ML20085N163

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Proposed Tech Specs Removing Specific Variables to Add in Core Operating Limits Rept
ML20085N163
Person / Time
Site: Arkansas Nuclear 
Issue date: 11/07/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20085N162 List:
References
NUDOCS 9111140159
Download: ML20085N163 (47)
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Text

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PROPOSED TECHNICAL SPECIFICATION PAGES 9111140139 911107 PDR ADOCK 05000313

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TABLE OF CONTENTS S1011D8 IllLE PAGE 1.

DEFINITIONS 1

1.1 RATED POWER 1

1.2 REACTOR OPERATING CONDITION 1

1.3 OPERABLE 2

s 1.4 PROTECTION INSTRUMENTATION LOGIC 2

1.5 INSTRUMENTATION SURVEILLANCE 3

1.6 POWER DISTRIBUTION 4

1.7 REACTOR BUILDING 5

1.8 FIRE SUPPRESSION WATER SYSTEM 5

1.9 STAGGERED TEST BASIS 5

1.10 RADIOLOGICAL EFFLUENT TECliNICAL SPECIFICATIONS Sa (PETS) DEFINITIONS 1.11 CORE OPERATIi1G LIMITS REPORT 6

l 2.

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 7

2.1 SAFETY LIMITS REACTOR CORE 7

2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE 10 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION 11 3.-

LIMITING _[QHDITIONS FOR OPERATIDN 16 3.1 REACTOR COOLANT SYSTEM 16 3.1.1 Doerational Comoonents 16

-3.1.2 Pressurization. Heatuo and Cooldown Limitatigns 18 3.1.~3 Minimum Conditions for Criting111y 21 3.1.4-Reactor Coolant System Activity 23 13.1.5 Chemistry 25 3.1 6 Leakaae 27 3.1.7 Moderator Temoerature Coef ficient of Reactivity 30 3.1.8 Low Power Physics Testina Restrictions 31 3.1.9 Control Rod Operation 32 3.2 MAKEUP AND CHEMICAL ADDITION SYSTEMS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, AND REACTOR BUILDING SPRAY SYSTEMS 36 3.4 STEAM AND POWER CONVERSION' SYSTEM 40

3. 5' INSTRUMENTATION SYSTEMS-

-42 3.5.1 Doerational Safety Instrumentation 42 3.5.2 fontrol Rod Group and Power Distribution Limi13 46 3.5.3 SABLty_fu tates Actuation System Selp h 49 3.5.4 Incore Instrumentation 51 3.5.5 Eire Detection Instrumentation 53d 3.5.6 Radioactive Liauid Effluent Instrumentation 53f 3.5.7 Radioactive Gasgqqs Efflu. tat Instrumentation-531 3.6 REACTOR BUILDING 54-3.7 AUXILIARY ELEClRICAL SYSTEMS 56 3.8 FUEL LOADING AND REFUELING 58 3.9 CONTROL ROOM EMERGENCY AIR CONDITIONING AND ISOLATION SYSTEM 60 3.10 SECONDARY SYSTEM ACTIVITY 66 3.11 EMERGENCY COOLING POND 66a 3.12 MISCELLANEOUS RADIDACTIVE MATERIALS SOURCES 66b 3.13 PENETRATION ROOM VENTILATION SYSTEM 66c Auendment No. EE, SS, i

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LIST OF FIGURES

.- thlalba.t lille EA9e 2.1-1 CORE PROTECTION SAFE 1Y LIMITS 9a 2.1 CORE PROTECT. ION SAFETY LIMITS 9b 2.1-3 CORE PROTECTION SAFETY LIMITS 9c 2.3-1 PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINT 14a 2.3-2 PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS 14b 3.1.2 REACTOR COOLANT SYS1EM HEATUP AND C00LOOVN LIMITATIONS 20a 3.1.2-2 REACTOR COOLANT SYSTEM NORMAL OPERATION-HEATUP 20b LIMITATIONS 3.1.2-3 REACTOR COOLANT SYSTEM, NORMAL OPERATION C00LDOWN 20c LIMITATIONS 3.1.9-1

