ML20133J485
| ML20133J485 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/14/1997 |
| From: | Salehi K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20133J487 | List: |
| References | |
| NPF-06-A-179 NUDOCS 9701210036 | |
| Download: ML20133J485 (5) | |
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UNITED STATES p*
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20656-0001 49 * * *, +,o 1
ENTERGY OPERATIONS. INC.
l DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 179 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 November 24, 1996, as supplemented by letter dated December 2, 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 i
provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(1) thv. '
activities authorized l
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that surn activities will be conducted in compliance with the Comi.ision's regulations; D.
The issuance of this license 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.
9701210036 970114 PDR ADOCK 05000368 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
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. 179, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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The license amendment is effective as of its date of issuance.
1 FOR THE NUCLEAR REGULATORY COMMISSION o'
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f Kombiz a ehi, Acting Project Manager Project Directorate IV-1 i
Division of Reactor Projects III/IV j
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications j
Date of Issuance:
January 14, 1997 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 179 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 6-21 6-21 6-21a 6-21a i
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i-ADM8NISTRAT2VE CONTROL i
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CORE OPERATING LIMITS REPORT l
6.9.5 The core operating limits shall be established and documented in the j
OORE OPERATING LIMITS REPORT prior to each reload cycle or any remaining part of a reload cycle.
i 6.9.5.1 The analytical methods used to determine the core operating limits addressed by the individual Technical Specifications shall be those previously reviewed and approved by the NRC for use at ANO-2, specifical.y j
1)
"The ROCS and DIT Computer Codes for Nuclear Design", CENPD-266-P-A, April 1983 (Methodology for specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margirs, 3.1.1.4 for NEC, 3.1.3.6 for Regulating and Group P CEA Insertion Limits, and 3.2.4.b for DNBR Margin).
2)
"CE Method for control Element Assembly Ejection Analysis,"
CENPD-0190-A, January 1976 (Methodology for Specification 3.1.3.6 for Regulating and Group P CEA Insertion Limits and 3.2.3 for Azimuthal Power Tilt).
3)
" Modified Statistical Combination of Uncertainties, CEN-356(V)-P-A, Revision 01-P-A, May 1988 (Methodology for specification 3.2.4.c and 3.2.4.d for DNBR Margin and 3.2.7 for ASI).
4)
" Calculative Methods for the CE Large Break LOCA Evaluation Model,"
CENPD-132-P, August 1974 (Methodology for specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).
5)
" Calculational Methods for the CE Large Break LOCA Evaluation Model,"
CENPD-132-P, Supplement 1, February 1975 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).
6)
" Calculational Methods for the CE Large Break LOCA Evaluation Model,"
CENPD-132-P, Supplement 2-P, July 1975 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).
7)
" Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed N555," CEN-132, supplement 3-P-A, June 1985 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).
8)
" Calculative Methods for the CE Small Break LOCA Evaluation Model,"
l CENPD-137-P, August 1974 (Methodology for specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).
9)
" Calculative Methods for the CE Small Break LOCA Evaluation Model,"
CENPD-137, supplement 1-P, January 1977 (Methodology for specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).
ARKANSAS - UNIT 2 6-21 Amendment No. M3,M4,M9, 179
ADMINISTRATIVE CONTROL
_ Core OPEPATING LIMITS REPORT
- 10) "CESEC-Digital simulation of a Combustion Engineering Nuclear Steam l
Supply System," December 1981 (Methodology for Specifications l
3.1.1.1 and 3.1.1.2 for shutdown Margin, 3.1.1.4 for MTC, 3.1.3.1 for Movable control Assemblies - CEA Position, 3.1.3.6 for Regulating CEA and Group P Insertion Limits, and 3.2.4.b for DNBR Nargin).
- 11) Letter:
0.D. Parr (NRC) to F.M. Stern (CE), dated June 13, 1975 l
i (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:
0.D. Parr (NRC) to 7.E. Scherer (CE), dated December 9, 1975 l
3 (NRC Staff Review of the Proposed Combustion Engineering ECCS i
Evaluation Model changes). MRC approval for 6.9.5.1.6 methodology.
- 13) Letter:
K. Kniel (NRC) to A.E. Scherer (CE), dated September 27, 1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P).
NRC approval for 6.9.5.1.9 methodology, 4
- 14) Letter: 2CNA038403, dated March 20, 1984, J.R. Ndller (NRC) to l
J.M. Griffin (APEL), "CESEC Code Verification." NRC approval for 6.9.5.1.10 methodology.
l 6.9.5.2 The core cperating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic lind te,,
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?.CCS limits, nuclear limits such as shutdown margin, and transient and accident 4
anslysis af adts) of the safety analysis are met.
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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4 ARKANSAS - UNIT 2 6-21a Amendment No. M3,M4,M9, 179 4