is temporarily restricted from operating at full rated power pending completion of the staff's detailed review of the core protection calculator system (CPCS) changes for. Cycle 2 operation.
i The facility is located at the licensee's site in Pope County, Arkansas. The license amendment is effective as of its date of issuance.
The amendment authorizes Cycle 2 operation at seventy (70) percent of the licensed power level of 2815 MWt with:
Changes in the Core Protection Calculator System (CPCS) to reflect utilization of the CE-1 critical heat flux correlation and associated thermal hydraulic methodology.
l Changes in the CPCS to reflect utilization of the Statistical Combination of Uncertainties (SCU) thermal hydraulic methodology for the combination j-of system parameter uncertainties.
- Changes in the RPS and ESFAS trip setpoints to reflect a change in signal transmitter design and to reflect staff approval of the licensee's l
equipment trip setpoints.
N1th 160 [Q
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. t.nanges in-tne minimum reauired snutoown margin to lengthen the time available for operator action during a coron dilution event.
' Changes required to maintain acceptabla results for the steamline break analysis.
. Some demonstration fuel; assemblies to test new fuel: designs.
. Numerous other miscellaneous changes of a clarifying,. editorial and administr'ative nature.
. Other changes in the Technical Specification to incorporate requirements resulting from the detailed physics and thermal hydraulic analysis of the Cycle 2 reload core.
The applications for the amendment comply with the standards and requirements of-the-Atomic. Energy Act of 1954,- as amended _(the_Act), and -
_ _ 2_ r the Commission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in-10 CFR Chapter I, which are set forth in the license amendment. Prior a
public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
~
The Commission has determined that the issuance of this amendment l
will not result in any significant environmental impact and that pursuant to 10 CFR Sl.5(d)(4) an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with L
issuance of this amendment.
For further details with respect to this action, see (1) the applications L
for amendment dated February 20 and March 5, 1981, as supplemented by references identified in the related Safety Evaluation, (2) Amendment No. 24
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3-to License No. NFF-6.and (3) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Oc.raission's Public Document Room, 1717 H Street, N. W., Washington. D. C. and. at the Arkansas Tech University, Russellville, Arkansas 72801. A copy of items (2) and (3) may be obtained upon request addresseo to the U. S. Nuclear Regulatory Commission, Washington, D. C.
20555, Attention: Director, Division of Licensing.
k Dated at Bethesda, Maryland this 19th day of June, 1981.
FOR THE NUCLEAR REGULATORY COMMISSION r
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u Robert A.
rk, Chief Operating Reactors Branch #3 Division of Licensing Y