. LIMITING PRESSURE VS. TEMPERATURE FOR CONTROL R00 DRIVE 33 OPERATION WITH 100 STD CC/ LITER H-0 3.2-1 BORIC ACID ADDITION TANK VOLUME AND CONCENTRATION VS, RCS 35a AVERAGE TEMPERATURE 3.5,4-1

-INCORE INSTRUMENTATION SPECIFICATION AXIAL IMBALANCE 53a INDICATION 3.5.4-2 INCORE INSTRUMENTATION SPECIFICATION RADIAL FLUX TILT 53b INDICATION 3.5.4-3 INCORE INSTRUMENTATION SPECIFICATION 53c 3.24-1 HYDROGEN LIMITS FOR ANO-1 WASTE GAS SYSTEM 110bc 4.4.2-1 NORMALIZED LIFTOFF FORCE - HOOP TENDONS 85b

-4.4.2-2 NORMALIZED LIFT 0FF FORCE - DOME TENDONS 85c 4.4.2-3 NORMALIZED LIFTOFF FORCE - VERTICAL TENDONS 85d 4.18.1 UPPER TUBE SHEET-VIEW 0F SPECIAL GROUPS PER SPECIFICATION 110o2 4.18.3.a.3 5,1-1 MAXIMUM AREA BOUNDARY FOR RADIOACTIVE RELEASE CALCULATION lila (EXCLUSION AREA) 6.2-1 MANAGEMENT ORGANIZATION CHART 119 6.2-2 FUNCTIONAL ORGANIZATION FOR PLANT OPERATIONS 120 Amendment No. E2, 7J, 92,105, JJ3, iv

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-_-__,.._--._.._.___..-._._._....._.___.____..y DELETED Amendment No. Et, E0, M, 92, 93, y

97, 105, 111, lil,

DELETED Amendment No. $$, ES, 92, vi 1

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- Amendment No. SS, 5b 1

.1 1

l 1.10,8 tiemberb),.oltheJuhlis Member (s) of the Public shall include all persons who are not occupationally associated with the plant.

This c? dory does not include employees of the utility, its contractors or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

1.10.9 ExclusiorLAtta The exclusion area is that area surrounding ANO within a minimum l

radius of.65 miles of the reactor buildings and controlled to the extent necessary by the licensee for purposes of protection of individuals from expoture to radiation and radioactive materials.

1.10.10 L!ntultl1LeiAr1A An unrestricted area shall be any area beyond the exclusion area boundary.

1.11 CORE OPERATING LIMITS rep 0R1 L

. The CORE OPERAllNG LIMITS REPORT is the ANO-1 specific document that provides core operating limits for the current operating reioad cycle.

These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.12.3.

Plant operation within these operatin, limits is addressed in individual specifications.

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Amendment No. 9.

6

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If a control rod in the regulating or axial power shaping I

groups - is declared inoperable per Specification 4.7.1.2 operation above 60 percent of the thermal power allowable for the reactor coolant pump combination may continue provided the rods in the group are positioned such that the i

rod that was declared inoperable is contained within allowable group average position limits of Specification 4.7.1.2 and the withdrawal limits of Specification 3.5.2.5.3.

3.5.2.3 The worth of single inserted control rods during criticality are limited by the restrictions of Specificatior, 3.1.3.5 and the Control Rod Position Limits defined in $pecification 3.5.2.5.

3.5.2.4 Quadrant Power Tilt:

1.

Except for physics teste, if quadrant power tilt exceeds the tilt limit set in the CORE OPERATING LIMITS REPORT, reduce power so as not to exceed the allowable power level for the existing reactor coolant pump combination less at least E%

for each l'4 tilt in excess of the tilt limit.

2.

Within a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the quadrant power tilt shall be reduced to less than the tilt limit except for physics tests, or the following adjustments in setpoints and limits shall be made:

a.

The protection system traximum allowable setpoints (Figure 2.3-2) shall be reduced 2%-in power for each 1%

tilt in excess of the tilt limit, b.

