ML20092J437
| ML20092J437 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  (NPF-006) |
| Issue date: | 09/19/1995 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20092J439 | List: |
| References | |
| NPF-06-A-164 NUDOCS 9509220133 | |
| Download: ML20092J437 (7) | |
Text
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4 UNITED STATES g
g NUCLEAR REGULATORY COMMISSION S
WASHINGTON, D.C. 20066-0001 o
44.....,o ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.164 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated March 17, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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 Commission; f
C.
There is reasonable assurance:
(1) 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
9509220133 950919 PDR ADOCK 05000368 P
1 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 Specifications j
The Technical Specifications contained in Appendix A, as revised through Amendment No.164, 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 3
Y George Kalman, Senior Project Manager Project Directorate IV-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specificati6ns
{
Date of Issuance:
September 19, 1995 i
c ATTACHMENT TO LICENSE AMENDMENT NO. 164 j
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. The corresponding overleaf pages are also provided to maintain document completeness.*
i REMOVE PAGES INSERT PAGES 3/4 2-5 3/4 2-5 B 3/4 2-6*
B 3/4 2-6*
6-21 6-21 6-21a 6-21a 1
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POWER DISTRIBUTION LIMITS DNBR MARGIN LIMITING CONDITION FOR OPERATION 3.2.4 The DNBR limit shall be maintained by one of the following methods:
a.
Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR (when OOLSS is in service, and at least one CEAC is operable); or b.
Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by the value specified in the CORE OPFRATING LIMITS REPORT (when OOLSS is in service and neither CEAC is operable);
i or c.
Operating within the region of acceptable operation specified in the CORE OPEAATING LIMITS REPORT using any operable CPC channel a
(when COLSS is out of service and at least one CEAC is operable);
or d.
Operating within the region of acceptable operation specified in the CORE OPERATING LIMITS REPORT using any operable CPC channel i
(when COLSS is out of service and neither CEAC is operable).
APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.
j s
ACTIONt a.
With COLSS in service and the DNBR limit not being maintained as indicated by'COLSS calculated core power exceeding the COLSS calculated core power operating limit based on DNBR, within 15
)
minutes initiate corrective action to reduce the DNBR to within the limits and either
)
1.
Restore the DNBR to within its limits within I hour of the
]
initiating event, or 2.
Reduce THERMAL POWER to less than or equal to 20% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With COLSS out of service and the DNBR limit not being maintained as indicated by operation outside the region of acceptable operation specified in the CORE OPERATING LIMITS REPORT, either 1.
Restore the DNBR to within its limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the initiating event, or 2.
Reduce THERMAL POWER to less than or equal to 20% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ARKANSAS - UNIT 2 3/4 2-5 Amendment No. 94,49,M,4M,M% M4
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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS l
4.2.4.1 The provisions of Specification 4.0.4 are not applicable.
4.2.4.2 The DNBR shall be determined to be within its limits when TERMAL 4
POWER is above 20% of RATED THERMAL POWER by continuously monitoring the core power distribution with the Core operating Limit Supervisory system (COLSS) or, with the COL 88 out of service, by verifying at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> that the DNBR, as indicated on any OPERABLE CPC channel, is within the limit specified in the CORE OPERATING LIMITS REPORT.
l 4.2.4.3 At least once per 31 days, the COL 55 Margin Alarm shall be 1
verified to actuate at a THERMAL POWER level less than or equal to the core power operating limit based on DNBR.
l l
i t
1 i
o' i
s i
a ARKANSAS - UNIT 2 3/4 2-6 Amendment No. 77, 157 I
3..
ADMINISTRATIVE CONTROL CORE OPERATING LIMITS REPORT 6.9.5 The core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle or any remaining part of a reload cycle.
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, specificallys 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 Margins, 3.1.1.4 for MTC, 3.1.3.6 for Regulating 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 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 Spepification 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 NSSS," 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)
" Calculational Methods for the CE Small Break LOCA Evaluation Model,"
CENPD-137-P, August 1974 (Methodology for specification 3.1.1.4 i
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. 464. 164
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 Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating CEA Insertion Limits, 3.1.3.7 for Part Length CEA Insertion Limits, and 3.2.4.b for DNBR Margin).
- 10) Letter O.D. Parr (NRC) to P.M. Stern (CE), dated June 13, 1975 (NRC Staff Review of the Combustion Engineering ECCS Evaluation l
Model). NRC approval for 6.9.3.1.4, 6.9.5.1.5, and 6.9.5.1.8 methodologies.
- 11) 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.
4
- 12) Letter 2CNA038403, dated March 20, 1984, J.R. Miller (NRC) to J.M. Griffin (AP&L), "CESEC Code Verification." NRC approval for 6.9.5.1.9 methodology.
6.9.5.2 The core operating Ilmits 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.
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 Inspe6 tor.
d I
ARKANSAS - UNIT 2 6-21a Amendment No. 454, 164