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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20247A7101998-04-30030 April 1998 Rev 0 to 97-R-1012-03, ANO-1 Cycle 15 Colr ML20198M7921998-01-12012 January 1998 Rev 1 to ANO-1 Cycle 14 to Colr ML20210P3121997-08-20020 August 1997 Rev 2 to 96-R-2015-02, ANO-2 COLR for Cycle 13 ML20140E0381997-06-0404 June 1997 Rev 0 to 96-R-2015-02, ANO - Unit 2 COLR for Cycle 13 ML20129A6491996-10-14014 October 1996 Rev 0 to ANO-1 Cycle 14 Colr ML20117M3631996-09-0505 September 1996 Rev 1 to ANO Unit 2 COLR for Cycle 12 ML20101B9401996-03-11011 March 1996 Rev 1 to Pages 13 & 14 of 20 to ANO-1 Cycle 13 Colr ML20094A2001995-10-24024 October 1995 Rev 0 to 95-R-2003-01, Entergy Operations ANO-2 COLR for Cycle 12 ML20081J8291995-03-23023 March 1995 ANO 1 Cycle 13 Colr ML20065L8301994-04-13013 April 1994 COLR for Cycle 11 ML20046A2451993-07-22022 July 1993 Rev 0 to Core Operating Limits Rept for Cycle 10. ML20101A5481992-04-23023 April 1992 Rev 0 to Arkansas Nuclear One - Unit 1 Cycle 11 Core Operating Limits Rept ML20028G7821990-06-30030 June 1990 Cycle 10 Reload Rept. ML20207J0361988-06-30030 June 1988 Cycle 9 Reload Rept ML20213F2131986-11-0707 November 1986 Errata to Arkansas Nuclear One,Unit 1 Cycle 8 Reload Rept, Correcting Figure 1-3 to Change thrice-burned Lead Test Assembly from NJ023Q to NJ023P ML20210C1541986-08-31031 August 1986 Cycle 8 Reload Rept ML20098F1351984-08-31031 August 1984 Cycle 7 Reload Rept ML20071A1481983-02-11011 February 1983 Corrected Page 8-11,Figure 8-10 to 821119 Cycle 6 Reload Rept ML20083P1861983-01-27027 January 1983 Corrected Page 9-2 of 821119 Cycle 6 Reload Rept ML20069M1261982-07-31031 July 1982 AR Nuclear One,Unit 1 Cycle 6 Reload Rept, Including Proposed Tech Spec Changes ML20063G8911982-05-31031 May 1982 to AR Nuclear One,Unit 1,Cycle 5 Reload Rept ML19350C6651981-03-30030 March 1981 CEA Guide Tube Surveillance Program at End of Cycle 1, Reload Outage. ML20008E6861981-03-0505 March 1981 Cycle 2 Reload Analysis Rept, Remaining sections.Marked-up Tech Specs Encl ML20148T2291981-02-20020 February 1981 Cycle 2 Reload Analysis Rept ML19341B5371981-01-31031 January 1981 AR Nuclear One,Unit 1,Cycle 5 Reload Rept. ML19339A5501980-07-31031 July 1980 Cycle 5 Reload Rept. ML20148J7041978-10-31031 October 1978 Cycle 4 Reload Report ML19326B7161977-11-30030 November 1977 Cycle 3 Reload Rept. ML19326C0041976-11-30030 November 1976 Cycle 2 Reload Rept. Nonproprietary Version 1999-09-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) 0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with ML20212G6381999-02-25025 February 1999 Ano,Unit 2 10CFR50.59 Rept for 980411-990225 ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20199F0351998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ano,Units 1 & 2 ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With1998-12-11011 December 1998 LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20198D2441998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20195B4801998-11-0707 November 1998 Rev 20 to ANO QA Manual Operations ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with ML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 0CAN099803, Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with ML20237B7671998-08-19019 August 1998 ANO REX-98 Exercise for 980819 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed 0CAN089804, Monthly Operating Repts for July 1998 for Ano,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ano,Units 1 & 2 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20236R0531998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ano,Units 1 & 2 ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage 1999-09-30
[Table view] |
Text
. . . .. . - .-. . . . .. .. . _. . . - . _ _ _ . ._
f 4 i
i ENTERGY OPERATIONS I ARKANSAS NUCLEAR ONE - UNIT 2 4
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4 4
. CORE OPERATING LIMITS REPORT f FOR CYCLE 13 I
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9706110216 970604 PDR ADOCK0500g8
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CORE OPERATING LIMITS REPORT FOR CYCLE 13 4
INDEX PAGE I. INTRODUCTION 3 II.
