ML20138B579
| ML20138B579 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/24/1997 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20138B584 | List: |
| References | |
| NPF-06-A-182 NUDOCS 9704290211 | |
| Download: ML20138B579 (4) | |
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retuqk UNITED STATES O
NUCLEAR REGULATORY COMMISSION g
, *g WASHINGTON, D.C. 20665 4001 ge...../
ENTERGY OPERATIONS. INC.
DQCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 182 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated December 19, 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 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 i
comon 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.
9704290211 970424 PDR ADOCK 05000368 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.182, 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 Af e
George Kalman, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation I
Attachment:
Changes to the Technical Specifications Date of Issuance: April 24, 1997
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ATTACHMENT TO LICENSE AMENDMENT NO.187 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO.50-11g Revise the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGE INSERT PAGE 6-21a 6-21a M
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ADMINISTRATIVE CONTROL CORE OPERATING LIMITS REPORT 9)
"CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System," December 1981 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin, 3.1.1.4 for MTC, 3.1.3.1 for CEA Position, 3.1.3.6 for Regulating CEA and Group P Insertion l Limits, and 3.2.4.b for DNBR Margin).
- 10) " Technical Manual for the CENTS Code," CENPD 282-P-A, February 1991 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin, 3.1.1.4 for MTC, 3.1.3.1 for CEA Position, 3.1.3.6 for Regulating and Group P Insertion Limits, and 3.2.4.b for DNBR Nkrgin.
- 11) Letter:
O.D. Parr (NRC) to F.M. Stern (CE), dated June 13, 1975 l
(NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for 6.9.5.1.4, 6.9.5.1.5, and 6.9.5.1.8 methodologies.
- 12) Letter O.D. Parr (NRC) to A.E. Scherer (CE), dated December 9, 1975 l
(NRC Staff Review of the Proposed Combustion Engineering ECCS Evaluation Model changes). NRC approval for 6.9.5.1.6 methodology.
- 13) Letter: 2CNA038403, dated March 20, 1984, J.R. Miller (NRC) to l
J.M. Griffin (AP&L), "CESEC Code Verification." NRC approval for 6.9.5.1.9 methodology.
i 6.9.5.2 The core operating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
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6.9.5.3 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
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ARKANSAS - UNIT 2 6-21a Amendment No. 4M,M4,M9,182 l