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M CALVERT CLIFFS NUCLEAR POWER PLANT i
M CALVERT CLIFFS NUCLEAR POWER PLANT i
CORE OPERATING LIMITS REPORT for UNIT 2, CYCLE 12 I
CORE OPERATING LIMITS REPORT for UNIT 2, CYCLE 12 i
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-l 9705080235 970505 PDR ADOCK 05000318 PDR p
l l
Calvert Cliffs 2, Cycle 12 COI.it Page 1 of 22 llev 0
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9705080235 970505 PDR   ADOCK 05000318 p                     PDR Calvert Cliffs 2, Cycle 12 COI.it                 Page 1 of 22 llev 0


CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 2, CYCLE 12 l
CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 2, CYCLE 12 The following limits are included in this Core Operating Limits Report:
The following limits are included in this Core Operating Limits Report:                                                                                                                     l Soccification Titic                                                                                                                                                             Pg         I l
l Soccification Titic Pg l
introd uction .. ...........             . . . . . . . . .        . . . . . . . . . . . . . . . . .                ...          . . . . . . . .                  .4 2.2.1           Reactor Trip Setpoints.. .. . ........                                                   . . . . . . . . . . . . . . . . . . . . . . .                  .    .. 5 3.1.1.1           Shutdown Margin - Tavg > 200 *F . .. ................. .. . ... .                                           . . . . . . .....                      ........5 3.1.1.2         Shutdown Margin - Tavg $ 200 *F .. .                                                     .... .. ......                          ................5                       j 3.1.1.4         Moderator Temperature Coefficient ... . . ........ ... . . .. . .........................5 3.1.3.1         C EA Position .... ............... . ........... .. . ..                        . . . . . . .          . . . . .                  .............5 3.1.3.6         Regulating CEA Insertion Limits ....                                             .                            . . . . . . .    ...................5 3.2.1 -           Linear Heat Rate .. ....         . . . . . . . . . . . . . . . . . . . . . . . . . .                    .......................5 3.2.2.1         Total Planar Radial Peaking Factor . ........ .. . .. .. . . .. . . .. . . .                                                       . . . . . . . . . . .      ... 6 3.2.3           Total Integrated Radial Peaking Factor ... .............. .. . . ... ...... .                                                     . . . . . . . . .            .. . 6 3.2.5             DNB Parameters............ ..... . .. . .. . . .                                         . . . . . . . . . . . . . . .        .        . . .                    .6 3.9.1             Boron Concentration .... ... . ......................... ... .....                                             . . . . . . .        . . . . .              .. . 6 List of Approved Methodologies ... . . . .                             . . . .        . . . . . . . . . . . . .                      . . . . . . .            .19 The following figures are included in this Core Operating Limits Report:
introd uction.............
1 Number           Title                                                                                                                                                       P. age       i I
.4 2.2.1 Reactor Trip Setpoints.............
i Figure 2.2-1     Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power..                                                                         . . .          ...7 Figure 2.2-2     Thermal Margin / Low Pressure Trip Setpoint - Part 1.                                                       .          . . .            ..                      .8 Figure 2.2-3     Thermal Margin / Low Pressure Trip Setpoint - Part 2.                                                 . . . . . . . .                  ..              . . .. 9 Figure 3.1.1-1     Shutdown Margin vs. Time in Cycle. . . . .. . . . . . . . . . . . .                                                                    . . . .          . 10 Figure 3.1.3-1     Allowable Time To Realign CEA Versus                                                                                                                                     !
.. 5 3.1.1.1 Shutdown Margin - Tavg > 200 *F...........................
i Initial Total Integrated Radial Peaking Factor... . . .                                                   . . . .                      ..                . 11 Figure 3.1.3-2 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power .                                                                         . . .              . 12 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle . .                                                                 .                        ..        .      .13 Figure 3.2.1-2 Linear lleat Rate Axial Flux Offset Control Limits . .                                                       . . . . . .                  . . . .            .. 14           l Figure 3.2.1-3 Total Planar Radial Peaking Factor /Fxy ys,                       T                                                                                                         j Maximum Allowable Fraction of Rated Thermal Power .... ...                                                                         . . . . .        .. . 15             i Figure 3.2.2-1 Total Planar Radial Peaking Factor vs. Allowable Fraction of Rated                                                                                                           ;
........5 3.1.1.2 Shutdown Margin - Tavg $ 200 *F...
Thermal Power.. .. ... . ..             . . . . . . . . . . . . . .                            . . . . . . .                    . . .                        .16       l Figure 3.2.3-1 Total Integrated Radial Peaking Factor vs.                                                                                                                                   l Allowable Fraction of Rated Thermal Power .                                           ..              . . . . . .                . . .            .      .. 17 Figure 3.2.3 2 DNB Axial Flux Offset Control Limits .                                   .        .....                            ..                        .              .    .I8 i
................5 j
l Calvert Cliffs 2. Cvele 12 COLR                                             Pace 2 of 22                                                                                           Rev.1    ,
3.1.1.4 Moderator Temperature Coefficient.....................
1
.........................5 3.1.3.1 C EA Position..................................
.............5 3.1.3.6 Regulating CEA Insertion Limits....
...................5 3.2.1 -
Linear Heat Rate......
.......................5 3.2.2.1 Total Planar Radial Peaking Factor...........................
... 6 3.2.3 Total Integrated Radial Peaking Factor...............................
... 6 3.2.5 DNB Parameters..........................
.6 3.9.1 Boron Concentration.........................................
... 6 List of Approved Methodologies.......
.19 The following figures are included in this Core Operating Limits Report:
1 Number Title P. age i
I i
Figure 2.2-1 Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power..
...7 Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint - Part 1.
.8 Figure 2.2-3 Thermal Margin / Low Pressure Trip Setpoint - Part 2.
.... 9 Figure 3.1.1-1 Shutdown Margin vs. Time in Cycle.
. 10 Figure 3.1.3-1 Allowable Time To Realign CEA Versus Initial Total Integrated Radial Peaking Factor......
. 11 i
Figure 3.1.3-2 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power.
. 12 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle..
.13 Figure 3.2.1-2 Linear lleat Rate Axial Flux Offset Control Limits..
.. 14 Figure 3.2.1-3 Total Planar Radial Peaking Factor /Fxy ys, j
T Maximum Allowable Fraction of Rated Thermal Power.......
... 15 i
Figure 3.2.2-1 Total Planar Radial Peaking Factor vs. Allowable Fraction of Rated Thermal Power..........
.16 Figure 3.2.3-1 Total Integrated Radial Peaking Factor vs.
Allowable Fraction of Rated Thermal Power.
.. 17 Figure 3.2.3 2 DNB Axial Flux Offset Control Limits.
.I8 i
Calvert Cliffs 2. Cvele 12 COLR Pace 2 of 22 Rev.1


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,i ralvert Cliffs 2. Cvele 12 C01.11 l' ace 3 of 22 Itev. O


        .                                                                                                          i INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 2, Cycle 12.' It contains the limits for:
i INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 2, Cycle 12.' It contains the limits for:
1 I
1 Reactor Trip Setpoints Shutdown Margm Moderator Temperature Coefficient CEA Position Regulating CEA Insertion Limits Linear Heat Rate Total Planar Radial Peaking Factor Total Integrated Radial Peaking Factor DNB Parameters Refueling Boron Concentration in addition, this report contains a number of figures which give limits on the parameters listed above. If any of the limits contained in this report are exceeded, corrective action will be taken as defined in the Technical Specifications.
Reactor Trip Setpoints Shutdown Margm Moderator Temperature Coefficient
;                      CEA Position Regulating CEA Insertion Limits Linear Heat Rate Total Planar Radial Peaking Factor                                                           l Total Integrated Radial Peaking Factor                                                       !
DNB Parameters Refueling Boron Concentration in addition, this report contains a number of figures which give limits on the parameters listed above. If any of the limits contained in this report are exceeded, corrective action will be taken as defined in the Technical Specifications.
This report has been prepared in accordance with the requirements of Technical Specification 6.9.1.9. The cycle specific limits have been developed using the NRC-approved methodologies given in the " List of Approved Methodologies" section of this report and in Section 6.9.1.9 of the Technical Specifications.
This report has been prepared in accordance with the requirements of Technical Specification 6.9.1.9. The cycle specific limits have been developed using the NRC-approved methodologies given in the " List of Approved Methodologies" section of this report and in Section 6.9.1.9 of the Technical Specifications.
l Calvert Cliffs 2. Cvele 12 col.R                   l' ace 4 of 22                             Rev.O
Calvert Cliffs 2. Cvele 12 col.R l' ace 4 of 22 Rev.O