SUMMARY
OF CHANGES 3 III. AFFECTED TECHNICAL SPECIFICATIONS 4 I
IV. CORE OPERATING LIMITS 5 i
- V. METHODOLOGES 7 VI. LIST OF FIGURES 8 1
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i ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 13 h
L IN TRODUCTION
}-
This CORE OPERATING LIMITS REPORT (COLR) has been prepared in accordance with the requirements of Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.9.5 for ANO-2's Cycle ?J. The core operating limits have been developed using the NRC approved methodologies specified in Section V. This is Revision 0 of the Cycle 13 COLR.
IL
SUMMARY
OF CliANGES Listed b: low are the changes to the COLR from the latest revision of the Cycle 12 COLR.
-
- The specifc values for MTC have been upf,ated for cycle 13.
- The PDIL for Group 6 and P has been combined into one PDIL with a restriction regarding simultaneous insertion above 80% power.
e The COLSS cut of service limit lines have been updated. Additionallines were added to the I g CEAC operable plot to reflect the new analyses.
1
/
- The CENTS code was added to the reference list.
i The statement of' Movable Control Assemblies' was removed from the CESEC reference to be j consistent with the actual technical specification title.
E
[; 3 96-R-2015-02 Revisica o
1
. [IL- AFFECTED TECHNICAL SPECIFICATIONS l
- 1) 3/4.1.1.1 Shutdown Margin - Tavg > 200*F I
- 2) 3/4.1.1.2 Shutdown Margin - Tavg s200 F ,
l 3) 3.1.1.4 Moderator Temperature Coefficient l
l 4) 3.1.3.1 CEA Position
- 5) 3.1.3.6 Regulating CEA Insenion Limits
- 6) 3/4.2.1 Linear Hect Rate
- 7) 3.2.3 Azimuthal Power Tilt - Tq
- 8) 3/4.2.4 DNBR Margin I
- 9) 3.2.7 Axial Shape Index 1
l 1 l l
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s . .
t !
IV. ' CORE OPERATING LIMITS The cycle-specific operating limits for the specifications listed are presented below.
- 1) 3/4.1.1.1 - SHUTDOWN MARGIN- Ta> 200*F The SHUTDOWN MARG {N shall be greater than or equal to 5.0 % Ak/k in Modes 1,2, ,
3, and 4.
- 2) 3/4.1.1.2 - SHUTDOWN MARGIN - T 3yg s 200*F The SHUTDOWN MARGIN shall be greater than or equal to 5.0% Ak/k in Mode 5. ;
- 3) 3 1.1.4 - MODERATOR TEMPERATURE COEFFICIENT The Modernor Temperature Coefficient (MTC) shall be:
a) in accordance with Figure 1 b) less negative than - 3.4 E-4 A k/k/*F at RATED THERMAL POWER
- 4) 3.1.3.1 - CEA POSITION With one or more CEAs trippable but misaligned from any other CEAs in its group by more than the Technical Specification 3.1.3.1 allowed value, the minimum required core power reduction for Modes 1 and 2 is specified in Figure 2.
- 5) 3.1.3.6 - REGULATING CEA INSE~ R TION LIMITS The regulating CEA groups (groups 6 & P) shall be limited to the withdrawal and insertion limits shown on Figure 3. Figure 3 assumes that Banks 1 through 5 are fully withdrawn.