The control rod group and Ap5R withdrawal limits shall be reduced 2% 'in power for each 1% tilt in excess of g

the tilt limit.

c.

The reactor power imbalance setpoints shall be reduced 2% in power for each 1% tilt in excess of the tilt limit.

3.

If quadrant power tilt is in excess of 25%, except for physics tests or diagnostic testing, the reactor will be placed in the hot shutdown condition.

Diagnostic testing during pcwer operation with a quadrant power tilt is-permitted provided the thermal power allowable for the reactor coolant pump combination is restricted as stated in 3.5.2.4.1 above.

- 4 Quadrant power tilt shall be monitored on a minimum i

frequency of once every two hours during power operation above 15% of rated power.

Amendment No. 6, RJ, /J, $3, Pl. JPE, 47 Ji?. 177.

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3.

Except for physics tests or exercising control rods, the i'

control rod position setpoints are specified in the CORE OPERATING LlH11S REPORT for 4, 3,

and 2 pump operation.

If the applicable control rod position setpoints are exceeded, corrective measures shall be taken in, mediately to c hieve an acceptable control rod position.

Acceptable control rod positions shall be attained within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.

Except for physics tests or exercising axial power shaping rods (ApSR$). the limits for ApSR position are specified in the CORE OPERATING LlH115 REPORT.

With the APSRs outside the specified limit provided in the CORE OPERATING LIMITS REPORT, corrective measures shall be taken immediately to achieve the correct position.

Acceptable APSR positions shall be attained within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3.5.2.6 Reactor Power Imbalance:

1.

Rea: tor power imbalance shall be monitored on a frequency not to exceca 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during power operation above 40% rated power.

2.

Except for physics. tests, reactor power imbalance shall be maintained within the envelope defined by the CORE OPERATING LIMITS REPORT.

3.

If the reactor power imbalance is not within the envelope defined by the CORE OPERATING LIMITS REP 0F corrective measures shall be taken to achieve an acces wie reactor power imbalance.

4.

If an acceptable r: actor power imbalance is not achieved within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, reactor power shall be reduced until reactor-power imbalance setpoints are met.

3.5.2.7 The control rod drive patch panels shall be locked at all times with limited access to be authorized by the Superintendent.

- Bun The reactor power imbalance envelope defined in the CORE OPERATit40 LIMITS REPORT is based on LOCA analyses which have defined the maximum linear heat rate (see CORE OPERATING LIMITS REPORT), such that the maximum cladding

temperature will not exceed the Final Acceptance Criteria.

Corrective

= measures vill be taken immediately should the indicated quadrant power l

tilt, control; rod - position, or - reactor power imbalance be outside their specified boundaries.

Operation in a situation that would cause the Final Acceptance -Criteria to be approached should a LOCA occur is highly improbable because all of the power distribution parameters (quadrant power tilt, rod position, and reactor power imbalance) must be at their limits while Amendment No. E, /J, JJ, A), N, J0E 48 JJ1, J77,

The quadrant power tilt limits set forth in the CORE OPERAllNG LIMITS l

REPORT have been established within the thermal analysis design base using the definition of quadrant power tilt given in lechnical Specifications, Section 1.6.

These limits in conjunction with the control rod position setpoints in the CORE OPERA 11NG LIM 11$ REPOR1, ensure that design peak heat rate criteria are not exceeded dur;ng normal operation when including the effects of potential fuel densification.

The quadrant power tilt limits and reactor power imbalance setpoints in the CORE OPERA 11NG LIM 11$ Rfp0R1, apply when using the plant computer to monitor the limits.

The 2-hour frequency for monitoring these quantities will provide adequate surveillante when the computer is out of service.

Additional uncertainty is applied to the limits when other monitoring methods are used.

During the physics testing program, the high flux trip setpoints are administrative 1y set as follows to ensure that an additional safety margin is provided.