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..  .                                                                                                                  l CYCI E SPECIFIC LIMITS FOR UNIT 2, CYCLE 12 ,
CYCI E SPECIFIC LIMITS FOR UNIT 2, CYCLE 12,
2.2.1     Reactor Trip Setpoints                                                                             ,
2.2.1 Reactor Trip Setpoints The Axial Flux Offset trip setpoint and allowable values are given in COLR Figure 2.2-1.
1 The Axial Flux Offset trip setpoint and allowable values are given in COLR Figure 2.2-1.         )
)
The Thermal Margin / Low Pressure trip setpoint is given in COLR Figures 2.2-2 and 2.2-3.         l The allowable values are to be not less than the larger of(l) 1875 psia or (2) the value         !
The Thermal Margin / Low Pressure trip setpoint is given in COLR Figures 2.2-2 and 2.2-3.
calculated from COLR Figures 2.2-2 and 2.2-3, 3.1.1.1   Shutdown Margin - Tavg > 200 'F The shutdown margin shall be equal to or greater than the limit line of COLR Figure 3.1.1-1.
l The allowable values are to be not less than the larger of(l) 1875 psia or (2) the value calculated from COLR Figures 2.2-2 and 2.2-3, 3.1.1.1 Shutdown Margin - Tavg > 200 'F The shutdown margin shall be equal to or greater than the limit line of COLR Figure 3.1.1-1.
3.1.1.2   Shutdown Margin - Tavg < 200 *F l
3.1.1.2 Shutdown Margin - Tavg < 200 *F The shutdown margin shall be >._3.0% Ap.
The shutdown margin shall be >._3.0% Ap.
3.1.1.4 Moderator Temperature Coefficient i
l 3.1.1.4   Moderator Temperature Coefficient                                                                   i The moderator temperature coefficient (MTC) she.ll be less negative than -3.0 x 10-4 Ap/0F       l at rated thermal power.
The moderator temperature coefficient (MTC) she.ll be less negative than -3.0 x 10-4 Ap/0F at rated thermal power.
3.1.3.1   CEA Position The allowable time to realign a CEA versus the initial total integrated radial peaking factor is given in COLR Figure 3.1.3-1.
3.1.3.1 CEA Position The allowable time to realign a CEA versus the initial total integrated radial peaking factor is given in COLR Figure 3.1.3-1.
3.1.3.6   Regulating CEA Insertion Limits The regulating CEA groups insertion limita are shown on COLR Figure 3.1.3-2.
3.1.3.6 Regulating CEA Insertion Limits The regulating CEA groups insertion limita are shown on COLR Figure 3.1.3-2.
3.2.1     Linear IIcat Rate The lir..:ar heat rate shall not exceed the limits shown on COLR Figure 3.2.1-1.
3.2.1 Linear IIcat Rate The lir..:ar heat rate shall not exceed the limits shown on COLR Figure 3.2.1-1.
The axial shape index power dependent control limits are given in COLR Figure 3.2.1-2.
The axial shape index power dependent control limits are given in COLR Figure 3.2.1-2.
When using the excore detector monitorine system (SR 4.2.1.3h                                   .
When using the excore detector monitorine system (SR 4.2.1.3h The axial shape index alarm setpoints are shown on COLR Figure 3.2.12.
The axial shape index alarm setpoints are shown on COLR Figure 3.2.12.
T The maximum allowable fraction of rated thermal power vs. Fxy is shown in COLR Figure I
T The maximum allowable fraction of rated thermal power vs. Fxy is shown in COLR Figure I
3.2.1-3.
3.2.1-3.
Ylhennsing3he incore detectar monitoring sysigm (SR 4.2.1.4h The alarm setpoints are set to protect the Linear lleat Rate limits shown on COLR Figure 3.2.1-1.
Ylhennsing3he incore detectar monitoring sysigm (SR 4.2.1.4h The alarm setpoints are set to protect the Linear lleat Rate limits shown on COLR Figure 3.2.1-1.
Calvert Cliffs 2. Cycle 12 COLR                       Page 5 of 22                                 Rev.O
Calvert Cliffs 2. Cycle 12 COLR Page 5 of 22 Rev.O


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)
i l
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t CYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 12
t CYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 12
                                                                                                                  )
)
The uncertainty factors for the incore detector monitoring system are:                           ,
The uncertainty factors for the incore detector monitoring system are:
: 1. A measurement-calculational uncertainty factor of 1.062,                                   -
1.
: 2. An engineering uncertainty factor of 1.03,
A measurement-calculational uncertainty factor of 1.062, 2.
: 3. A linear heat rate uncertainty factor of 1.002 due to axial fuel densification and thennal expansion, and                                                                             i 4.a For measured the mal power less than or equal to 50 percent but greater than 20 percent       !
An engineering uncertainty factor of 1.03, 3.
of rated full core power a thennal power measurement uncertainty factor of 1.035.
A linear heat rate uncertainty factor of 1.002 due to axial fuel densification and thennal expansion, and i
4.a For measured the mal power less than or equal to 50 percent but greater than 20 percent of rated full core power a thennal power measurement uncertainty factor of 1.035.
4.b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertainty factor of 1.020.
4.b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertainty factor of 1.020.
3.2.2.1 Total Planar Radial Peaking Factor T
3.2.2.1 Total Planar Radial Peaking Factor T
The calculated value of Fxy shall be limited to s 1.70.
The calculated value of Fxy shall be limited to s 1.70.
T The allowable combinatio'nof thermal power and Fxy are shown on COLR Figure 3.2.2-1.
The allowable combinatio' of thermal power and Fxy are shown on COLR Figure 3.2.2-1.
3.2.3   Total Integrated Radial Peaking Factor T
T n
3.2.3 Total Integrated Radial Peaking Factor T
The calculated value of Fr shall be limited to $ 1.70.
The calculated value of Fr shall be limited to $ 1.70.
T The allowable combinations of thermal power and Fr are shown on COLR Figure 3.2.3-1.
T The allowable combinations of thermal power and Fr are shown on COLR Figure 3.2.3-1.
The DNB axial flux control limits are shown on COLR Figure 3.2.3-2.
The DNB axial flux control limits are shown on COLR Figure 3.2.3-2.
3.2.5   DNB Parameters The axial shape index, thermal power shall be maintained within the limits estab'ished by the Better Axial Shape Selection System (BASSS) for CEA insertions of the lead bank of < 55%
3.2.5 DNB Parameters The axial shape index, thermal power shall be maintained within the limits estab'ished by the Better Axial Shape Selection System (BASSS) for CEA insertions of the lead bank of < 55%
when B ASSS is operable, or within the limits of COLR Figure 3.2.3 2 for CEA insertions specified by COLR Figure 3.1.3 2.
when B ASSS is operable, or within the limits of COLR Figure 3.2.3 2 for CEA insertions specified by COLR Figure 3.1.3 2.
3.9.1   Boron Concentration The refueling boron concentration shall be maintained uniform and sufficient to ensure that the boron concentration is it 2473 ppm.
3.9.1 Boron Concentration The refueling boron concentration shall be maintained uniform and sufficient to ensure that the boron concentration is it 2473 ppm.
Calvert Cliffs 2, Cycle 12 col.R                     Page 6 af 22                                   Rev.O j
Calvert Cliffs 2, Cycle 12 col.R Page 6 af 22 Rev.O j


4 .
4 1
1 1.300 1.250     -
1.300 1.250 1.200 UNACCEPTABLE UNACCEPTABLE 1.150 OPERATION OPERATION 1.100 REGION REGION '
1.200     -
1.050 1.000
UNACCEPTABLE                                 UNACCEPTABLE                                       !
(-0.2,1.00)
1.150     -
(0.2,1.00) g
OPERATION                                   OPERATION                                       :
' y ~ 0.950 2
1.100   -              REGION                                       REGION '
0.900 a
1.050   -
g 0.850 6 0.800 IH 0.750 O
g    1.000   -
$ 0.700 0.650 0
(-0.2,1.00)                         (0.2,1.00)                                           -
0.600 ACCEPTABLE OPERATION 0.550 REGION g
                            ' y ~ 0.950     -
0.500 -
2 0.900     -
0.450 0 400 -
a g 0.850     -
(-0.6, 0.40)
6 0.800     -
(0.6, 0.40) 0.350 0.300 -
I H 0.750 O
0.250
                              $ 0.700     -
~
0.650   -
0.200 -
0 0.600   -
l O.150 e
ACCEPTABLE 0.550                                       OPERATION
                              $                                                  REGION g   0.500 -
0.450 0 400 -                 (-0.6, 0.40)                           (0.6, 0.40) 0.350 0.300 -                                                                                                               !
0.250                                                                                                 '
                                                                                                                                          ~
0.200 -                                                                                                               l O.150                 e         :        :
u
u
                                        -0.80         -0.60   -0.40     -0.20   0,00       0.20     0.40         0.60   0.80                       i PERIPHERAL AXtAL SHAPE INDEX, Yi                                                           i i
-0.80
Figure 2.21 i
-0.60
Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power cm,ueu n               m com                               m e n:                                                     -            I
-0.40
-0.20 0,00 0.20 0.40 0.60 0.80 i
PERIPHERAL AXtAL SHAPE INDEX, Yi i
i Figure 2.21 i
Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power cm,ueu n m com m e n:
I


                                                            . . - . . . . ~ - . - - . . - - . . - . _ . - . .                                          _ . . . - . . . - .  - . . .
.. -.... ~ -. - -.. - -.. -. _. -..
        ..                                                                                                                                                                          ?
?
h l
h l
1 1.60       ,              ,        ,        ,        ,        ,          ,  ,      ,
1 1.60 TRIP Pvan = 2892 x (A ) x (QR ) + 17.16 x Tm - 10393
TRIP Pvan = 2892 x (A i) x (QR )i + 17.16 x Tm - 10393                                                                                   ,i 1.50                                                                                                                                                     l
,i i
                                                                                                                                                                                      )
i 1.50 l
)
Oone = As x QR, i
Oone = As x QR, i
1.40 1.30 < (& ,1.3) l E
1.40 1.30 < (&,1.3)
1.20                                                                                                                                                   1 jr'                               Atj +0.1 367 x ASI+         1.0                                                           i
E 1.20 1
                                          /                                                     N                                 (+0.6,1.1)                                         '
jr' Atj +0.1 367 x ASI+ 1.0 i
At     0.5 x ASI+ 1.0                                               \(  i     .
/
p                                                           i 1.00 --
N
(+0.6,1.1)
\\(
At 0.5 x ASI+ 1.0 i
p i
1.00 --
(0.0, 1.0)
(0.0, 1.0)
I                             I 0.90 --                                                                     '
I I
                                -0.60 -0.50 -0.40 -0.30 -0.20 -0.10 0.00 0.10 0.20 0.30 0.40 0.50 0.60                                             ,,        _
0.90 --
l ASI Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint Part 1 (ASI vs. A1 )
-0.60 -0.50 -0.40 -0.30 -0.20 -0.10 0.00 0.10 0.20 0.30 0.40 0.50 0.60 ASI Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint Part 1 (ASI vs. A )
Calvert Clif fs 2. Cy cle 12 col.lt                                                   I'd8C 8 OI'22                                               llev. 0
1 Calvert Clif fs 2. Cy cle 12 col.lt I'd8C 8 OI'22 llev. 0


