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=Text=
=Text=
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{{#Wiki_filter:'.
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w cn wau r vue Pxt 0% e Ra N9 lt im;m Ahnu $3!H
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Eu(. INION
                                                                                                "*" *'" """ ?
"*" *'" """ ?
Eu(.crme INION                                                                            ;
crme
                'i3 January 29, 1 92 U.S. Nucleas Regulatory Commission Attn: Documes'.c Control Desk Mail Station F1-137 Washington, D.C. 20555                                         ULNRC- 2 551 Gentlemen:
'i3 January 29, 1 92 U.S. Nucleas Regulatory Commission Attn: Documes'.c Control Desk Mail Station F1-137 Washington, D.C.
20555 ULNRC-2 551 Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT - CYCLE 5 CORE OPERATING LIMITS REPORT
DOCKET NUMBER 50-483 CALLAWAY PLANT - CYCLE 5 CORE OPERATING LIMITS REPORT


Line 30: Line 31:
: 2) ULNRC-2360 dated January 31, 1991
: 2) ULNRC-2360 dated January 31, 1991
: 3) ULNRC-2379 dated March 19, 1991
: 3) ULNRC-2379 dated March 19, 1991
: 4) ULNRC-2513 dated November 13, 1991 j                                            5) ULNRC-2532 dated December 12, 1991 Reference 1 transmitted the Callaway Plant Cycle 5 Core Operating Limits Report (COLR). Attached please find Revision 6 to Sections 2.4.1, 2.5 and Figure 7 of the COLR. Revision 6-modifies the Axial Flux Difference (AFD) target band and corresponding W(Z) values to +12%, -7% for Normal Operation. The revised AFD target bands are applicable through the end of Cycle 5.
: 4) ULNRC-2513 dated November 13, 1991
: 5) ULNRC-2532 dated December 12, 1991 j
Reference 1 transmitted the Callaway Plant Cycle 5 Core Operating Limits Report (COLR).
Attached please find Revision 6 to Sections 2.4.1, 2.5 and Figure 7 of the COLR.
Revision 6-modifies the Axial Flux Difference (AFD) target band and corresponding W(Z) values to +12%, -7% for Normal Operation.
The revised AFD target bands are applicable through the end of Cycle 5.
Should you have any questions concerning this information, please contact us.
Should you have any questions concerning this information, please contact us.
Very truly yours, f)           .,
Very truly yours, f) lf,J
lf,J                 .
,- t -. ' f2ff g Art- '< ~
                                                              ,- t - . ' f2ff g Art- '< ~
Donald F.
Donald F. Schnell WEK/ dis Attachment T
Schnell WEK/ dis Attachment T
                                                                                                          ?j 9202030266 92C129 i                 PDR     ADOCK 05000483 P                        PDR l
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_ . . _ . _. _ ..___-._                  _.__ _ .-                                            . . _ . _ _ _ . _ _ . = - - .. _._ _ _ _ _ - . . - - .
.. _. _ _ _. _ _. = - -..
cc t _     T. A. . Baxt er, I''sq .
cc t _
T. A.. Baxt er, I''sq.
Shaw, -- Pittman, Potts & Trowbridge 2300 N.-Street, N.W.
Shaw, -- Pittman, Potts & Trowbridge 2300 N.-Street, N.W.
Washinoton, D.C. 20037 Dr. J. O. Cermak CFA, Inc.
Washinoton, D.C. 20037 Dr. J. O. Cermak CFA, Inc.
18225-A~ Flower Hill Way.
18225-A~ Flower Hill Way.
Gaithersburg, MD 20879-5334 R. C. Knop.
Gaithersburg, MD 20879-5334 R.
Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III                                                                                                   1 799 Roosevelt Road                                                                                         J Glen Ellyn, Illinois 60137 Bruce Bartlett Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077                                                                                     l L. R. Wharton (2)                                                                                             .
C.
Knop.
Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 1
799 Roosevelt Road J
Glen Ellyn, Illinois 60137 Bruce Bartlett Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077 L. R. Wharton (2)
Office of' Nuclear Reactor Regulation U.S. Nuclear: Regulatory Commission 1 White Flint,. North, Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20852 Manager,fElectric Department Missouri Public Service Commission P.O.-Box 360 Jefferson City, MO 65102
Office of' Nuclear Reactor Regulation U.S. Nuclear: Regulatory Commission 1 White Flint,. North, Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20852 Manager,fElectric Department Missouri Public Service Commission P.O.-Box 360 Jefferson City, MO 65102
                                                                                                                                                              ' I e
' I e


