ML20081F798
| ML20081F798 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/17/1995 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20081F792 | List: |
| References | |
| NUDOCS 9503220272 | |
| Download: ML20081F798 (3) | |
Text
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1 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 COLSS 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 13.0". the value soecified in the CORE OPERATING LIMITS M (when COLSS is in service and neither CEAC is operable); or c.
Operating within the region of acceptable operation specified in the CORE OPERATING LIMITS REPORT using any operable CPC channel (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 (when COLSS is out of service and neither CEAC is operable).
APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.
ACTION 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-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 />.
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, eithers 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 THERHAL 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 />.
)
9503220272 950317 PDR ADOCK 0500 8
P ARKANSAS - UNIT 2 3/4 2-5 Amendment No. 94,49,99,449,469
i ADMINISTRATIVE CONTROL
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CORE OPERATING LIMITS REPORT 6.9.5' The core operating limits shall be established and documented in the CORE OPERATING LIMITS LEPORT 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 addressou by the individual Technical Specifications shall be those previously reviewed and approved by the NRC for use at ANO-2, specifically:
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, end-3.1.3.6,for Regulating CEA Insertion Limits. and 3.2.4.b for DNBR Marcin).
2)
"CE Method for Control Element Assembly Ejection Analysis,"
CENPD-Ol90-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, 0--.iin ti;; ef Art;;;;; ;;1 :: Cn: Unit 2," 0:M 130(A) 7, Me.
- 1000 CEN-356fV)-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 LOOA Evaluation Model,"
CENPD-132-P, Supplement 1, February 1975 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Meat 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 Pate, 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 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, e J 3.2.7 for ASI).
ARKANSAS - UNIT 2 6-21 Amendment No. H
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' ADMINISTRATIVI' CONTROL :
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7..,
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CORE OPERATING LIMITS REPORT 9)^ ' "CESEC-Digital simulation'of a combustion Engineering Nuclear Steam f
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 l
'7 for Movable Control Assemblies - CEA Position, 3.1.3.6-for
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Regulating CEA Insertion Limits,_end-3.1.3.7-for Part Length CEA Insertion Limits. and 3.2.4.b for DNBR Marain).
- 10) Letter:
0.D. Parr (NRC) to F.M. Stern (CE), dated June 13, 1975 (NRC Staff Review of the combustion Engineering ECC8 Evaluation i
Model). NRC approval for 6.9.5.1.4, 6.9.5.1.5, and 6.9.5.1.8' methodologies.
l
- 11) Letter:
0.D. Parr (NRC) to A.E. Scherer (CE), dated December 9, 1975 (NRC Staff Review of the Proposed Combustion Engineering ECCS L Evaluation Model changes). NRC approval for"6.9.5.1.6 methodology.
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- 12) Letter: 2CNA038403,- dated March 20, 1984, J.R. Miller (NRC) to l
-J.M. Griffin (APGL), "CESEC code Verification." NRC approval for 6.9.5.1.9 methodology.
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, l
ECCS limits,. nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
I 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. 4 M
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