4 I
4 I
12                                                                                                                                         o (1.2,1.2) 1.1 1.0                                                                                                                         _ja)_
12 o (1.2,1.2) 1.1 1.0
0.9 O.8                                                           ,              (0.6 0.85) 1 0.7
_ja)_
                                                                                                                              \                                                     \
0.9 O.8 (0.6 0.85) 1 0.7
g     0.6   -- -                                                      -                                      '
\\
O.5 ---                              -
\\
1 0.4 -- - - -                          -    -
g 0.6 O.5 ---
l 0.3 ( -(0.0 -0.3)                 .-
1 0.4 -- - - -
Oonn = Ai x OR,                                                                                                   ;
l 0.3 ( -(0.0 -0.3)
0.2       -  -                        -
Oonn = A x OR, i
                                                                    ,,g i
0.2
0.1   - --              --  . - - - - -                                                                                                          -
,,g i
0.0 0.0     0.1           0.2           0.3     04         0.5       0.6       0.7       0.8       0.9       1.0     1.1             1.2 FRACTION OF RATED THERMAL POWER                                                                                           ;
0.1 0.0 0.0 0.1 0.2 0.3 04 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 FRACTION OF RATED THERMAL POWER Figure 2.2-3 Thermal Margin / Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QR )
Figure 2.2-3 Thermal Margin / Low Pressure Trip Setpoint - Part 2                                                                       '
1 Calveit Cliffs 2. Cycle 12 COI.it l' ape 9 of 22 Itev. O
(Fraction of Rated Thermal Power vs. QR1 )
Calveit Cliffs 2. Cycle 12 COI.it                                                     l' ape 9 of 22                                                           Itev. O


_ .          - . . .          _ _ _ _ _ . _ . - . ~ . . - . ~ . _ _ . . . . . . . _ . _ _ . . _ . _ . . . . - . _ _ _ _ _ . _ _ . _ _ _ _ _ . _ .
_ _ _ _ _. _. -. ~.. -. ~. _ _....... _. _ _.. _. _.... -. _ _ _ _ _. _ _. _ _ _ _ _. _.
i
i
[               .                                                                                                                                                        ;
[
                                  .                                                                                                                                      i I
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l 4
l 4
I I
I I
i t
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1 6-                                                           -
1' 6-l
l
~ ACCEPTABLE 5--
!                                                                                            ~ ACCEPTABLE                                                               :
OPERATION REGION (EOC,4.5) j
5--                                   OPERATION REGION                                       (EOC,4.5)               j O                                                                                                                  ,,
-Oz e
z                                                                                                                  e l                                                   cr:
l cr:
I                                                   d 4--                                                                                                           i
I d
_J W-0       (
4--
6           (BOC, 3.5)                                                                                             !
i
!.                                                  z                                                                                                                   l 3"
_J W-0
l                                                  .$                                                    MINUMUM SHUTDOWN MARGIN                                       l t                                                   <                                                                                                                  !
(
!                                                    E                                                                                                                   !
6 (BOC, 3.5) z l
l                                                    0
3" l
;                                                    o    2 "                                                 UNACCEPTABLE                                               i, H                                                                                                                   ,
MINUMUM SHUTDOWN MARGIN t
D                                                                                                                   '
E l
OPERATION I                                                                                                                   !
0 o
e                                                             REGION                                               !
2 "
,                                                        1-                                                                                                             i l
UNACCEPTABLE i,
I l                                                         0                                                                                                             i l
H D
i BOC                                                                                     EOC ..           }
OPERATION I
}-                                                                                                    TIME IN CYCLE                                                      !
e REGION 1-i l
I l
0 i
l BOC EOC..
}
i
i
                                                                                                                                                                        }
}-
I                                                                                                                                                                       )
TIME IN CYCLE i
!                                                                                                  Figure 3.1.1-1
}
:                                                                                                                                                                        t
I
!-                                                                              Shutdown Margin vs. Time in Cycle                                         ,
)
i l                                    Calvert ClilTs 2, Cvele 12 col,R                                       l' age 10 of 22                                     Rev.O
Figure 3.1.1-1 t
                          - , -                                          -      ,      - . =       ,-.                  -
Shutdown Margin vs. Time in Cycle i
Calvert ClilTs 2, Cvele 12 col,R l' age 10 of 22 Rev.O l
-. =


t l
t l
1 l
1 l
l 70 I
70 I
I 60 c           (1.57,60)                                                             j
I 60 c (1.57,60) j 50 --
_  50 --
_v)
v)                             '
N E
N E                                                           r g   40 --                                       1002 - 600 Fa o
r g
z  30   .
40 --
o
1002 - 600 Fa oz 30 o
                        .i 6
.i 6
                        $  20 --
20 --
tu 3
tu3 i:
i:
10 --
10 --           ALLOWED REGION 0--                                                                 :)
ALLOWED REGION 0--
(1.67, 0) 1.55                   1.60                     1.65             1.70 MEASURED PRE-MISALIGNED TOTAL INTEGRATED RADIAL                   ,,
:)
PEAKING FACTOR                               .
(1.67, 0) 1.55 1.60 1.65 1.70 MEASURED PRE-MISALIGNED TOTAL INTEGRATED RADIAL PEAKING FACTOR Figure 3.1.3-1 Allowable Time to Realign CEA Versus initial Totalintegrated Radial Peaking Factor Palvett rtiffs 2 rvele 12 Col,lt l' age !) of 22 Rev.O
Figure 3.1.3-1 Allowable Time to Realign CEA Versus initial Totalintegrated Radial Peaking Factor Palvett rtiffs 2 rvele 12 Col,lt                   l' age !) of 22                           Rev.O


          -      .                    .-          . .                      . _ .                .          .- - - .-~.                             .-.. ~ - .             ~-.     . -
.- - -.-~.
.-.. ~ -.
~-.
t 1
t 1
                                  .                                                                                                                                                        1 l              ,
l 1
I l
I l
l l
l l
l                                                                                                                                                                                           I 1.000 c               , - (1.00. Group 5 @ 35%)
l I
e O.900                   ' ' - (O E Grotp5@ 35 %i E                                                                                                                                                                     <
1.000 c
i o          0.800                 e }(
, - (1.00. Group 5 @ 35%)
A-                                             (-).75, i3roup     5@     50%)
e O.900
:                                                                                                                                                                  t
- (O E Grotp5@ 35 %i e }(
                                                        '                      3, Gnup 5 @ 60".)
E o
(                     $          0.700                               ,
0.800 i
g                                  s          e\(0.7(O.SS, G'oup! @85%)
A-(-).75, i3roup 5@ 50%)
l l                                                       0         8                                                                                                                       i 1
t e\\(0.7 3, Gnup 5 @ 60".)
                      % 0.600                           '          '
(
().56, i3roup 4@         50%)
0.700 (O.SS, G'oup! @85%)
i 0.500                 '                                 -
l g
Long ferm steady S@                                '
s l
State Insertion Urnit.
0 8
Group 5 @ 25%                                                                                                                 i 0.400                                                                ._
% 0.600 i
l                    u.                                                       '
1 i
o           0.300                 '          '
().56, i3roup 4@ 50%)
z                                  i         e O                                             '          i                                                                                                           i (0.2                @ 60".)
S@
5          0.200                           ,
0.500
:g                                             3. G]up 3 short Term steady                               8 l
' Long ferm steady State Insertion Urnit.
l O.100 _                         a            '. state insertion umit.     --                      L                                                     l e                 Group 4 @ 20%
0.400 Group 5 @ 25%
O.000                                                 I     I     I   I e IU'U ' U' "" 0 6U ''I Allowable OASSS               M - (Group 5 @ 55%)
i l
Operating Region 5                                           3                                           1
u.
;                                                  I I         I       I       I     I     I     I   I         I       I       I     I   1   I         I I       I O 20 40 60 80 100 0                               20 40 60 80 100 0                           20 40 60 80 100 13G 0 108.8 81.6 54.4 27.2 0.0133.0 108.8 81.6 54.4 27.2 0.0136.0 108.8 81.6 54.4 27.2 0.0 4                                             2 I       I       I     I     I   I         I       I       I       I   I   I               '
o 0.300 z
O      20 40 60 80 100 0                             20 40 60 80 100
i e
* 136.0 108.8 81.6 54.4 27.2 0.0136.0 108.8 81.6 54.4 27.2 0.0 l
O i
!                                                                                                                                                                                            I l
i 5
0.200
:g
: 3. G]up 3 (0.2
@ 60".)
' short Term steady 8
l l
O.100 _
'. state insertion umit.
L l
a e
Group 4 @ 20%
O.000 I
I I
I IU'U ' U' "" 0 6U ''I e
Allowable OASSS M - (Group 5 @ 55%)
Operating Region 5
3 1
I I
I I
I I
I I
I I
I I
I 1
I I
I I
O 20 40 60 80 100 0 20 40 60 80 100 0 20 40 60 80 100 13G 0 108.8 81.6 54.4 27.2 0.0133.0 108.8 81.6 54.4 27.2 0.0136.0 108.8 81.6 54.4 27.2 0.0 4
2 I
I I
I I
I I
I I
I I
I O
20 40 60 80 100 0 20 40 60 80 100 136.0 108.8 81.6 54.4 27.2 0.0136.0 108.8 81.6 54.4 27.2 0.0 l
I l
l
l
                                                                                                  %CEA INSERTION INCHES CEA WITHDRAWN i
%CEA INSERTION INCHES CEA WITHDRAWN i
1 l
1 1
;.                                                                                                                                                                                          1 Figure 3.1.3-2
Figure 3.1.3-2
~
~
CEA Group Insertion Limits vs. Fraction of Rated Thermal Power i
CEA Group Insertion Limits vs. Fraction of Rated Thermal Power i
Calvert (lilk ?. Cvele 12 C()l.it                                                         l' ace 12 of 22                                                     ig ey, <,
Calvert (lilk ?. Cvele 12 C()l.it l' ace 12 of 22 ig ey, <,