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i l
- 6) 3/4.2.1 - LINEAR HEAT RATE With COLSS out of service, the linear heat rate shall be maintained s 13.5 kw/ft .
- 7) 3.2.3 - AZIMUTHAL POWER TILT- T2 The measured AZIMUTHAL POWER TILT shall be maintained s 0.03.
- 8) 3/4.2.4 - DNBR MARGIN The DNBR limit shall be maintained by one of the following methods:
With COLSS in service and neither CEAC operable - Maintain COLSS calculated ;
a) !
core power less than or equal to COLSS calculated core power operating limit '
based on DNBR decreased by 13%. 1 With COLSS out of service and at least one CEAC operable - Operate within the b)
Region of Acceptable Operation shown on Figure 5, using any operable CPC channel.
With COLSS out of service and neither CEAC operable - Operate within the c)
Region of Acceptable Operation shown on Figure 6, using any operable CPC channel.
- 9) 3.2.7 - AXIAL SHAPE INDEX The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
a) COLss IN SERVICE
- 0.27 s ASI s + 0.27 b) COLSS OUT OF SERVICE (CPC)
- 0.20 s ASI s + 0.20 6
96-R-2 "
Rivi . < a
V. ' METHODOLOGIES The analytical methods used to determine the core operating limits listed above are those previously reviewed and approved by the NRC in:
- 1) "The ROCS and DIT Computer Codes for Nuclear Design," CENPD-266-P-A, April 1983. Methodology for the limit on Shutdown Margins, MTC, DNBR Margin and the l l
CEAInsertion Limits.
- 2) "CE Method for Control Element Assembly Ejection Analysis," CENPD-0190-A, January j 1976. Methodology for the CEA Insenion Limits and Azimuthal Power Tilt. ;
- 3) " Modified Statistical Combination of Uncertainties," CEN-356(V)-P-A, Revision 01-P-A, May 1988. Methodology for the limits on the DNBR Margin and the ASI.
" Calculative Methods for the CE Large Break LOCA Evaluation Model," CENPD-132-P, 4)
August 1974. Methodology for the limits on the Linear Heat Rate and Azimuthal Power
' Tilt. ;
" Calculational Methods for the CE Large Break LOCA Evaluation Model," <
- 5) )
CENPD-132-P, Supplement 1, February 1975. Methodology for the limits on the MTC, Linear Heat Rate, Azimuthal Power Tilt and ASI.
- 6) " Calculational Methods for the CE Large Break LOCA Evaluation Model,"
CENPD-132-P, Supplement 2-P, July 1975. Methodology for the limits on the MTC, Linear Heat Rate, Azimuthal Power Tilt and ASI. l
" Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis 7) of CE and y{ 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.
" Calculational Methods for the CE Small Break LOCA Evaluation Model,"
- 8) j CENPD-137-P, August 1974. Methodology for the limits on the MTC, Linear Heat Rate, Azimuthal Power Tilt and ASI.
- 9) "CESEC - Digital Simulation of a Combustion Engineering Nuclear Steam Supply System," December 1981. Methodology for the limits on the Shutdown Margins, MTC, CEA Position, CEA Insenion Limits, and DNBR Margin.
" Technical Mar.ual for the CENTS Code," CENPD 282-P-A, February 1991 Methodology 10) for the Tunits on the Shutdown Margins, MTC, CEA Position, CEA Insenion Limits, and DNBR Margin.
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\
VL LIST OF FIGURES Figure 1. Moderator Temperature Coefficient 4
Figure 2. Required Power Reduction After CEA Deviation Figure 3. CEA Insertion Limits Versus Thermal Power Figure 4. Intentionally Deleted Figure 5. DNBR Margin Operating Limit Based on Core Protection
- Calculators (COLSS Out of Sewice, CEAC Operable) 4 Figure 6. DNBR Margin Operating Limit Based on Core Protection l
Calculators (COLSS Out of Service, Bo:h CEACs Inoperable) i j
i 1
i 1
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i FIGURE 1 MODERATOR TEMPERATURE COEFFICIENT 5.00E-05 l I I ~
Unacceptable ~
^ ,
Operating Region (0,0 33) N .
