View source for NL-06-069, Revised Core Operating Limits Report, Cycle 18

{{Adams
| number = ML061800344
| issue date = 06/22/2006
| title = Revised Core Operating Limits Report, Cycle 18
| author name = Conroy P
| author affiliation = Entergy Nuclear Northeast
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000247
| license number = DPR-026
| contact person = 
| case reference number = NL-06-069
| document type = Fuel Cycle Reload Report, Letter type:NL
| page count = 37
}}

=Text=
{{#Wiki_filter:EnteraE Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Patric Conroy Manager, Licensing Tel 914 734 6668 June 22, 2006 Re:     Indian Point Unit 2 Docket No. 50-247 NL-06-069 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

==Subject:==
Revised Core Operating Limits Report for Indian Point Unit 2

==Dear Sir/Madam:==

Please find attached Core Operating Report (COLR) for Indian Point Unit 2 Cycle 18 in accordance with the Indian Point 2 Technical Specifications 5.6.5.d which presents the cycle-specific operating limits for the operation of Indian Point Unit 2. Also included are two Cycle 17 mid-cycle revisions.
There are no new commitments being made in this submittal. If you have any questions or require additional information, please contact Patric Conroy, Manager, Licensing at (914) 734-6668.
Sincerely, Manager, Licensing Indian Point Energy Center : Indian Point 2 COLR - Cycle 18 : Indian Point 2 COLR - Cycle 17 Mid-Cycle Revisions cc: next page

Docket 50-247 NL-06-069 Page 2 of 2 cc: Mr. Samuel J. Collins, Regional Administrator, NRC Region I Mr. John Boska, Senior Project Manager, NRC NRR DORL NRC Resident Inspector's Office, Indian Point 2

ENCLOSURE 1 TO NL-06-069 Indian Point 2 Cycle 18 COLR ENTERGY NUCLEAR OPERATIONS, INC. "
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247

I.
Procedure Use Is:      Control Copy:
E3 Continuous b
Effective Date: ,5/, ?/2 6, Nuclear Northeast o   Reference 0 Information          Page 1 of 11 CORE This procedure Is excluded from further I Approved By:
a*r ProcedZre Sponsor, RPO i Team Staff Procedure Owner PARTIAL REVISION

Indian Point Unit 2 Cycle 18 COLR Page 2 of 11 TABLE OF CONTENTS SECTION                                                                                                                                                       PAGE TS 2.0   Safety Limits (SLs) ....................................................................................................................                3 TS 3.1.1 Shutdown Margin (SDM) ..................................................................................................                                3 TS 3.1.3 Moderator Temperature Coefficient (MTC) ....................................................................                                            3 TS 3.1.5  Shutdown Bank Insertion Limits ...................................                                                                                     3 TS 3.1.6 Control Bank Insertion Limits .....................................                                                                                     4 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor F ...................................................................                                          4 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology) ...... 4 TS 3.3.1 RPS Instrumentation ...........................................................................................................                         5 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)
Lim its...........................................................................................................................................      5 TS 3.9.1 Refueling Boron Concentration ........................................................................................                                  5 ATTACHMENTS Attachment I    Overtemperature AT & Overpower AT Allowable Values ................................                                                              6 FIGURES Figure 1 Reactor Core Safety Limit - Four Loops In Operation .....................................................
Figure 2 Rod Bank Insertion Limits ...................................................................................................                           9 Figure 3 Hot Channel Factor Normalized Operating Envelope ........................................................                                              10 Figure 4 Axial Flux Difference Envelope Limits ................................................................................                                 II

Indian Point Unit 2 Cycle 18 COLR Page 3 of I1 NOTE The Technical Specification references shown next to each Factor OR Limit in this COLR, are there to identify the corresponding sections in the Technical Specifications, that refer to the COLR.
The data presented in this report applies to Cycle 18 ONLY and may NOT be used for other cycles of operation. Any technical change to this document requires a Safety Evaluation to be performed in accordance with 10 CFR 50.59.
TS 2.0 Safety Limits ,SLs)
In MODE I and 2, the combination of thermal power level, pressurizer pressure, and highest loop average coolant temperature SHALL not exceed the limits shown in Figure 1.
The safety limit is exceeded if the point defined by the combination of Reactor Coolant System average temperature and power level is at any time above the appropriate pressure line.
TS 3.1.1 Shutdown Margin (SDM)
The shutdown margin SHALL be greater than or equal to 1.3% Ak/k.
TS 3.1.3 Moderator Temperature Coefficient (MTC)
The MTC upper limit SHALL be < 0.0 Ak/k/OF at hot zero power.
The MTC lower limit SHALL be > -36.5 pcm/F @ 300 ppm
                                   > -43.0 pcm/F @ 60 ppm
_ -45.5 pcm/F @ 0 ppm Reference Graph RV-12 for cycle specific predicted MTC.
TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn when the reactor is in MODE 1 and MODE 2. Shutdown Banks with a group step counter demand position > 221 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.