l l
l i
l l
17.0 l
l l
I l
i 17.0 l
16.5 b
16.5 b
h 16.0 uI _
h 16.0 uI _
He kO l-
He kO l- < 15.5 1
                    <m < 15.5                                                                                               1 I
<m ww
ww                                                                                                       '
:t o e9
:t o                                                                                                   ,
<.=
e9
W + 15.0 IEE o a<J M0 UNACCEPTABLE OPERATION
                    < .=
$ 314.5 c ACCEPTABLE OPERATION ma 4
1 W + 15.0 IEE o a<J M0
4~
                  <                                        UNACCEPTABLE OPERATION
>g 14.0
                  $ 314.5 c                                           ,            ,
.J
ma ACCEPTABLE OPERATION
.J 13.5 -- - -
                                                                                    ,      4 4~                                                                       !
I 13 0 BOC EOQ TIME IN CYCLE Figure 3.2.1 1 Allowable Peak Linear Heat Rate vs. Time in Cycle.
l g     14.0   - - - - -            ----
calven clirrs ?. cycle I? c ol R Page n nrr n,.s.
                  .J
n
                  .J 13.5 -- - -     . - - - - - -      - - - -    - - - -      .      . - - - _ _ _
I 13 0 BOC                                                                       EOQ TIME IN CYCLE Figure 3.2.1 1 Allowable Peak Linear Heat Rate vs. Time in Cycle.
calven clirrs ?. cycle I? c ol R                                   Page n nrr                             n ,.s. n


1.100 1.050 --
1.100 1.050 --
1.000 --                 (-0.06,1.00)                 (0.12,1.00) 0.950 --       UNACCEPTABLE                             UNACCEPTABLE 0.900       . OPERATION                               OPERATION REGION                                 REGION a:   0.850 --
1.000 --
(-0.06,1.00)
(0.12,1.00) 0.950 --
UNACCEPTABLE UNACCEPTABLE 0.900 OPERATION OPERATION REGION REGION a:
0.850 --
0.800 --
0.800 --
n.
n.
                          .;  0.750 --
0.750 --
                          !    0.700 --     (-0.3, 0.70)                                     (0.3, 0.70)
0.700 --
(-0.3, 0.70)
(0.3, 0.70)
W
W
                        '            '~
'~
g                                        ACCEPTABLE g    0.600 --                             OPERATION
ACCEPTABLE gg 0.600 --
                          <                                          REGION
OPERATION REGION
                          !!ll 0.550 --
!!ll 0.550 --
o d   0.500 -- (-0.3, 0.50) g   0.450 -
o d
5   0.400 --
0.500 --
P o    0.350 -
(-0.3, 0.50) g 0.450 -
u-   0.300 --
5 0.400 --
Po 0.350 -
u-0.300 --
0.250 --
0.250 --
0.200 -  -
0.200 -
0.150 -               (-0.45, 0.15) 0.100                                                                           '.
0.150 -
0.050             e:           :          :          :    c     :
(-0.45, 0.15) 0.100 0.050 e:
                                    -0.60         -0.40       -0.20     0.00       0.20       0.40       0.60 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits calvert Ulirrs 2. cycle 12 col.it                       l' ace 14 of 22                           i<cv. o
c
-0.60
-0.40
-0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits calvert Ulirrs 2. cycle 12 col.it l' ace 14 of 22 i<cv. o


x h   1.00 <       (1.47,1.00) o n.
x h
1.00 <
(1.47,1.00) o n.
:d
:d
:E e
:Eewp 0.90 --
w p  0.90 --                         1.57, 0.90)
1.57, 0.90)
O N
O N
u.
u.
O   0.80 --
O 0.80 --
(1.785, 0.80)
(1.785, 0.80)
P                                                                                                                   i O
P i
: u.                           ACCEPTABLE VALUE                                                                        )
O ACCEPTABLE VALUE u.
w   0.70 --                                                                                                           1
w 0.70 --
                    )                                                                                                                   i O
1 i
D o
)
d
O<
                  $  0.60 a
Do d
R s
0.60
0.50 l         l                                               , :.:
$aR<s 0.50 l
l                          1 45     1.50       1 55   1.60     1 65           1.70             1.75     1.80 1.85 T
l l
Fxy                                             .
1 45 1.50 1 55 1.60 1 65 1.70 1.75 1.80 1.85 T
Figure 3.2.1-3 Total Planar Radial Peaking Factor /FxyT vs.
Fxy Figure 3.2.1-3 T
Maximum Allowable Fraction of Rated Thermal Power (Surveillance 4.2.1.3) 4 S        ,
Total Planar Radial Peaking Factor /Fxy vs.
Maximum Allowable Fraction of Rated Thermal Power (Surveillance 4.2.1.3)
S 4


0                                                                                                                                                             ,
0 t
t i
i i
i T
L 1.00 e (1.70,1.00)
L                                                     1.00 e                                   (1.70,1.00)                                                           !
UNACCEPTABLE T
!                                                  "                                                                UNACCEPTABLE OPERATION                                    !
E OPERATION o
E                                                                                                                   '
REGION A
o                                                                      REGION A                                                                                                                   ,
T I
T                                       I g 0.90 --                                                         g xy FLIMITCURVE                                  l E
g 0.90 --
w                                                                                                                    !
F g xy LIMITCURVE l
i                                                h O                                  ACCEPTABLE
Ew i
: l.                                                                                                                                                                     :
h l.
1-                                 OPERATION
O ACCEPTABLE 1-OPERATION 0.80 --
                                                  <  0.80 --
REGION E
E             -
u.
REGION r
(1.785, 0.80) r o
'                                                u.                                                                     (1.785, 0.80) o                                                                                                                   -
i z
i z                                                                                                                   ;
OP U
O P
0.70 --
U 0.70 --
N u.
N u.
w J
w J
c)
c)<%o 0.60 -
                                                %   0.60 -
l i
o l                                               $<
l 0.50 e
i l                                                     0.50                             :                              :              e 1.65                       1.70                           1.75               1.80 T
1.65 1.70 1.75 1.80 T
Fxy                                 ",                      ,
Fxy i
i l
l 1
1 l
l Figure 3.2.2-1 Total Planar Radial Peaking Factor vs.
Figure 3.2.2-1 4
4 Allowable Fraction of Rated Thermal Power I
Total Planar Radial Peaking Factor vs.
(ACTION 3.2.2.1.a 1) s 4
I Allowable Fraction of Rated Thermal Power s                                                                                  (ACTION 3.2.2.1.a 1) 4 i
i Calvert Cliffs 2, Cycle 12 COI.It l' age 16 of 22 1(ev. o
Calvert Cliffs 2, Cycle 12 COI.It                                         l' age 16 of 22                                       1(ev. o


4 1.00 e                   (1.70,1.00)     UNACCEPTABLE g
4 1.00 e (1.70,1.00)
UNACCEPTABLE g
OPERATION g
OPERATION g
o n.
REGION o
REGION T
n.
p      Fr LIMITCURVE
T Fr LIMITCURVE 0.90 --
                        $    0.90 --
p 5g ACCEPTABLE OPERATION o
5 g                        ACCEPTABLE o                         OPERATION
REGION g
                        $                          REGION g   0.80 --
0.80 --
: u.                                                    (1.785,0.80) o z
(1.785,0.80) u.ozO P'j 0.70 --
O P
u.
                      'j u.
c3<Do 0.60 --
0.70 --
d<
c3 D    0.60 --
0.50 1.65 1.70 1.75 1.80 T
o d
F, i
0.50                   :                    ;              .
)
1.65             1.70                 1.75               1.80 T
* F, i
                                                                                                              )
Figure 3.2.3-1 i
Figure 3.2.3-1 i
Total Integrated Radial Peaking Factor vs.                             )
Total Integrated Radial Peaking Factor vs.
Allowable Fraction of Rated Thermal Power                             j C IvoI Cliffs 2, Cycle 12 Col.lt               Page 17 of 22                           Itev. O
)
Allowable Fraction of Rated Thermal Power j
C IvoI Cliffs 2, Cycle 12 Col.lt Page 17 of 22 Itev. O