(20,0.2) 0.00E+00 (50'0)
N N
\
-5 00E-05 (90,.0.4) (100,. 42)
-1.00E-04 j Acceptable Operating' -
Region
_ -1.50E-04 u.
W g 2 00E-04 s
-2.50E 04 l
- l
-3 00E-04 l
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-3.40E-04 j '
-3.50E-04 40 50 60 70 60 90 100 0 10 20 30 CORE POWER (% OF RATED THERMAL POWER) 96-R-2015-02 9 Revision 0
t FIGURE 2 REQUIRED POWER REDUCTION AFTER CEA DEVIATION
- aWhen core power is reduced to 60% of rated power per this limit curve, further reduction is not required 30 1
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g 20 p (60 MIN.;20%)
g i Ew Wg #
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.ar LO y ;g o$
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z 0 e 2 0 15 30 45 60 TIME AFTER DEVIATION (MINUTES) 10 96-R-2015-02 Revision 0 ,
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3 FIGURE 3 4
CEA INSERTION LIMITS VERSUS TilERMAL POWER Groups 6 and P PDil(1)
Simultaneous insertion of Group 6 AND P Prohibited unless during a downpower 110
'/
(112.5,100) r" 100 - Transient insertion Line 90
! (60,82.5) A 80 (135,74)l. 'y
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(O. 82.5) g 70 s (112.5, 65)
~ 60 %
l ii!$ % PA-
(60, 44)
$ $ '.h E
- s #> 2
(0,20 20 S$ $$3$$ %
10 4
0 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0 -10 CEA Position, Inches WKi;. .tawn ,
h
- 1) Regulating Banks 1 through 5 in Full-Out Position i
i l
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. ._ -- . . . ~ .._. ___ __ _ _ _ . . . _ _ _ . - . _ . . - _. . . . .. __
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FIGURE 4 ,
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GROUP P INSERTION LIMIT VERSUS THERMAL POWER ;
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INTENTIONALLY DELETED j
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96-R-2015-02 :
Revision 0
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FIGURE 5 4
DNBR MARGIN OPERATING LIMIT BASED l ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC OPERABLE)
ANO-2 Cycle independent COOS Limit
! Minimum 1 CEAC Operable 2.8 ACCEPTABLE OPERATION Any Power Level 27' (om,2.es) f 1
(o.03,2.se) l 2.6- j ACCEPTABLE OPERATION 2.5 - Power at or above 80% !
l 1 (4.20 2.4s) l (0.20,2.as)
D 2.4-N (4.to,2.as)
B R 2.3 - (4.2o, tso)
ACCEPTABLE OPERATION Power at or above 90%
(
2.2-(4. o,2.ce) 2.1 om,2.oe) l
( 4.20, 2.01) 2.0 - UNACCEPTABLE OPERATION l Any Power Level 1.9
-0.30 -0.20 -0.10 0.00 0.10 0.20 0.30 CPC Indicated ASI 13 96-R-2015-02 Revision 0 W
, 1 FIGURE 6 i
DNBR MARGIN OPERATING LIMIT BASED f ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACS INOPERABLE) j i
l 4 .1 b,
ANO-2 Cycle Independent COOS Limit
)
Both CEACs Inoperable
- 3.2 ACCEPTABLE OPERATION
' Any Power level 3.0 -
- 1 (o.04,2.se)
' (o.20,2.so)
\
1 2.8 -
l D
I N B
J R j 2.6 (4.20,2.as) l UNACCEPTABLE OPERATION j
! Any Power Level i
l 2.4 1
)
j 2.2
-0.10 0.00 0.10 0.20 0.30
-0.30 -020 CPC Indicated ASI
' 14 96-R-2015-02 Revision 0