L 1 L 10Kct I.thdtt1%luta_L 0

(5 15 50 40 50 50 60 75 85 75 105.5 EllIEEEfuS (1) FSAR, Section 3.2.2.1.2 (2) FSAR, Section 14.2.2.2 Amendment No. H, P/,

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Rod Position Sotpoints for 4-Pump Operation from 30 410/-0 to 335 410/-10 EFPD ANO-1 Cycle 10 rigure 3. 5. 2 - 1 11 DELETED Amendment No.;/05, JJ3, 131, 4Rc k

Rod Position Setpoints for 4 - Pump Operation Af ter 335 410/-10 EPPD ANO 1 Cycle 10 riguro 3.5.2-10 del.ETF.D Amendment No. J M, JJ), 137, 48d

Rcxl Position Setpoints for 3+ Pump Operation from 0 to 30 410/-0 ETPD -- ANO-1 Cycle 10 riguro 3.5.2-2A del.ETED l

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Rod Position Sotpoints for 3-Pump Operation From'30 410/-0 to 335 410/-10 1:FPD -- ANO-1 Cycle 10 riguro 3.$.2-2B DI:LETED i

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Amendment No 19), 1J), J)/,

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i Oparational l'ower 1mbalanen Sotpoints for Operation

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l' rom 30 +10/-0 to 335 410/-10 EITD -- AND-1. Cycle 10 l'igu re 3. 5. 2 - 4 11 i

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6.12.3-CORE OPERATING LIMITS REPORT

- 6.12.3.1 The core operating limits shall be established and documented in the CORE OPERATING LIM 115 REPORT prior to each reload cycle or prior to any remaining part of a reload cycle.

t 6.12.3.2 1he analytical methods used to determine the core operating limits addressed by the individual Technical Specification shall be those previously reviewed and approved by the NRC for use at AtM 1 specifically:

1.

Babcock & Wilcox Topical Report BAW-10122A Rev. 1, " Normal Operating Controls," May 1984.

2.

Babcock & Wilcox Topical Report BAW-10116-A " Assembly Calculations and Fitted Nuclear Data " May 1977.

Babcock & Wilcox Topical Re Wilcox Version of PDQ User' port BAW-10117P-A, " Babcock &

3.

s Manual," January 1977.

4.

Babcock & Wilcox Topical Report BAW-10118A, " Core Calculational Techniques and Procedures," December 1979.

5.

Babcock & Wilcox Topical Report BAW-10124A, " FLAME 3 A Three-Dimensional Nodal Code for Calculating Core Reactivity and Power Distributions." August 1976.

6.-

Babcock & Wilcox Topical Report BAW-10125A, " Verification of Three-Dimensional FLAME Code," August 1976.

i 7.

Babcock & Wilcox Topical Report BAW-10152A, " NOODLE-A MultiaDirsensional Two-Group Reactor Simulator," June 1995.

8.

Babcock & Wilcox Topical Report BAW-10119, " Power Peaking Nuclear Reliability factors," June 1977.

6.12.3.3 The core operating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS 1%its, nuclear limits such as shutdown margin,-and transient arid accident analysis limits) of the safety analysis are met.

6.12.3.4 The. CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance for each reload cycle to the NRC Document Control Desk with copies to.the Regional Administrator and Resident Inspector.

l 1

Amendment No. 7A 79. PE, JJE, 142 (noxt page is 146) i T

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i ENTERGY OPERATIONS ARKANSAS NUCLEAR ONE - UNIT 1 i

t CYCLE 10 t

I CORE ~ OPERATING LIM 11S REPOR1 i

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i ENTERGY OPERATIONS ARKANSAS NUCl. EAR ONE - UNIT ONE CYCLE 10 CORE OPERATING LIM 11$ REPORT 1.0 CORE OPERATING LIM 115 This CORE-OPERAllNG LIMITS REPORT for ANO-1 Cycle 10 has been prepared in accordance with-the requirements of Technical Specification 6.12.3.

The Core Operating Limits have been developed using the methodology

-l provided in the references..