l l                                                                                                                                                                           i l
l i
l 1.100 l
l l
1.050 --                                                                                                                !
1.100 1.050 l
l 1.000 --             (-0.10,1.00)                                 (0.15,1.00) 0.950
1.000 --
                                                          " UNACCEPTABLE                                               UNACCEPTABLE                                       ,
(-0.10,1.00)
l                                        a      0.900 --     OPERATION                                                 OPERATION W                                                                                                                               l REGION                                                   REGION                                       .
(0.15,1.00) 0.950 " UNACCEPTABLE UNACCEPTABLE l
l                                        @      0.850 --
0.900 --
1 g'                                                                                                                               ;
OPERATION OPERATION l
i 0.800 -- (-0.3, 0.80)                                                       (0.3, 0.80)                                 i l
a W
g                                                                                                                               '
REGION REGION l
l                                         o     0.750 --                                                                                                                 l
0.850 --
: n.                                                                                                                               1 l                                         g 0.700 -                                                                                                                       !
1 g'
:                                        co                                               ACCEPTABLE                                                                     :
0.800 --
g      0.650 --
(-0.3, 0.80)
OPERATION b
(0.3, 0.80) i i
3 a
g l
0.600     .                                    REGION l                                       y     0.550 --
l o
o                                                                                                                                 l
0.750 --
                                                                                                                                                                          ^
l n.
l                                       g     0.500 --     (-0.3, 0.50) l X
1 l
y     0.450 --
g 0.700 -
l Ui     0.400 --                                                                                                                  -
co ACCEPTABLE 0.650 --
z o      0.350 --
OPERATION g
s
3 0.600 REGION b
!                                        U 0.300 --
a l
l                                       $
y 0.550 --
0.250 --
l o
t.200 -                                                                                                                 '
l g
O.150 -             (-0.45. 0.15)                                                                         -
0.500 --
0.100 --
(-0.3, 0.50)
                                                                                                                                                                          ~
^
0.050             e:                  :                :          :    :.:
l X
l                                                     -0.60       -0.40         -0.20               0.00       0.20         0.40           0.60 PERIPHERAL AXtAL SHAPE INDEX, Yi                                                                   l l
y 0.450 --
l Ui 0.400 --
zo 0.350 --
s U
0.300 --
l 0.250 --
t.200 -
O.150 -
(-0.45. 0.15) 0.100 --
~
0.050 e:
l
-0.60
-0.40
-0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXtAL SHAPE INDEX, Yi l
l l
l l
Figure 3.2.3-2                                                                     '
l Figure 3.2.3-2 DNB Axial Flux Offset Control Limits i
;                                                              DNB Axial Flux Offset Control Limits                                                                       >
I i
i I
Calveit Cliffs 2, Cycle 12 COLR Pa:7.c 18 of'22 itev.O
i Calveit Cliffs 2, Cycle 12 COLR                                       Pa:7.c 18 of'22                                             itev.O


LIST OF APPROVED METHODOLOGIES (1)     CENPD-199-P, Rev l-P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodobgy for Analog Protection Systems," January 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
LIST OF APPROVED METHODOLOGIES (1)
(2)     CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin / Low Pressure LSSS for Calvert Cliffs Units I and II,"
CENPD-199-P, Rev l-P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodobgy for Analog Protection Systems," January 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
(2)
CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin / Low Pressure LSSS for Calvert Cliffs Units I and II,"
December 1979 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.2.1,3.2.3)
December 1979 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.2.1,3.2.3)
(3)   _ CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2,"
(3)
_ CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2,"
January 1980 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
January 1980 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
(4)     CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (Methodology for Specifications 3.1.3.6,3.2.1, i
(4)
CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (Methodology for Specifications 3.1.3.6,3.2.1, i
3.2.2.1, 3.2.3, 3.2.5)
3.2.2.1, 3.2.3, 3.2.5)
                                                                                                                            ]
]
(5)     CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units I and 2," December 1981 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2,5)                         I (6)     Letter from Mr. D.11. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24,1982, Unit I Cycle 6 License Approval (Amendment No. 71 to DPR 53 and SER)[ Approval to CEN-124(B)-P (three parts) and CEN-191(B)-P)]
(5)
(7)     CEN-348(B)-P, " Extended Statistical Combination of Uncertainties," January 1987 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)                                           ;
CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units I and 2," December 1981 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2,5)
l (8)     Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21,1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-348(B)-P, Extended           .
(6)
Statistical Combination of Uncertainties"                                                             !
Letter from Mr. D.11. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24,1982, Unit I Cycle 6 License Approval (Amendment No. 71 to DPR 53 and SER)[ Approval to CEN-124(B)-P (three parts) and CEN-191(B)-P)]
(9)     CENPD-161-P-A, " TORC Code, A Computer Code for Determining the Thermal Margin of a                   l Reactor Core," April 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
(7)
CEN-348(B)-P, " Extended Statistical Combination of Uncertainties," January 1987 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5) l (8)
Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21,1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9)
CENPD-161-P-A, " TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
{
{
(10)   CENPD-162-P-A, " Critical lleat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975 (Methodology for Specifications           i 2.2.1, 3.1.3.6, 3.2.3, 3.2.5)                                                                         ;
(10)
1
CENPD-162-P-A, " Critical lleat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975 (Methodology for Specifications i
;              (Il)   CENPD-207-P-A," Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer           l j
2.2.1, 3.1.3.6, 3.2.3, 3.2.5)
Grids Part 2, Non-uniform Axial Power Distribution," December 1984 (Methodology for Specifications 2.2.1, 3,1.3.6, 3.2.3, 3.2.5)                                                         ;
(Il)
(12)   CENPD-206-P A, " TORC Code, Verification and Simplified Modeling Methods," June 1981 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
CENPD-207-P-A," Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer l
(13)   CENPD-225-P A, " Fuel and Poison Rod Bowing," June 1983 (Methodology for Specifications
j Grids Part 2, Non-uniform Axial Power Distribution," December 1984 (Methodology for Specifications 2.2.1, 3,1.3.6, 3.2.3, 3.2.5)
;                      2.2.1, 3.1.3.6, 3.2.3, 3.2.5)
(12)
Calvert Cliffs 2, Cycle 12 COI.R                     - Page 19 of 22                               Rev.0
CENPD-206-P A, " TORC Code, Verification and Simplified Modeling Methods," June 1981 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
(13)
CENPD-225-P A, " Fuel and Poison Rod Bowing," June 1983 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.3, 3.2.5)
Calvert Cliffs 2, Cycle 12 COI.R
- Page 19 of 22 Rev.0


1 e l',    .,
1 e l',
(14)   CENPD-266-P-A, "The ROCS and DIT Computer Code for Nuclear Design," April 1983 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
(14)
(15) CENPD-275-P-A, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable Absorbers," May 1988 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
CENPD-266-P-A, "The ROCS and DIT Computer Code for Nuclear Design," April 1983 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
(16)   CENPD-382-P-A, " Methodology for Core Designs Containing Erbium Burnable Absorbers," August 1993 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1, 3.2.3, 3.2.5)
(15)
(17)   CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)
CENPD-275-P-A, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable Absorbers," May 1988 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
(18)   CEN-161-(B)-P-A, " Improvements to Fuel Evaluation Model," August 1989 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)
(16)
(19)   CEN-161-(B)-P, Supplement 1-P, " Improvements to Fuel Evaluation Model," April 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)
CENPD-382-P-A, " Methodology for Core Designs Containing Erbium Burnable Absorbers," August 1993 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1, 3.2.3, 3.2.5)
(20)   Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-161-(B)-P, Supplement 1-P, Improvements to Fuel Evaluation Model" (Approval of CEN-161(B), Supplement 1-P)
(17)
(21)   CEN-372-P-A, " Fuel Rod Maximum Allowable Gas Pressure," May 1990 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.1, 3.2.2.1 )
CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)
(22)   Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC) dated December 15,1981, LD-81-095, Enclosure 1-P, "C-E ECCS Evaluation Model Flow Blockage Analysis"                 ;
(18)
(Methodology for Specifications 3.2.1,3.2.2.1) 4 (23)   CENPD-132, Supplement 3-P-A, " Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and .W Designed NSSS," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1 and approval of Letter LD-81-095, dated       i December 15,1981)                                                                           j (24)   CENPD-133, Supplement 5,"CEFLASH-4A, a FORTRAN 77 Digital Computer Program                   l for Reactor Blowdown Analysis," June 1985 (Methodology for Specifications 3.2.1,             (
CEN-161-(B)-P-A, " Improvements to Fuel Evaluation Model," August 1989 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)
1 3.2.2.1)
(19)
(25)   CENPD-134, Supplement 2,"COMPERC-II, A Program for Emergency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1) l l          (26)   Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE), dated July 31,1986,     ;
CEN-161-(B)-P, Supplement 1-P, " Improvements to Fuel Evaluation Model," April 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)
                    " Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and         1 Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133, Supplement 5 and CENPD-134, Supplement 2)
(20)
(27)   CENPD-135, Supplement 5-P,"STRIKIN-ll, A Cylindrical Geometry Fuel Rod lleat Transfer Program," April 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-161-(B)-P, Supplement 1-P, Improvements to Fuel Evaluation Model" (Approval of CEN-161(B), Supplement 1-P)
(21)
CEN-372-P-A, " Fuel Rod Maximum Allowable Gas Pressure," May 1990 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.1, 3.2.2.1 )
(22)
Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC) dated December 15,1981, LD-81-095, Enclosure 1-P, "C-E ECCS Evaluation Model Flow Blockage Analysis" (Methodology for Specifications 3.2.1,3.2.2.1) 4 (23)
CENPD-132, Supplement 3-P-A, " Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and.W Designed NSSS," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1 and approval of Letter LD-81-095, dated December 15,1981) j (24)
CENPD-133, Supplement 5,"CEFLASH-4A, a FORTRAN 77 Digital Computer Program for Reactor Blowdown Analysis," June 1985 (Methodology for Specifications 3.2.1, 3.2.2.1)
(25)
CENPD-134, Supplement 2,"COMPERC-II, A Program for Emergency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1) l (26)
Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE), dated July 31,1986,
" Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and 1
Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133, Supplement 5 and CENPD-134, Supplement 2)
(27)
CENPD-135, Supplement 5-P,"STRIKIN-ll, A Cylindrical Geometry Fuel Rod lleat Transfer Program," April 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
I t
I t
rNN[rliffs 2. cvele 12 col.R                     Pane 20 of 22                             Rev.O
rNN[rliffs 2. cvele 12 col.R Pane 20 of 22 Rev.O


