ML20117F481
| ML20117F481 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/23/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20117F476 | List: |
| References | |
| NUDOCS 9609040083 | |
| Download: ML20117F481 (8) | |
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l 9609040083 960823 PDR ADOCK 05000368 P
POWER DISTRIBUTION LIMI'2S
- RCS PLOW RATE LIMITING CONDITION FOR OPERATION 3.2.5 The actual Reactor Coolant System total flow rate shall be within the limit provided in the CORE OPERATING LIMITS REPORT.
APPLICABILITY: MODE 1.
ACTION:
With the actual Reactor Coolant System total flow rate determined to be less than the above limit, reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.5 The actual Reactor Coolant System total flow rate shall be determined to'be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ARKANSAS - UNIT 2 3/4 2-7 Amendment No. 34, -lM,
i i
ADMINISTRATIVE CONTROL
- CORE OPERATING LIMITS REPORT 6.9.5 The core operating lindts shall be established and documented in the CORE 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 j
reviewed and approved by the NRC for use at ANO-2, specifically:
J 1)
"The ROCS and DIT Computer Codes "or 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 and Group P CEA Insertion Limits, and 3.2.4.b for DNBR Margin).
2)
"CE Method for Control Element Assembly Ejection Analysis,"
1 CENPD-0190-A, January 1976 (Methodology for Specification 3.1.3.6 for Regulating and Group P CEA Insertion Limits and j
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).
i 4)
" Calculative Methods for the CE Large Break LOCA Evaluation Model,"
1' 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 l
Tilt, 3.2.5 for RCS Flow Rate, and 3.2.7 for ASI).
l 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, 3.2.5 for RCS Flow Rate, and 3.2.7 for l
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, 3.2.5 for RCS Flow Rate, and 3.2.7 for l
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, 3.2.5 for RCF Flow Rate, and 3.2.7 for ASI).
l 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, 3.2.5 for RCS Flow Rate, and 3.2.7 for ASI).
l 9)
" Calculational 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, 3.2.5 for RCS Flow Rate, and 3.2.7 for ASI).
ARKANSAS - UNIT 2 6-21 Amendment No. M7,M4,M9,
ADMINISTRATIVE CONTROL
- CORE OPERATING LIMITS REPORT
- 10) "CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam l
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 and Group P Insertion Limits, 3.2.4.b for DNBR Margin, and 3.2.5 for RCS Flow Rate).
- 11) Letter:
0.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:
0.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:
K. Kniel (. RC) to A.E. Scherer (CE), dated September 27, 1977 N
(Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, supplement 1-P).
NRC approval for 6.9.5.1.9 methodology.
- 14) Letter: 2CNA038403, dated March 20, 1984, J.R. Miller (NRC) to l
J.M. Griffin (AP&L), "CESEC Code Verification." NRC approval for 6.9.5.1.10 methodology.
l
- 15) " 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 CEA Insertion Limits, 3.2.4.b for DNBR Margin, and 3.2.5 for RCS Flow Rate).
- 16) " Qualification of Reactor Physics Methods for the Pressurized Water Reactors of the Entergy System," ENEAD-01-P, December 1993, Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin.
- 17) Letter: OCAN099519, dated September 29, 1995, G. Kalman (NRC) to F.W. Titus (Entergy Operations), NRC Staff Review of the Entergy Operations Topical Report ENEAD-01-P.
NRC approval for 6.9.5.1.16 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, 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 Inspector.
(
ARKANSAS - UNIT 2 6-21a Amendment No. M4,M4,MG,
4 4
j i
MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FOR INFO ONLY) i i
POWER DISTRIBUTTON LTMXTS iRCS FLOW RATE LIMITING CONDITION FOR OPERATION 3. 2.." The actual Reactor Coolant System total flow rate shall be g:::ter th:n :: :qu:1 t: 120.'. 10* lbr/hrwithin the limit provided in the CORE OPERATING LIMITS REPORT.
APPLICABILITY:- MODE 1.
ACTION:
With the actual Reactor Coolant System total flow rate determined to be less than the above limit, reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 1
4.2.5 The actual Reactor Coolant System total flow rate shall be determined to be within its limit at least once por 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l ARKANSAS - UNIT 2 3/4 2-7 Amendment No. G4,FA,
/
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, 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 NTC, 3.1.?.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 Jroup 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, 3.2.5 for RCS Flow Rate, and 3.2.7 for ASI).
l 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, _ 3.2. 5 for RCS Flow Rate, and 3.2.7.for l
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, 3.2.5 for RCS Flow Rate, and 3.2.7 for l
ASI).
7)
" Calculative Methods for the CE Large Break LOCA F luation Model for the Analysis of CE and W Designed NSSS," iUN-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, 3.2.5 for RCS Flow Rate, and 3.2.7 for ASI).
l 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, 3.2. 5 for RCS Flow Rate, and 3.2.7 for ASI).
l 9)
" Calculational Methods for the CE Small Break LOCA Evaluation Model,"
CENPD-137, Supplement 1-P, January 1977 (Methodoloav for Specifigation 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate. 3.2.3 for Azimuthal Power Tilt, 3.2.5 for RCS Flow Rate, and 3.2.7 for ASI).
ARKANSAS - UNIT 2 6-21 Amendment No. M7,M4,M9,
~
ADMINISTRATIVE CONTROL
- CORE OPERATING LIMITS REPORT 4
910) "CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam l
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 Tor Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating CEA and Group P Insertion Limits, end-3.2.4.b for DNBR Margin, and 3.2.5 for RCS Flow Rate).
]
110) Letter:
0.D. Parr (NRC) to F.M.
Stern (CE), dated June 13, 1975 l
j (NRC Staff Review of the Combustion Engineering ECCS Evaluation i
Model). NRC approval for 6.9.5.1.4, 6.9.5.1.5, and 6.9.5.1.8 methodologies.
121) Letter:
0.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:
K.
Kniel (NRC) to A.E.
Scherer (CE), dated September 27, 1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Sucolement 1-P).
NRC approval for 6.9.5.1.9 methodoloov.
I 14G) Letter: 2CNA038403, dated March 20, 1984, J.R. Miller (NRC) to l
J.M. Griffin (AP&L), "CESEC Code Verification." NRC approval for 6.9.5.1 109 methodology.
l 151 " Technical Manual for the CENTS Code," CENPD 282-P-A, February 1991 JMethodoloav for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Marain, 3.1.1.4 for MTC, 3.1.3.1 for CEA Position, 3.1.3.6 for Reculatina and Group P CEA Insertion Limits, 3.2.4.b for DNBR M, and 3.2.5 for RCS Flow Rate).
- 16) " Qualification of Reactor Physics Methods for the Pressurized Water Reactors of the Entercy System," ENEAD-01-P, December 1993, Methodoloav for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown
- Marcin, j
- 17) Letter:
OCAN099519, dated September 29, 1995, G.
Kalman (NRC) to F.W. Titus (Enterav Operations), NRC Staff Review of the Enteray Operations Topical Report ENEAD-01-P.
NRC acoroval for 6.9.5.1.16 methodoloav.
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.
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.
ARKANSAS - UNIT 2 6-21a Amendment No. M7,M4,M9,