The:following cycle-specific core-operating limits are included in this j

report:

1)

Regulating control rod position setpoints

]

2)

Reactor power _ imbalance setpoints 3)

LOCA limited maximum allowable linear heat rate limits 4)

Axial power shaping rod insertion limits e

5)

Quadrant power tilt limits l

V COLR

.2 of 19 Revision 0--

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M I4 ' 'll I

2.0 REFERENCES

1)

Babcock & Wilcox, lopical Report BAW-10122A, Rev.1, " Normal Operating Controls," May 1984.

2)

Babcock & Wilcox, lopical Report BAW-10ll6-A, " Assembly Calculations and fitted Nuclear Data," May 1977.

3)

Babcock & hilcox, Topical Report BAW-10ll7P-A, " Babcock & Wilcox Ver 'on of PDQ User s Manual," January 1977.

4)

Babcock & Wilcox, Topical Report BAW-10ll8A, " Core Calculational Techniques and Procedures," December 1979.

5)

Babcock & Wilcox Topical Report BAW-10124A, " FLAME 3 - A Three-Dimensiona$NodalCodeforCalculatingCoreReactivityand Power Distributions," August 1976.

6)

Babcock & Wilcox Topical Report BAW-10125A, " Verification of Three-DimensionalFLAMECode," August 1976.

7)

Babcock & Wilcox Topical Report BAW-10152A, "N000LE

-AMulti-DimenslonalTwo-GroupReactorSimulator," June 1985.

8)

Babcock &Wilcox,TopicalRegortBAW-10119,"PowerPeaking Nuclear Reliability factors, June 1977.

COLR 3 of 19 Revision 0

TABLE Of CON 1LNTS pag Regulating Rod Position Setpol.its for 4-Pump Operation 5

from 0 to 30 + 10/-0 EfPD Regulating Rod Position Setpoints for 4-Pump Operation 6

from 30 + 10/-0 to 335 i 10 EfPD Regulating Rod Position Setpoints for 4-Pump Operation 7

af ter 3351 10 EfPD l

Regulating Rod Position Setpoints for 3-Pump Operation 8

i from 0 to 30 + 10/-0 EfPD Regulating Rod Position Setpoints for 3-Pump Operation 9

from 30 4 10/-0 to 335 1 10 EfPD Regulating Rod Position Setpoints for 3-Pump Operation 10 after 335110 EfPD t

Regulating Rod-Position Setpoints for 2-Pump Operation 11 from 0 to 30 + 10/-0 EfPD Regulating Rod Position Setpoints for 2-Pump Operation 12 from 30 + 10/-0 to 335 i 10 EfPD Regulating Rod Position Setpoints for 2-Pump Operation

.13 af ter 3351 10 LFPD Operational Power.lmbalance Setpoints for Operation from 14 0 to 30 4 10/-0 EfPD Operational Power Imbalance Setpoints for Operation 15 from 30 + 10/-0 to 335 1 10 LfPD Operational ~ Power Imbalance Setpoir,ts for Operation 16 l

after 335110 EfPD

- LOCA Limited Maximum Allowable Li_1 ear Heat Rate Limits 17 Axial Power Shaping Rod Insertio's Limits 18 Quadrant Power. Tilt timits 19 I

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COLR 4 of 19 Revision 0

Figure is referred to by Technical Specification 3.5.2.L j

Rod Position Setpoints for Four-Pump Operation from 0 to 30 +10/-0 CFPD -- ANO-1 Cycle 10 110 (200.9,102)

(300,102)

(272.9.102);

100 SHUTOOWN

.,90) 90 MARGIN LIMIT 80 OPERATION IN THIS e

REG!ON IS NOT f

ALLOWED OPERATION (255.5,78) 70 m

RESTRICTE0 N

60

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(227.5,48) c.

40 PERMISSIBLE 30 OPERATING 20 10 (73.5.13)

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20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0

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Figure is referred to by Technical Specificatit,n 3.5.2.5 Rod Position Setpoints for Four-Pump Operation From 30 +10/-0 to 335 1 10 EFPD --

i ANO-1 Cycle 10 i

110 (300.102)

(200.9.102)

(270.1.102);

100 SHUTDOWN (266.5.90) l 90 MARGIN LIMIT ag 80 (251.5,78) m OPERATION IN THIS

?