l (28)   Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6,1978,
l (28)
                        " Evaluation of Topical Report CENPD-135, Supplement 5" l               (29)   CENPD-137, Supplement 1-P, " Calculative Methods for the C-E Small Break LOCA l                       Evaluation Model," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6,1978,
(30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, "A Computer Program for the Reactor             ,
" Evaluation of Topical Report CENPD-135, Supplement 5" l
l Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 l                       (Methodology for Specifications 3.2.1,3.2.2.1)
(29)
(31)   Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE), dated September 27,1977,
CENPD-137, Supplement 1-P, " Calculative Methods for the C-E Small Break LOCA l
                        " Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, l
Evaluation Model," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
;                        Supplement 1-P" l
(30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, "A Computer Program for the Reactor l
(32)   CENPD-138, Supplement 2-P," PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 l
(33)   Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer (CE), April 10,1978. " Evaluation of Topical Report CENPD-138, Supplement 2-P" l
(Methodology for Specifications 3.2.1,3.2.2.1)
(34)   Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC), dated February 22,1985, "Calvert Cliffs Nuclear Power Plant Unit 1, Docket No. 50-317, Amendment to Operating License DPR-53, Eighth Cycle License Application" (Section 7.3.2 contains Methodology for Specifications 3.1.1.1 and 3.1.1.4 and 3.1.3.6)
(31)
(35)   Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated May 20, 1985, Safety Evaluation Repon Approving Unit 1 Cycle 8 License Application l
Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE), dated September 27,1977, l
l               (36)   Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September l                       22,1980, " Amendment to Operating License No. 50-317, Fifth Cycle License               l l                        Application (Section 7.1.2 contains Methodology for Specifications 3.1.1.2,3.9.1) l Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated December (37) 12,1980," Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" (38)   Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1,       I 1986, "Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Docket Nos. 50-317 and 50-318, Request for Amendment"(Methodology for Specifications 3.1.3.1) l               (39)     Letter from S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated July 7,1987, Docket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2)
" Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P" l
(Support for Specification 3.1.3.1) l l                 (40)   CENPD-188-A,"llERMITE: A Multi-Dimensional Space - Time Kinetics Code for PWR Transients," July 1976 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1, 3.2.2.1, 3.2.3, 3.2.5) l Calvert Cliffs 2, Cycle 12 cot.R               Page 21 of 22                             Rev.O
(32)
CENPD-138, Supplement 2-P," PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
(33)
Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer (CE), April 10,1978. " Evaluation of Topical Report CENPD-138, Supplement 2-P" l
(34)
Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC), dated February 22,1985, "Calvert Cliffs Nuclear Power Plant Unit 1, Docket No. 50-317, Amendment to Operating License DPR-53, Eighth Cycle License Application" (Section 7.3.2 contains Methodology for Specifications 3.1.1.1 and 3.1.1.4 and 3.1.3.6)
(35)
Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated May 20, 1985, Safety Evaluation Repon Approving Unit 1 Cycle 8 License Application l
l (36)
Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September l
22,1980, " Amendment to Operating License No. 50-317, Fifth Cycle License l
Application (Section 7.1.2 contains Methodology for Specifications 3.1.1.2,3.9.1) l (37)
Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated December 12,1980," Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" (38)
Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1, 1986, "Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Docket Nos. 50-317 and 50-318, Request for Amendment"(Methodology for Specifications 3.1.3.1) l (39)
Letter from S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated July 7,1987, Docket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2)
(Support for Specification 3.1.3.1) l l
(40)
CENPD-188-A,"llERMITE: A Multi-Dimensional Space - Time Kinetics Code for PWR Transients," July 1976 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1, 3.2.2.1, 3.2.3, 3.2.5) l Calvert Cliffs 2, Cycle 12 cot.R Page 21 of 22 Rev.O


O (41)   The Full Core Power Distribution Monitoring System referenced in Specifications 3.1.3.1,3.2.2.1,3.2.3, and the BASES is described in the following documents:
O (41)
(a)     CENPD-153-P, Revision 1-P-A, " Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May           l 1980 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.1, 3.2.2.1, 3.2.3, 3.2.5)
The Full Core Power Distribution Monitoring System referenced in Specifications 3.1.3.1,3.2.2.1,3.2.3, and the BASES is described in the following documents:
(b)     CEN-119(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit 1 and Unit 2," November 1979 (Referenced in Appendix B of Unit 2 Cycle 9 License Application)
(a)
(c)       Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318. Request for Amendment, Unit 2 Ninth Cycle License Application" (Appendix B contains Methodologies for Specifications 3.1.3.1,3.2.2.1,3.2.3, 3.2.5)
CENPD-153-P, Revision 1-P-A, " Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.1, 3.2.2.1, 3.2.3, 3.2.5)
(d)       Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated           ,
(b)
January 10,1990, " Safety Evaluation Report Approving Unit 2 Cycle 9 License       I Application" (42)   Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995,"Approva! to Use Convolution Technique in Main Steam Line Break Analysis -
CEN-119(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit 1 and Unit 2," November 1979 (Referenced in Appendix B of Unit 2 Cycle 9 License Application)
Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 (TAC Nos. M90897 and M90898)           l 1
(c)
                                                                                                                )
Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318. Request for Amendment, Unit 2 Ninth Cycle License Application" (Appendix B contains Methodologies for Specifications 3.1.3.1,3.2.2.1,3.2.3, 3.2.5)
I l
(d)
i
Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10,1990, " Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42)
                                                                                    ~
Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995,"Approva! to Use Convolution Technique in Main Steam Line Break Analysis -
l Calvert Clifts 2, Cycle 12 COLR                 Page 22 of 22                                 Rev.0}}
Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 (TAC Nos. M90897 and M90898) l i
~
l Calvert Clifts 2, Cycle 12 COLR Page 22 of 22 Rev.0}}

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,

4 l

M CALVERT CLIFFS NUCLEAR POWER PLANT i

CORE OPERATING LIMITS REPORT for UNIT 2, CYCLE 12 i

I REVISION 0 1

]

l 1

-l 9705080235 970505 PDR ADOCK 05000318 PDR p

Calvert Cliffs 2, Cycle 12 COI.it Page 1 of 22 llev 0

CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 2, CYCLE 12 The following limits are included in this Core Operating Limits Report:

l Soccification Titic Pg l

introd uction.............

.4 2.2.1 Reactor Trip Setpoints.............

.. 5 3.1.1.1 Shutdown Margin - Tavg > 200 *F...........................

........5 3.1.1.2 Shutdown Margin - Tavg $ 200 *F...

................5 j

3.1.1.4 Moderator Temperature Coefficient.....................

.........................5 3.1.3.1 C EA Position..................................

.............5 3.1.3.6 Regulating CEA Insertion Limits....

...................5 3.2.1 -

Linear Heat Rate......

.......................5 3.2.2.1 Total Planar Radial Peaking Factor...........................

... 6 3.2.3 Total Integrated Radial Peaking Factor...............................

... 6 3.2.5 DNB Parameters..........................

.6 3.9.1 Boron Concentration.........................................

... 6 List of Approved Methodologies.......

.19 The following figures are included in this Core Operating Limits Report:

1 Number Title P. age i

I i

Figure 2.2-1 Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power..

...7 Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint - Part 1.

.8 Figure 2.2-3 Thermal Margin / Low Pressure Trip Setpoint - Part 2.

.... 9 Figure 3.1.1-1 Shutdown Margin vs. Time in Cycle.

. 10 Figure 3.1.3-1 Allowable Time To Realign CEA Versus Initial Total Integrated Radial Peaking Factor......

. 11 i

Figure 3.1.3-2 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power.

. 12 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle..

.13 Figure 3.2.1-2 Linear lleat Rate Axial Flux Offset Control Limits..

.. 14 Figure 3.2.1-3 Total Planar Radial Peaking Factor /Fxy ys, j

T Maximum Allowable Fraction of Rated Thermal Power.......

... 15 i

Figure 3.2.2-1 Total Planar Radial Peaking Factor vs. Allowable Fraction of Rated Thermal Power..........

.16 Figure 3.2.3-1 Total Integrated Radial Peaking Factor vs.

Allowable Fraction of Rated Thermal Power.

.. 17 Figure 3.2.3 2 DNB Axial Flux Offset Control Limits.

.I8 i

Calvert Cliffs 2. Cvele 12 COLR Pace 2 of 22 Rev.1

4 a

i LIST OF EFFECTIVE PAGES Page No.

Rev. No.

Page No.

Rev.No.

1 0

15 0

2 0

16 0

4 l

3 0

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6 0

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21 0

1 8

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0 1

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11 0

12 0

13, 0

14 _

0 4

4 i

,i ralvert Cliffs 2. Cvele 12 C01.11 l' ace 3 of 22 Itev. O

i INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 2, Cycle 12.' It contains the limits for:

1 Reactor Trip Setpoints Shutdown Margm Moderator Temperature Coefficient CEA Position Regulating CEA Insertion Limits Linear Heat Rate Total Planar Radial Peaking Factor Total Integrated Radial Peaking Factor DNB Parameters Refueling Boron Concentration in addition, this report contains a number of figures which give limits on the parameters listed above. If any of the limits contained in this report are exceeded, corrective action will be taken as defined in the Technical Specifications.

This report has been prepared in accordance with the requirements of Technical Specification 6.9.1.9. The cycle specific limits have been developed using the NRC-approved methodologies given in the " List of Approved Methodologies" section of this report and in Section 6.9.1.9 of the Technical Specifications.

Calvert Cliffs 2. Cvele 12 col.R l' ace 4 of 22 Rev.O

1 l

CYCI E SPECIFIC LIMITS FOR UNIT 2, CYCLE 12,

2.2.1 Reactor Trip Setpoints The Axial Flux Offset trip setpoint and allowable values are given in COLR Figure 2.2-1.

)

The Thermal Margin / Low Pressure trip setpoint is given in COLR Figures 2.2-2 and 2.2-3.

l The allowable values are to be not less than the larger of(l) 1875 psia or (2) the value calculated from COLR Figures 2.2-2 and 2.2-3, 3.1.1.1 Shutdown Margin - Tavg > 200 'F The shutdown margin shall be equal to or greater than the limit line of COLR Figure 3.1.1-1.