Indian Point Unit 2 Cycle 18 COLR Page 4 of II TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE I and MODE 2 with kef > 1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply to the step counter demand position.
TS 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))
I                              NOTE K(Z) is the fraction given in Figure 3 AND Z is the core height location of Fo.
IF P > .5, FQ(Z) < (2.50 P) x K(Z)
IF P< .5, FQ(Z) - (5.00) x K(Z)
TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FPN NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
FNH < 1.70 {1 +0.3(1 -P)}
TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)
Methodology)
The Indicated limit is the Target Band; i.e., the Target +/- 5%
The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 4, as required by TS 3.2.3.

Indian Point Unit 2 Cycle 18 COLR Page 5 of II TS 3.3.1 RPS Instrumentation
: 1. Overtemperature AT      Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1.
Refer to Attachment 1
: 2. Overpower AT            Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 6, Note 2.
Refer to Attachment I TS 3.4.1 RCS Pressure,          Temperature,      and   Flow Departure      from    Nucleate Boiling (DNB) Limits The following DNB related parameters are applicable in MODE 1:
: a. Reactor Coolant System average Tj,v9 : 568.1 OF and highest loop T,,g < 571.1 OF
: b. Pressurizer Pressure;> 2216 psia
: c. Reactor Coolant System Total Flow Rate;> 348,300 gpm TS 3.9.1 Refueling Boron Concentration When required by Technical Specification 3.9A1, the minimum boron concentration in the RCS, Refuel Canal, and Reactor Cavity SHALL be the more restrictive of either
> 2050 ppm or that which is sufficient to provide a shutdown margin > 5% Ak/k.

Indian Point Unit 2 Cycle 18 COLR Page 6 of 11 Attachment I (Page 1 of 2)
Overtemperature AT The Overtemperature AT Function Allowable Value SHALL not exceed the following:
Note: Forlimitations on the maximum trip Setpoint see Technical Specification3.3.1.
r{    K3 (1+ rS)[T-T,]+K,(p- P')-f,(AI)}
AT<AT"~ K"- (I+'       + s)                                 V Where:     AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform opr.r.tor,        "
T is the measured RCS average temperature, OF.
T' is the loop specific indicated Ta"g at RTP, OF.
P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, > 2235 psig Ki < 1.22                    1K2> 0.020/&deg;F           K3 > 0.00070/psig
           -tl;&#x17d; 25 sec                 '12:< 3 sec fl(AI) =    -1.97 {30 + (qt- qb)}     when qt- qb<- 30% RTP 0% of RTP                 when -30% RTP < qt- qb < 7% RTP 2.25 {(qt- qb) - 7)       when qt- qb > 7% RTP Where qtand qbare percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

Indian Point Unit 2 Cycle 18 COLR Page 7 of 11 Attachment I (Page 2 of 2)
Overpower AT The Overpower AT Function Allowable Value SHALL not exceed the following:
Note: Forlimitations on the maximum trip Setpoint see TechnicalSpecification 3.3.1.
AT :-ATo        -K
                        ,"     +, s T -K.(T-T")-f,(A, fon     -K 5 (1+lrs)                         4 Where:    AT is measured RCS AT, OF.
AT0 is the loop specific indicated AT at RTP, 'F.
s is the Laplace transform operator, sec 1 .
T is the measured RCS average temperature, OF.
T" is the loop specific indicated Tan at RTP, OF.
K(45 1.074            K5 > 0.01 88/&deg;F for increasing Tavg Ke k 0.0015PF when T > T" 01/F for decreasing Tan        0/&deg;F when T < T' 13 ; 10 sec f2(AI) = 0