E 70 REGION IS NOT OPERATION ALLOWED o-RESTRICTED 1

60 g

s' i

[50 (109.5.48)

(227.5.48) a.

40 30 PERMISSIBLE OPERATING-REGION 20 10 (73.5.13)

.(0,0).0 1

I I

I I

I I

I I

I i

l I

l_

0 20 40 60 80 100 120 140 160 180 200 220 240.260 280 300 0

20 40 60-80 100-I f

I e

i I -.

-t Group 7

.0-20 40 60-80 100

.I I

I I

I I

Group 6 0

20-'40 60 80 100 1

I I

I t

i Rod index. % WD i

Group 5 j

COLR Page-_6 of 19

=-

Revision-0

~. _,... _.... _ _ _., _ - _ _.. _. -. - _ _

h Figure.is referred to by Technical Specification 3.5.2.5 Rod Position Setpoints for Four-Pump Operation After 335 110 EFPD -- ANO-1 Cycle 10-110 (215.0,102)

(300,102)

(270.1,102)-

100

. SHU100WN OPERATION IN THIS MAFjlN (266.5,90) 90 LIM T REGION IS NOT h

(251.5,78) e

~

OPERATION RESTRICTED e

60 C

[ 50

. (121.5,48)-

(227.5,48) 40 30 PERMISSIBLC OPERATING 20 4

REGICN 10 (79.5.13)

I i

1 I

I I

I I

I I

I I

I (0,0) 0,

20 40 60 80 100 120 140 160 180 200 7?n 240 -260 280 300 O

0 20 40 60 - 80 100 i

f f

I I

t Group 7 0

20 40 60 80 100-1 I

f-f I

1 Group 6 0.

20 40 60 80 100 I

I I

I t

i Rod Index, % WD Group 5 COLR Page 7 of 19 Revision 0

Figure is referred to by Technical Specification

3. 5. E. 5 Rod Position Setpoints for Three-Pum: Oa ration From 0 to 30 +10/-0 EFF0 -- ANO-1 Cy -le r 110 i

100.

90 (300,77) 80 (202.0,77)

(273.0,77) h SHUTDOWN 70 MARGIN (270.5,67) )>

e

-l 60 OPERATION IN THIS LIMIT

/

REGION IS NOT (255.5,58) m-C

. ALLOWED 50 --

J OPERATION E

RESTRICTED

. o 40 (109.5,36)

(227.5,35.5) 3a 20 PERMISSIBLE OPERATING REGION L

10 (0,'0) 0 -

1 I

I l

l I

I I

l 0-20 -40 60 80 100 120 140 160 180 200 220 240 260 280 300 0

20 40 60 80 '100 I

t t

i I

Group 7 0

20 40 60 80 100 i

f I-f l

i Group 6 1

y u

0 20 40 60.

80~

100 I

1 e

t i

Rod Index, % WD

]

Group 5 i

COLR 4

Page 8 of 19 Revision 0

.~.

Figure is referred to by Technical Specification 3.5.2,5 Rod Position Setpoints for Three-Pump Operation From 30 +10/-0 to 335 110 EFPD -- ANO-1 Cycle 10 110 100 90 80 (202.0,77)

(300 77)

(270.3,77) e E

SHUTDOWN O

~

MARGIN' (266.5,67)

OPERATION IN THIS LIMIT 60 REGION IS NOT

}.

(251.5.58) m ALLOWED e

~

f OPERATION 40 (109.5,36)

(227.5,35.5) 30

~

PERMISSIBLE OPERATING' 10

~

(73.5,9.8)

REGION

-(0,0)0{

t i

I I

I l

t 1

1 I

I i

1

.0

'20 -40 60 80 100 120 140 160 180 200 220 240 260 280 300 O

20-40 60 80 100 t

i f

f I

I Group 7 0

20 40 60 80-100 i

f:

I l'

I t

l Group 6 0

20 40 60' 80 100 i

I t

I t

Rod Index, % WD Group 5 COLR Page 9 of 19 L

Revision 0 L

rigure is re* erred to b

schnical Specification 3.5.2.5-Rod Position Setpoints for Three-Pump Operation After 335 110 EFPD - ANO-1 Cycle 10 110 100

.90 (300,77)

(270.3,77) 80 (216.1,77)

E

$ 70 OPERATION IN THIS SHUTDOWN (266.5,67)

N.