3.1.1.2 Shutdown Margin - Tavg < 200 *F The shutdown margin shall be >._3.0% Ap.

3.1.1.4 Moderator Temperature Coefficient i

The moderator temperature coefficient (MTC) she.ll be less negative than -3.0 x 10-4 Ap/0F at rated thermal power.

3.1.3.1 CEA Position The allowable time to realign a CEA versus the initial total integrated radial peaking factor is given in COLR Figure 3.1.3-1.

3.1.3.6 Regulating CEA Insertion Limits The regulating CEA groups insertion limita are shown on COLR Figure 3.1.3-2.

3.2.1 Linear IIcat Rate The lir..:ar heat rate shall not exceed the limits shown on COLR Figure 3.2.1-1.

The axial shape index power dependent control limits are given in COLR Figure 3.2.1-2.

When using the excore detector monitorine system (SR 4.2.1.3h The axial shape index alarm setpoints are shown on COLR Figure 3.2.12.

T The maximum allowable fraction of rated thermal power vs. Fxy is shown in COLR Figure I

3.2.1-3.

Ylhennsing3he incore detectar monitoring sysigm (SR 4.2.1.4h The alarm setpoints are set to protect the Linear lleat Rate limits shown on COLR Figure 3.2.1-1.

Calvert Cliffs 2. Cycle 12 COLR Page 5 of 22 Rev.O

i l

)

i l

t CYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 12

)

The uncertainty factors for the incore detector monitoring system are:

1.

A measurement-calculational uncertainty factor of 1.062, 2.

An engineering uncertainty factor of 1.03, 3.

A linear heat rate uncertainty factor of 1.002 due to axial fuel densification and thennal expansion, and i

4.a For measured the mal power less than or equal to 50 percent but greater than 20 percent of rated full core power a thennal power measurement uncertainty factor of 1.035.

4.b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertainty factor of 1.020.

3.2.2.1 Total Planar Radial Peaking Factor T

The calculated value of Fxy shall be limited to s 1.70.

The allowable combinatio' of thermal power and Fxy are shown on COLR Figure 3.2.2-1.

T n

3.2.3 Total Integrated Radial Peaking Factor T

The calculated value of Fr shall be limited to $ 1.70.

T The allowable combinations of thermal power and Fr are shown on COLR Figure 3.2.3-1.

The DNB axial flux control limits are shown on COLR Figure 3.2.3-2.

3.2.5 DNB Parameters The axial shape index, thermal power shall be maintained within the limits estab'ished by the Better Axial Shape Selection System (BASSS) for CEA insertions of the lead bank of < 55%

when B ASSS is operable, or within the limits of COLR Figure 3.2.3 2 for CEA insertions specified by COLR Figure 3.1.3 2.

3.9.1 Boron Concentration The refueling boron concentration shall be maintained uniform and sufficient to ensure that the boron concentration is it 2473 ppm.

Calvert Cliffs 2, Cycle 12 col.R Page 6 af 22 Rev.O j

4 1

1.300 1.250 1.200 UNACCEPTABLE UNACCEPTABLE 1.150 OPERATION OPERATION 1.100 REGION REGION '

1.050 1.000

(-0.2,1.00)

(0.2,1.00) g

' y ~ 0.950 2

0.900 a

g 0.850 6 0.800 IH 0.750 O

$ 0.700 0.650 0

0.600 ACCEPTABLE OPERATION 0.550 REGION g

0.500 -

0.450 0 400 -

(-0.6, 0.40)

(0.6, 0.40) 0.350 0.300 -

0.250

~

0.200 -

l O.150 e

u

-0.80

-0.60

-0.40

-0.20 0,00 0.20 0.40 0.60 0.80 i

PERIPHERAL AXtAL SHAPE INDEX, Yi i

i Figure 2.21 i

Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power cm,ueu n m com m e n:

I

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

?

h l

1 1.60 TRIP Pvan = 2892 x (A ) x (QR ) + 17.16 x Tm - 10393

,i i

i 1.50 l

)

Oone = As x QR, i

1.40 1.30 < (&,1.3)

E 1.20 1

jr' Atj +0.1 367 x ASI+ 1.0 i

/

N

(+0.6,1.1)

\\(

At 0.5 x ASI+ 1.0 i

p i

1.00 --

(0.0, 1.0)

I I

0.90 --

-0.60 -0.50 -0.40 -0.30 -0.20 -0.10 0.00 0.10 0.20 0.30 0.40 0.50 0.60 ASI Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint Part 1 (ASI vs. A )

1 Calvert Clif fs 2. Cy cle 12 col.lt I'd8C 8 OI'22 llev. 0

4 I

12 o (1.2,1.2) 1.1 1.0

_ja)_

0.9 O.8 (0.6 0.85) 1 0.7

\\

\\

g 0.6 O.5 ---

1 0.4 -- - - -

l 0.3 ( -(0.0 -0.3)

Oonn = A x OR, i

0.2

,,g i

0.1 0.0 0.0 0.1 0.2 0.3 04 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 FRACTION OF RATED THERMAL POWER Figure 2.2-3 Thermal Margin / Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QR )

1 Calveit Cliffs 2. Cycle 12 COI.it l' ape 9 of 22 Itev. O

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

i

[

i I

l 4

I I

i t

1' 6-l

~ ACCEPTABLE 5--

OPERATION REGION (EOC,4.5) j

-Oz e

l cr:

I d

4--

i

_J W-0

(

6 (BOC, 3.5) z l

3" l

MINUMUM SHUTDOWN MARGIN t

E l

0 o

2 "

UNACCEPTABLE i,

H D

OPERATION I

e REGION 1-i l

I l

0 i

l BOC EOC..

}

i

}-

TIME IN CYCLE i

}

I

)

Figure 3.1.1-1 t

Shutdown Margin vs. Time in Cycle i

Calvert ClilTs 2, Cvele 12 col,R l' age 10 of 22 Rev.O l

-. =

t l

1 l

70 I

I 60 c (1.57,60) j 50 --

_v)

N E

r g

40 --

1002 - 600 Fa oz 30 o

.i 6

20 --

tu3 i:

10 --

ALLOWED REGION 0--

)

(1.67, 0) 1.55 1.60 1.65 1.70 MEASURED PRE-MISALIGNED TOTAL INTEGRATED RADIAL PEAKING FACTOR Figure 3.1.3-1 Allowable Time to Realign CEA Versus initial Totalintegrated Radial Peaking Factor Palvett rtiffs 2 rvele 12 Col,lt l' age !) of 22 Rev.O

.- - -.-~.

.-.. ~ -.

~-.

t 1

l 1

I l

l l

l I

1.000 c

, - (1.00. Group 5 @ 35%)

e O.900

- (O E Grotp5@ 35 %i e }(

E o

0.800 i

A-(-).75, i3roup 5@ 50%)

t e\\(0.7 3, Gnup 5 @ 60".)

(

0.700 (O.SS, G'oup! @85%)

l g

s l

0 8

% 0.600 i

1 i

().56, i3roup 4@ 50%)

S@

0.500

' Long ferm steady State Insertion Urnit.

0.400 Group 5 @ 25%

i l

u.

o 0.300 z

i e

O i

i 5

0.200

g
3. G]up 3 (0.2

@ 60".)

' short Term steady 8

l l

O.100 _

'. state insertion umit.

L l

a e

Group 4 @ 20%

O.000 I

I I

I IU'U ' U' "" 0 6U I e

Allowable OASSS M - (Group 5 @ 55%)

Operating Region 5

3 1

I I

I I

I I

I I

I I

I I

I 1

I I

I I

O 20 40 60 80 100 0 20 40 60 80 100 0 20 40 60 80 100 13G 0 108.8 81.6 54.4 27.2 0.0133.0 108.8 81.6 54.4 27.2 0.0136.0 108.8 81.6 54.4 27.2 0.0 4

2 I

I I

I I

I I

I I

I I

I O

20 40 60 80 100 0 20 40 60 80 100 136.0 108.8 81.6 54.4 27.2 0.0136.0 108.8 81.6 54.4 27.2 0.0 l

I l

l

%CEA INSERTION INCHES CEA WITHDRAWN i

1 1

Figure 3.1.3-2

~

CEA Group Insertion Limits vs. Fraction of Rated Thermal Power i

Calvert (lilk ?. Cvele 12 C()l.it l' ace 12 of 22 ig ey, <,

l i

17.0 l

16.5 b

h 16.0 uI _

He kO l- < 15.5 1

<m ww

t o e9

<.=

W + 15.0 IEE o a<J M0 UNACCEPTABLE OPERATION

$ 314.5 c ACCEPTABLE OPERATION ma 4

4~

>g 14.0

.J

.J 13.5 -- - -

I 13 0 BOC EOQ TIME IN CYCLE Figure 3.2.1 1 Allowable Peak Linear Heat Rate vs. Time in Cycle.

calven clirrs ?. cycle I? c ol R Page n nrr n,.s.

n

1.100 1.050 --

1.000 --

(-0.06,1.00)

(0.12,1.00) 0.950 --

UNACCEPTABLE UNACCEPTABLE 0.900 OPERATION OPERATION REGION REGION a:

0.850 --

0.800 --

n.

0.750 --

0.700 --

(-0.3, 0.70)

(0.3, 0.70)

W

'~

ACCEPTABLE gg 0.600 --

OPERATION REGION

!!ll 0.550 --

o d

0.500 --

(-0.3, 0.50) g 0.450 -

5 0.400 --

Po 0.350 -

u-0.300 --

0.250 --

0.200 -

0.150 -

(-0.45, 0.15) 0.100 0.050 e:

c

-0.60

-0.40

-0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Yi Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits calvert Ulirrs 2. cycle 12 col.it l' ace 14 of 22 i<cv. o

x h

1.00 <

(1.47,1.00) o n.

d
Eewp 0.90 --

1.57, 0.90)

O N

u.