Indian Point Unit 2 Cycle 18 COLR Page 8 of I I Figure 1 Reactor Core Safety Limit - Four Loops in Operation (Page I of 1) 6M8O 2440 psia 660*                        //                        UNACCEPTABLE 660-640-"
620-62-     2250 psia           /
, 600-0                      2000 psla FRACTION OF RATED POWER

Indian Point Unit 2 Cycle 18 COLR Page 9 of I I Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 100 Step Overlap (Page I of 1) 225 200                 FO (IOO,14 I  175 150 0
z  125 0
be                                                          ......
z 4
0  75 W*
50 25 0
0 10 20   30     40      50     60     70    80     90        100 Power Level (Percent of Rated Power)

Indian Point Unit 2 Cycle 18 COLR Page 10 of l1 Figure 3 Hot Channel Factor Normalized Operating Envelope (For S. G. Tube Plugging up to 10%)
(Page I of 1) 1.2 1.0 I-00 0.8 CL "o
0.6 N
0 0.4 zE N
0.2 0
0        2         4          6       8     10         12 Core Elevation (feet)

Indian Point Unit 2 Cycle I8 COLR Page 11 of 11 Figure 4 Axial Flux Difference Envelope Limits (Page I of 1)
'80 30      -20    -10        0       10   20     30 ,      40 Axial Flux Difference

ENCLOSURE 2 TO NL-06-069 Indian Point 2 Cycle 17 COLR Mid-Cycle Revisions ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247

Procedure Use Is: Control Copy:
9mEntergy.                         [3 Continuous D Reference Effective Date:__ ______-"
Nuclear Northeast P,!nformation     Page 1 of 11 2-                     -    -V -       09 CORE C                 TING LIMITS R            T (COLR)
This procedure Is excluded from fui   .vlews Approved By:.
Pro   ueSosr     P      V51ynice   Uale Team Staff Procedure Owner EDITORIAL REVISION

REVISION 

==SUMMARY==

1.0 REASON FOR REVISION 1.1  Change Attachment I Page 2 of 2 OPDT T3 from
* to > per CR IP2-2005-02150 CA #7 and Feedback IP2-6268. (Editorial 4.6.1) 2.0 

==SUMMARY==
OF CHANGES 2.1  Change Attachment I Page 2 of 2 OPDTr 3 from < to > per CR IP2-2005-02150 CA #7 and Feedback IP2-6268. (Editorial 4.6.1)

TABLE OF CONTENTS SECTION                                                                                                                                PAGE TS 2.0 Safety Limits (SLs) .........................................................................................................      4 TS 3.1.1 Shutdown Margin (SDM) ................................................................................................           4 TS 3.1.3 Moderator Temperature Coefficient (MTC) .....................................................................                    4 TS 3.1.5 Shutdown Bank Insertion Limits .....................................................................................             4 TS 3.1.6 Control Bank Insertion Limits .........................................................................................          5 TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) ................................................................................            5 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor F ...............................................................                       5 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology) ......                                           5 TS 3.3.1 RPS Instrumentation ....................................................................................................        6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ..... 6 TS 3.9.1 Refueling Boron Concentration .......................................................................................           6 ATTACHMENTS Attachment I Overtemperature AT & Overpower AT Allowable Values .........................................                                7 FIGURES Figure 1 Reactor Core Safety Limit - Four Loops in Operation .......................................................                     9 Figure 2 Rod Bank Insertion Limits .............................................................................................        10 Figure 3 Hot Channel Factor Normalized Operating Envelope .........................................................                     11

NOTE The Technical Specification references shown next to each Factor OR Limit in this COLR, are there to identify the corresponding sections in the Technical Specifications, that refer to the COLR.
The data presented in this report applies to Cycle 17 ONLY and may NOT be used for other cycles of operation. Any technical change to this document requires a Safety Evaluation to be performed in accordance with 10 CFR 50.59.
TS 2.0 Safety Limits (SLs)
In MODE 1 AND 2, the combination of thermal power level, pressurizer pressure, and highest loop average coolant temperature SHALL NOT exceed the limits shown In Figure 1. The safety limit is exceeded IF the point defined by the combination of Reactor Coolant System average temperature AND power level is at any time above the appropriate pressure line.
T"S 3.1.1 Shutdown Margin (SDM)
The shutdown margin SHALL be greater than OR equal to 1.3% Ak/k.
TS 3.1.3 Moderator Temperature Coefficient (MTC)
The MTC upper limit SHALL be < 0.0 Ak/k/&deg;F at hot zero power.
The MTC lower limit SHALL be > -36.5 pcm/F @ 300 ppm
                                   * -43.0 pcm/F @ 60 ppm
                                   * -45.5 pcm/F @ 0 ppm Reference Graph RV-12 for cycle specific predicted MTC.
TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn WHEN the Reactor is in MODE I AND MODE 2. Shutdown Banks with a group step counter demand position > 221 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.

TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE 1 AND MODE 2 with keff > 1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply to the step counter demand position.
TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
NOTE K(Z) is the fraction given in Figure 3 AND Z is the core height location of Fa.
IF P > .5, Fa(Z) < (2.50 1 P) x K(Z)
IF P,_..5, Fa(Z) < (5.00 ) XK(Z)
TS 3.2.2 Nuclear EnthalpyV Rise Hot Channel Factor FNH NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
FNH<I.70 {1 +0.3(1--P)}
TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology The Indicated Axial Flux Difference limit is the Target Band; i.e., the Target +/-5%
The Axial Flux Difference Envelope Limits at 90 percent power are -11%, + 11% AND increase by -1% and +1%, for each 2% of rated power below 90% power, as indicated by Graph RV-10, Unit 2 Target Flux Values.

TS 3.3.1 RPS Instrumentation
: 1. Overtemperature AT        Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1.
Refer to Attachment 1
: 2. Overpower AT              Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 6, Note 2.
Refer to Attachment I TS 3.4.1 RCS Pressure, Temperature and Flow Departure From Nucleate Boiling (DNB)
Limits The following DNB related parameters are applicable in MODE 1:
: a. Reactor Coolant System average Tavg < 565.1OF and highest loop Tvg < 568.1 OF
: b. Pressurizer Pressure > 2216 psia
: c. Reactor Coolant System Total Flow Rate > 348,300 gpm TS 3.9.1 Refueling Boron Concentration WHEN required by Technical Specification 3.9.1, the minimum boron concentration in the RCS, Refuel Canal AND Reactor Cavity SHALL be the more restrictive of either > 2050 ppm OR that which is sufficient to provide a shutdown margin k 5% Ak/k.

Attachment I Overpower AT & Overtemperature AT Allowable Values (Page 1 of 2)
Overtemperature AT The Overtemperature AT Function Allowable Value SHALL NOT exceed the following:
NOTE For limitations on the maximum trip setpoint see Tech Spec 3.3.1 A T5AT.{ K-K,:       (         [T-T']+K,(P- P)-fdA I T KK,(1+*,,s))-)f(I}
Where:    AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
AT0 is the loop specific Indicated AT at RTP, OF.
s is the Laplace transform operator, sec".
T is the measured RCS average temperature, 'F.
T' is the loop specific indicated Tavg at RTP, OF.
P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, > 2235 psig K15*1.22                     K2 k  0.020/&deg;F           K3 > 0.00070/psig
             ?:k 25 sec                 ,r2< 3 sec f,(AI) =     -1.97 {30 + (qt- qb))     when qt- qb:< - 30% RTP 0% of RTP                 when -30% RTP < qt- qb < 7% RTP 2.25 {(qt- qb) - 7)       when qt- qb > 7% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb Is the total THERMAL POWER In percent RTP.

Attachment I Overpower AT & Overtemperature AT Allowable Values (Page 2 of 2)
Overpower AT The Overpower AT Function Allowable Value SHALL NOT exceed the following:
NOTE For limitations on the maximum trip setpoint see Tech Spec 3.3.1 AT <AT{K,-Kog(1*S              T -K.(T-T")-f 2 (AI)}
Where:   AT is measured RCS AT, OF.
ATO is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec"1 .
T is the measured RCS average temperature, OF.
T" is the loop specific indicated Twg at RTP, OF.
K45 1.074            Ks> 0.0188/&deg;F for increasing Tivn  Ke > 0.0015/&deg;F when T > T" 0/1F for decreasing Tavg      01OF when T < T" S3&#x17d; 10 sec f2 (AI) = 0

Figure 1 Reactor Core Safety Limit - Four Loops In Operation 2440 psla UNACCEPTABLE OPERATION
   ~2250    Iosla 90 6mm-22000          psla FRACTION OF RATED POWER

Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 100 Step Overlap 225 200 175 uJ 150 (0
0~ 125 I-z                                                          I 0
100 o
I 75 50 25 0
0 10 20   30     40L    50      60     70    80 90 100 Power Level (Percent of Rated Power)

Figure 3 Hot Channel Factor Normalized Operating Envelope (For SG Tube Plugging up to 10%)
1.2 0.0. 1.00oo                  6,  1.
1.0 112.0,0o.925'I 03 0.8 UL-
-   0.6 o
                                                --         ,0 I--
T  0.4
 -E N
0.2 0          2             4        6        8         10          12 Core Elevation (feet)

T Procedure Use Is:   Control Copy:
03 Continuous Effective Date: 7/L1/,;t5 Nuclear Northeast            E3 Reference 21&#xfd; Information     Page 1 of 11 2-(                                      10 CORE 01              TING LIMITS R               .T (COLR)
This procedure Is excluded from fui       lews Approved By:.
a ure Sposr   P                                                               0r Team Staff Procedure Owner PARTIAL REVISION

                              'REVISION   

==SUMMARY==

1.0 REASON FOR REVISION 1.1  Revise to address Unit 2 Tavg increase to 565&deg;F as supported by Westinghouse analysis. (Ref IPP-04-129) 2.0 

==SUMMARY==
OF CHANGES 2.1  Revised DNB related parameters as follows:
* TS 3.4.1 criteria on Page 6 of 11: changed average Tavg from < 565.1&deg;F to
            <_568.1&deg;F.
e TS 3.4.1 criteria on Page 6 of 11: changed highest loop Tavg from < 568.1 OF to
            < 571.1OF 2.2  Changed the value r3 for Overpower AT on Page 8 from r3 > 10 sec to T3 = 10 sec. to ensure Unit 2 Technical Specifications, The Unit 2 Core Operating Limits Report and 2-GRAPH-RPC-6 are consistent until Unit 2 Technical Specifications are corrected.

TABLE OF CONTENTS SECTION                                                                                                                                 PAGE TS 2.0 Safety Limits (SLs) .........................................................................................................      4 TS 3.1.1 Shutdown Margin (SDM) .................................................................................................          4 TS 3.1.3 Moderator Temperature Coefficient (MTC) ......................................................................                   4 TS 3.1.5 Shutdown Bank Insertion Limits .....................................................................................             4 TS 3.1.6 Control Bank Insertion Limits .............................................................................................. 5 TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) ............................................................................                5 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor F*AH ...................................................................                5 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology) ......                                            5 TS 3.3.1 RPS Instrumentation ......................................................................................................       6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ..... 6 TS 3.9.1 Refueling Boron Concentration .....................................................................................              6 ATTACHMENTS Attachment 1 Overtemperature AT & Overpower AT Allowable Values .........................................                                 7 FIGURES Figure 1 Reactor Core Safety Limit - Four Loops in Operation .....................................................                        9 Figure 2 Rod Bank Insertion Limits ...............................................................................................       10 Figure 3 Hot Channel Factor Normalized Operating Envelope .........................................................                      11

NOTE The Technical Specification references shown next to each Factor OR Limit in this COLR, are there to identify the corresponding sections in the Technical Specifications, that refer to the COLR.
The data presented in this report applies to Cycle 17 ONLY and may NOT be used for other cycles of operation. Any technical change to this document requires a Safety Evaluation to be performed in accordance with 10 CFR 50.59.
TS 2.0 Safety Limits (SLs)
In MODE 1 AND 2, the combination of thermal power level, pressurizer pressure, and highest loop average coolant temperature SHALL NOT exceed the limits shown in Figure 1. The safety limit is exceeded IF the point defined by the combination of Reactor Coolant System average temperature AND power level is at any time above the appropriate pressure line.
TS 3.1.1 Shutdown Margin (SDM)
The shutdown margin SHALL be greater than OR equal to 1.3% Ak/k.
TS 3.1.3 Moderator Temperature Coefficient (MTC)
The MTC upper limit SHALL be < 0.0 Ak/k/&deg;F at hot zero power.
The MTC lower limit SHALL be > -36.5 pcm/F @ 300 ppm
                                   * -43.0 pcm/F @ 60 ppm
                                   * -45.5 pcm/F @ 0 ppm Reference Graph RV-1 2 for cycle specific predicted MTC.
TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn WHEN the Reactor is in MODE 1 AND MODE 2. Shutdown Banks with a group step counter demand position ; 221 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.

TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE I AND MODE 2 with keff _>1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply to the step counter demand position.
TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
NOTE K(Z) is the fraction given in Figure 3 AND Z is the core height location of Fo.
IF P > .5, Fa(Z) < (2.50/ P) x K(Z)
IF P::5.5, Fo(Z) - (5.00) x K(Z)
TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FN NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
FmN< 1.70 {1+0.3(1-P))
TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology The Indicated Axial Flux Difference limit is the Target Band; i.e., the Target +/-5%
The Axial Flux Difference Envelope Limits at 90 percent power are -11%, + 11% AND increase by -1% and +1%, for each 2% of rated power below 90% power, as indicated by Graph RV-1 0, Unit 2 Target Flux Values.                                              I

TS 3.3.1 RPS Instrumentation
: 1. Overtemperature AT        Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1.
Refer to Attachment 1
: 2. Overpower AT              Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 6, Note 2.
Refer to Attachment 1 TS 3.4.1 RCS Pressure, Temperature and Flow Departure From Nucleate Boiling (DNB)
Limits The following DNB related parameters are applicable in MODE 1:
: a. Reactor Coolant System average Tag < 568.1 OF and highest loop Tavg < 571.1 OF
: b. Pressurizer Pressure > 2216 psia
: c. Reactor Coolant System Total Flow Rate k 348,300 gpm TS 3.9.1 Refueling Boron Concentration WHEN required by Technical Specification 3.9.1, the minimum boron concentration in the RCS, Refuel Canal AND Reactor Cavity SHALL be the more restrictive of either 2!2050 ppm OR that which Is sufficient to provide a shutdown margin k 5% Ak/k.

Attachment I Overpower AT & Overtemperature AT Allowable Values (Page 1 of 2)
Overtemperature AT The Overtemperature AT Function Allowable Value SHALL NOT exceed the following:
NOTE For limitations on the maximum trip setpoint see Tech Spec 3.3.1 ATAT 1T;T   {K-K K,^(1        ,S)[T.T,]+Ki(P" P)-f,(AI)}
(1++ ns)                               0 Where:    AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
AT0 is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec*1 .
T is the measured RCS average temperature, OF.
T' is the loop specific indicated Tavg at RTP, OF.
P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, > 2235 psig Ki < 1.22                    K2 &#x17d;  0.0201&deg;F           K3 > 0.0070/psig TI &#x17d; 25 sec                 T2 *3  sec fl(AI) =    -1.97 {30 + (qt- qb)}     when qt- qb!< - 30% RTP 0% of RTP                 when -30% RTP < qt- qb < 7% RTP 2.25 {(qt- qb) - 7}       when qt- qb > 7% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

Attachment I Overpower AT & Overtemperature AT Allowable Values (Page 2 of 2)
Overpower AT The Overpower AT Function Allowable Value SHALL NOT exceed the following:
NOTE For limitations on the maximum trip setpoint see Tech Spec 3.3.1 T :SAT# K,'K         '   3S    T -K,(T-T")-f,(A Where:    AT Is measured RCS AT, &deg;F.
AT0 is the loop specific Indicated AT at RTP, OF.
s is the Laplace transform operator, sec"t .
T is the measured RCS average temperature, OF.
Tr is the loop specific indicated Ta, at RTP, OF.
K4<1.074             1K5' 0.0188/0F for Increasing Tsg Ke > 0.0015/1F when T > T" 0/OF for decreasing Tavn     0/&deg;F when T s T c3 = 10 sec fM(AI) = 0

Figure 1 Reactor Core Safety Limit - Four Loops in Operation 650 U-ao FRACTION OF RATED POWER

Figure 2 Rod BankInsextion Limits (Four Loop Operation) 100 Step Overlap 225 200 00175r Q
Z    125 0
E C-   100 C)    75 soo 5OO O
25 0    10 20   30    40      50      60     70    80 90 100 Power Level (Percent of Rated Power)

Figure 3 Hot Channel Factor Normalized Operating Envelope'.
(For SG Tube Plugging up to 10%)
1.2 0.0,_1.00:               6.0, 1.00 1.0 I-                                                       12.0, 0.92.5
 &deg;0.8
* 0.6 0~
S0.4 E
N 0.2 0               a~~~                    -   -          - ~t 0        2           4        6         8        10          12 Core Elevation (feet)}}