REGION IS NOT MARGIN ALLOWED LIMIT (251.5,58) g ; 60 w

c 50 OPERATION RESTRICTED

,i

" 40 (121.5,36)

(227.5,35.5)-

30 20 PERMISSIBLE OPERATING 10 (79.5,9.8)

REGION IO'o) i I

i i

I i

I I

I I

i i

1 0

20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0

20 40 60 80 100 1

1 1

1 1

1 Gimup 7 0

20 40 60 80 100 t

t t

t i

I Group 6 0

20 40 60- 80 100

-1 1

I t

t 1

Rod Index, % WD Group 5 COLR Page 10 of 19 Revision 0

Figure is referred to by-Technical. Specification 3.5,2.5 Rod Position Setpoints for Two-Pump Operation From 0 to 30 +10/-0 EFPD -- ANO-1 Cycle 10

--110 100 90

} 80 cai '70 N

g.

60 (204.3,52)

(300,52)

$ - ~ 50 (273.2,52)

OPERATION IN THIS SHUTDOWN o'

REGION-IS NOT MARGIN (270.5,44) 40 ALLOWED LIMIT (255.5,38) e OPERATION 30 R TRICTED (199.5,24)

20 PERMISSIBLE 10 OPERATING-(73,5,6,5).

REGION:

(O'0) 0 1

1 l

l I

t i

i l'

I i

i

~0 20 40 60 80 100- 120 140' 160 180 200-.220 240 260 280 30C r

0 20 40 60 80 100 t

i I

i-1 I

Group 7 0

20 40

-60 80 100 l'

1 I

1 1

I Group 6 0

20 40 60 80 100 1

I I

I I

I Roc Index, % WD Group 5 COLR Page 11 of 19 Revision 0

Figure is referred to by Technical Specification 3.5.2.5 Rod Position Setpoints for Two-Pump Operation From 30 +10/-0 to 335 110 EFPD -- ANO-1 Cycle 10 110 100 90 y 80 5

,0 g

o (300,52}

~

(204,3,52)

(270.5,52) -

g 50 2

OPERATION IN THIS S

REGION IS NOT SHUTOOWN (266.5,44)

ALLOWED MARGIN 40 (251.5,38)

LIMIT OPERATION 30 RESTRICTED (109.5,24)

(227.5,23)

PERMISSIBLE OPERATING 10 (73.5,6,5 REGION I

I I

I I

I I

I I

I I

I (0,0) 0 6 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0

20 40 60 80 100 t

I l

i I

1 Group 7 0

20 40 60 80 100 t

i 1

1 1

1 Group 6 0

20 40 60 80 100 1

I i

1 1

1 Rod Index, % WD Group 5 COLR Page 12 of 19 Revision 0

l Figure is referred to by Technical Specification 3.5.2.5 Rod Position Setpoints for Two-Pump Operation After 335 110 EFPD -- ANO-1 Cycle 10-110 100 90 l 80 c3

% 70 o" 60 (300,52) 50 OPERATION IN THIS SHUTDOWN (218.4.52)

(270.5,52)-

2 REGION'IS NOT MARGIN (266.5*44)

ALLOWED-LIMIT 40 (251.5.38) 30

-(121.5,24)

OPERATION RESTRICTED (227.5.23) 20 PERMISSIBLE 10 (79.5,6.5 OPERATING REGION (0,0) 0 I

I I

I l

i I

I l

-l I

I 0'