O 0.80 --

(1.785, 0.80)

P i

O ACCEPTABLE VALUE u.

w 0.70 --

1 i

)

O<

Do d

0.60

$aR<s 0.50 l

l l

1 45 1.50 1 55 1.60 1 65 1.70 1.75 1.80 1.85 T

Fxy Figure 3.2.1-3 T

Total Planar Radial Peaking Factor /Fxy vs.

Maximum Allowable Fraction of Rated Thermal Power (Surveillance 4.2.1.3)

S 4

0 t

i i

L 1.00 e (1.70,1.00)

UNACCEPTABLE T

E OPERATION o

REGION A

T I

g 0.90 --

F g xy LIMITCURVE l

Ew i

h l.

O ACCEPTABLE 1-OPERATION 0.80 --

REGION E

u.

(1.785, 0.80) r o

i z

OP U

0.70 --

N u.

w J

c)<%o 0.60 -

l i

l 0.50 e

1.65 1.70 1.75 1.80 T

Fxy i

l 1

l Figure 3.2.2-1 Total Planar Radial Peaking Factor vs.

4 Allowable Fraction of Rated Thermal Power I

(ACTION 3.2.2.1.a 1) s 4

i Calvert Cliffs 2, Cycle 12 COI.It l' age 16 of 22 1(ev. o

4 1.00 e (1.70,1.00)

UNACCEPTABLE g

OPERATION g

REGION o

n.

T Fr LIMITCURVE 0.90 --

p 5g ACCEPTABLE OPERATION o

REGION g

0.80 --

(1.785,0.80) u.ozO P'j 0.70 --

u.

c3<Do 0.60 --

d<

0.50 1.65 1.70 1.75 1.80 T

F, i

)

Figure 3.2.3-1 i

Total Integrated Radial Peaking Factor vs.

)

Allowable Fraction of Rated Thermal Power j

C IvoI Cliffs 2, Cycle 12 Col.lt Page 17 of 22 Itev. O

l i

l l

1.100 1.050 l

1.000 --

(-0.10,1.00)

(0.15,1.00) 0.950 " UNACCEPTABLE UNACCEPTABLE l

0.900 --

OPERATION OPERATION l

a W

REGION REGION l

0.850 --

1 g'

0.800 --

(-0.3, 0.80)

(0.3, 0.80) i i

g l

l o

0.750 --

l n.

1 l

g 0.700 -

co ACCEPTABLE 0.650 --

OPERATION g

3 0.600 REGION b

a l

y 0.550 --

l o

l g

0.500 --

(-0.3, 0.50)

^

l X

y 0.450 --

l Ui 0.400 --

zo 0.350 --

s U

0.300 --

l 0.250 --

t.200 -

O.150 -

(-0.45. 0.15) 0.100 --

~

0.050 e:

l

-0.60

-0.40

-0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXtAL SHAPE INDEX, Yi l

l l

l Figure 3.2.3-2 DNB Axial Flux Offset Control Limits i

I i

Calveit Cliffs 2, Cycle 12 COLR Pa:7.c 18 of'22 itev.O

LIST OF APPROVED METHODOLOGIES (1)

CENPD-199-P, Rev l-P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodobgy for Analog Protection Systems," January 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)

(2)

CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin / Low Pressure LSSS for Calvert Cliffs Units I and II,"

December 1979 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.2.1,3.2.3)

(3)

_ CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2,"

January 1980 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)

(4)

CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (Methodology for Specifications 3.1.3.6,3.2.1, i

3.2.2.1, 3.2.3, 3.2.5)

]

(5)

CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units I and 2," December 1981 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2,5)

(6)

Letter from Mr. D.11. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24,1982, Unit I Cycle 6 License Approval (Amendment No. 71 to DPR 53 and SER)[ Approval to CEN-124(B)-P (three parts) and CEN-191(B)-P)]

(7)

CEN-348(B)-P, " Extended Statistical Combination of Uncertainties," January 1987 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5) l (8)

Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21,1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9)

CENPD-161-P-A, " TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)

{

(10)

CENPD-162-P-A, " Critical lleat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975 (Methodology for Specifications i

2.2.1, 3.1.3.6, 3.2.3, 3.2.5)

(Il)

CENPD-207-P-A," Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer l

j Grids Part 2, Non-uniform Axial Power Distribution," December 1984 (Methodology for Specifications 2.2.1, 3,1.3.6, 3.2.3, 3.2.5)

(12)

CENPD-206-P A, " TORC Code, Verification and Simplified Modeling Methods," June 1981 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)

(13)

CENPD-225-P A, " Fuel and Poison Rod Bowing," June 1983 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.3, 3.2.5)

Calvert Cliffs 2, Cycle 12 COI.R

- Page 19 of 22 Rev.0

1 e l',

(14)

CENPD-266-P-A, "The ROCS and DIT Computer Code for Nuclear Design," April 1983 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)

(15)

CENPD-275-P-A, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable Absorbers," May 1988 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)

(16)

CENPD-382-P-A, " Methodology for Core Designs Containing Erbium Burnable Absorbers," August 1993 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1, 3.2.3, 3.2.5)

(17)

CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)

(18)

CEN-161-(B)-P-A, " Improvements to Fuel Evaluation Model," August 1989 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)

(19)

CEN-161-(B)-P, Supplement 1-P, " Improvements to Fuel Evaluation Model," April 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)

(20)

Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-161-(B)-P, Supplement 1-P, Improvements to Fuel Evaluation Model" (Approval of CEN-161(B), Supplement 1-P)

(21)

CEN-372-P-A, " Fuel Rod Maximum Allowable Gas Pressure," May 1990 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.1, 3.2.2.1 )

(22)

Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC) dated December 15,1981, LD-81-095, Enclosure 1-P, "C-E ECCS Evaluation Model Flow Blockage Analysis" (Methodology for Specifications 3.2.1,3.2.2.1) 4 (23)

CENPD-132, Supplement 3-P-A, " Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and.W Designed NSSS," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1 and approval of Letter LD-81-095, dated December 15,1981) j (24)

CENPD-133, Supplement 5,"CEFLASH-4A, a FORTRAN 77 Digital Computer Program for Reactor Blowdown Analysis," June 1985 (Methodology for Specifications 3.2.1, 3.2.2.1)

(25)

CENPD-134, Supplement 2,"COMPERC-II, A Program for Emergency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1) l (26)

Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE), dated July 31,1986,

" Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and 1

Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133, Supplement 5 and CENPD-134, Supplement 2)

(27)

CENPD-135, Supplement 5-P,"STRIKIN-ll, A Cylindrical Geometry Fuel Rod lleat Transfer Program," April 1977 (Methodology for Specifications 3.2.1,3.2.2.1)

I t

rNN[rliffs 2. cvele 12 col.R Pane 20 of 22 Rev.O

l (28)

Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6,1978,

" Evaluation of Topical Report CENPD-135, Supplement 5" l

(29)

CENPD-137, Supplement 1-P, " Calculative Methods for the C-E Small Break LOCA l

Evaluation Model," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)

(30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, "A Computer Program for the Reactor l

Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 l

(Methodology for Specifications 3.2.1,3.2.2.1)

(31)

Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE), dated September 27,1977, l

" Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P" l

(32)

CENPD-138, Supplement 2-P," PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)

(33)

Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer (CE), April 10,1978. " Evaluation of Topical Report CENPD-138, Supplement 2-P" l

(34)

Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC), dated February 22,1985, "Calvert Cliffs Nuclear Power Plant Unit 1, Docket No. 50-317, Amendment to Operating License DPR-53, Eighth Cycle License Application" (Section 7.3.2 contains Methodology for Specifications 3.1.1.1 and 3.1.1.4 and 3.1.3.6)

(35)

Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated May 20, 1985, Safety Evaluation Repon Approving Unit 1 Cycle 8 License Application l

l (36)

Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September l

22,1980, " Amendment to Operating License No. 50-317, Fifth Cycle License l

Application (Section 7.1.2 contains Methodology for Specifications 3.1.1.2,3.9.1) l (37)

Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated December 12,1980," Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" (38)

Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1, 1986, "Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Docket Nos. 50-317 and 50-318, Request for Amendment"(Methodology for Specifications 3.1.3.1) l (39)

Letter from S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated July 7,1987, Docket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2)

(Support for Specification 3.1.3.1) l l

(40)

CENPD-188-A,"llERMITE: A Multi-Dimensional Space - Time Kinetics Code for PWR Transients," July 1976 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1, 3.2.2.1, 3.2.3, 3.2.5) l Calvert Cliffs 2, Cycle 12 cot.R Page 21 of 22 Rev.O

O (41)

The Full Core Power Distribution Monitoring System referenced in Specifications 3.1.3.1,3.2.2.1,3.2.3, and the BASES is described in the following documents:

(a)

CENPD-153-P, Revision 1-P-A, " Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.1, 3.2.2.1, 3.2.3, 3.2.5)

(b)

CEN-119(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit 1 and Unit 2," November 1979 (Referenced in Appendix B of Unit 2 Cycle 9 License Application)

(c)

Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318. Request for Amendment, Unit 2 Ninth Cycle License Application" (Appendix B contains Methodologies for Specifications 3.1.3.1,3.2.2.1,3.2.3, 3.2.5)

(d)

Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10,1990, " Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42)

Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995,"Approva! to Use Convolution Technique in Main Steam Line Break Analysis -

Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 (TAC Nos. M90897 and M90898) l i

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l Calvert Clifts 2, Cycle 12 COLR Page 22 of 22 Rev.0

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