20 40 60 80 100 120 140 160-180 200 220 240 260 280 300 0

20-40 60 80 100-t i

1 1

1 I

Group 7 0

20 40 60 80 100 t

f 1

f f

1 Group 6 0

20 40-60 80-100 I

I I

1 I

I Rod Index, % WD Group 5 COLR Page 13 of 19 Revision 0

Figure is referred to by Technical Specification

_ 3. 5. 2, 6 Operational Power Imbalance Setpoints for Operation From 0 to 30 +10/-0 EFPD -- ANO-1 Cycle 10

. 110

~

(-15.05,102)

- (13.93,102)

-100

( 6.97,92)

(-16.15,92)

-90

(-22.10,80) 80

>(20.05,80) w w

-RESTRICTED de Ode RESTRICTED REGION-G5 G5 REGION

$W5

$75

-60 g g g g5g E8E ESE

- 50 o (20.50',50)

_(-22.50,50)o ak.-- 40 30 v4

~ 20

~

I E. 10 I

I I

1

=1 1

1 1

1

-50'~ -40 -10 0

10 20 30 40 50 Axial-Power Imbalance, %

COLR Page 14 of 19 Revision 0

~_

t figure'is referred to by Technical Specification 3.5.2.6 Operational Power Imbalance Setpoints -for Operation From 30 +10/-0 to 335 110 EFPD -- ANO-1 Cycle 10

- 110

- (17.53,102)

(-19.61,102)

(20.59,92)

(-20.72,92) 90 80,

,(23.68,80)

(-23.80,80)< w se se 705$y=

RESTRICTED 5h2 RESTRICTED gg REGION REGION ggo

$ES 60 S E w

c. c a
c. o a

(-24.26,50),

50 o (24.18,50) a 40

$n 30 C

D4 20 c.

I2-

'10 t

i f

f f

I I

I f

f 1-30 -20

-10 0

10 20 30 40 50 Axial Power Imbalance,.%

COLR Page 15 of 19 Revision 0

Figure is referred to by Technical Specification 3.5.2.6 Operational Power Imbalance Setpoints for.-

Operation After 335 110 EFPD -- ANO-1 Cycle 10

- - 110

- (17.58,102)

(-20.47,102)

(21.59,92)

(-21.59,92) 90

(-23.71,80)<

80 m(23.71,80)

RESTRICTED

$e 70 m e.

RESTRICTED REGION g=

g=

REGION

~~

SWE

$45 55G 60 5 5 G E8e M&M 50 o (24.19,50)

(-24.19,50) o.

a f

40 i

N

- - 30 mo te 20 b

to i

I I

I I

t t

i t

I -40 -20

-10 0

to 20 30 40 50 Ax!al Power Imbalance,' %

COLR Page 16 of 19 Revision 0

Liinits are referred to by Technical Specification 3.~5.2 Bases LOCA' Limited Maximum Allowable Linear Heat ~ Rate -- ANO-1 Cycle 10 20 d 18-Y

.w 4

._ w 16

.o E

/

/-

e 5

-/

5 14 R

E S

E 12 O to.1000 mwd /mtU z

After 1000 mwd /mtU 10 e

i i

e i

e i

i e

i 0

2 4

6 8

10 12 Axial Location From Bottom of Core, ft COLR l

Page 17 of 19 Revision 0

_ ~

g<

.+

LIMITS ARE REFERRED TO BY TECHNICAL SPECIflCATION 3.5.2.5.4-AXIAL POWER SHAPING R00 INSERTION LIMITS Up to 345 EfPD, the APSRs may be positioned as necessary for transient imbalance control, however, the APSRs shall be fully withdrawn by 345 EFPD.

After 345 EfPD, the APSRs shall not be reinserted.

COLR 18 of 19 Revision 0 l

.. ~.

. ~.. -.. _..

-VALUES ARE REFERRF' TO BY TECHNICAL SPECIFIf'.JN 3.5.2.4 1

ANO-1 CYCLE 10 TILT VALUES Tilt Limit Maximum Limit full ~Incore Symmetrics 4.24%

25.0'5 6

i l-L COLR 19 of 19 Revision 0 9

g w

.m y-

.--

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