bc'c:-D.-Shafer/A160.761
bc'c:-D.-Shafer/A160.761
                                /QA Record (CA-758)
/QA Record (CA-758)
Nuclear Date E210.01-
Nuclear Date E210.01-
                    .DFS/ Chrono D..F. Schnell J. E..B12:k J. V. Laux M .- A . Stiller-G. L. Randolph
.DFS/ Chrono D..F.
                    .R. J. Irwin P. Barrett C. D. Naslund.
Schnell J. E..B12:k J. V.
A. C. Passwater D. E. Shafer.                                                                                                         -
Laux M.- A. Stiller-G.
W.-E. Kahl(4 S. Wideman (WCNOC)
L. Randolph
.R.
J.
Irwin P.
Barrett C. D. Naslund.
A.
C.
Passwater D.
E.
Shafer.
W.-E.
Kahl(4 S. Wideman (WCNOC)
R. C. Slovic (Bechtel)
R. C. Slovic (Bechtel)
T. P. Sharkey NSRB (Sandra Dale) s I
T.
P. Sharkey NSRB (Sandra Dale) s I
me I
me I
l
l
_      ___-_.-__._-_.m_ __.m_m_____.___.__ .----_._ a - m .___._..._ -_  - -.. _.__.___._ __u_   __m__.-._-.
___-_.-__._-_.m_
__.m_m_____.___.__
a m
__u_
__m__.-._-.


m..>     _._ .            _ _            _.      .      - _ . _ _ . _ _ _ _ - - _ . . _ _ . . _ _ . ~ _ . _ _ _ . _ _ _ . _ . _ _ . . . _ _ _ .
m..>
r JAN 26 '92 17:06'                     FROM COM HUCLEAR FUEL D!V                                                               -                            PAGE.003 Westinghouse Proprietary Cass 3 -
- _. _ _. _ _ _ _ - - _.. _ _.. _ _. ~ _. _ _ _. _ _ _. _. _ _... _ _ _.
catim, cwe 5                                                                                                                                 f g,yy 1.4 - - Arial hr Difference (Specification 3.2.1) _
r JAN 26 '92 17:06' FROM COM HUCLEAR FUEL D!V PAGE.003 Westinghouse Proprietary Cass 3 -
2.4.1 The Axial Rux Difference (AFD) taryct bands are,
f catim, cwe 5 g,yy 1.4 - - Arial hr Difference (Specification 3.2.1) _
                                                    +l'LT                                                     -
2.4.1 The Axial Rux Difference (AFD) taryct bands are,
a._   48%, 7% for Normal Operation                                                                                                         '
+l'LT a._
: b.     3% for Restricted AFD Operation 2A.2 The Acceptable Operation Lindts are shown in Figure 3.
48%, 7% for Normal Operation b.
3% for Restricted AFD Operation 2A.2 The Acceptable Operation Lindts are shown in Figure 3.
2A.3 The minimum allowable power level for Restricted AFD Operation. APLN, is 90% of RATED THERMAL POWER.
2A.3 The minimum allowable power level for Restricted AFD Operation. APLN, is 90% of RATED THERMAL POWER.
x l
x l
1 Page 7 of 15 i
1 Page 7 of 15 i
i
~ - - - - --
                                                                                                , , _ ,            .                                    ~ - - - - --   " - - - ' - ' ' "'1
"'1


        .)AN.EG '92 17:07     FROM COM NUCLEAR FUEL DIV                                       PAGE.005 Callaway Cycle 5                                                             Rev. /
.)AN.EG '92 17:07 FROM COM NUCLEAR FUEL DIV PAGE.005 Callaway Cycle 5 Rev. /
                  ^
2.5 ' Hant' El'ur Hot channel Factgr - F (Z)
2.5 ' Hant' El'ur Hot channel Factgr - F9(Z)
^
(specification 3.2.2)
(specification 3.2.2) 9 RTP Y
RTP           .
F (2) 5 E---
Y Fg (2) 5 E---
g K(Z) for P > 0.5 P
* K(Z)                 for P > 0.5 P
RTP T
T RTP Tg (Z) $ o.sA--
T (Z) $ A--
* K(Z)                   for P $ 0.5 THERMAL POWER where   P = ----------              - - - - -
* K(Z) for P $ 0.5 g
RATED THERFAL POWER RTP 2.5.1   F     = 2.50 0
o.s THERMAL POWER where P = ----------
2.5.2   K(c) is providad in Figure 4.
RATED THERFAL POWER RTP 2.5.1 F
2.5.3 The W(z) functions that are to be used in Technical Specifications 4.2.2.2, 4.2.2.3, and 4.2.2.4 for FQ surveillance are shown in .^1gures 5 through 8.
= 2.50 0
Becauno significant nargin exists between the analyt1cally deterr.ined max 1:=na P0(z)*Prel values and their lisait, Restricted Arial Flux Difference (RAFDO) operation is not expected to be required for Cycle 5. Por this reason, no W(2)         values are supplied for Cycic 5.
2.5.2 K(c) is providad in Figure 4.
RAFDO The Norral Ope. ration W(z) values, W(z)       , were orig hn11y N3 determined fer three specific burnupc in Cycle 5, accu =ing Cycle 5 operates with the CAOC strategy and unce a +3%,
2.5.3 The W(z) functions that are to be used in Technical Specifications 4.2.2.2, 4.2.2.3, and 4.2.2.4 for FQ surveillance are shown in.^1gures 5 through 8.
                                        -12% dalta-I band about the target flux dif ference. This permita determination of W(z) at any cycle burnup through the use of three point interpolation. The end of cycle W( ) value has been revised based on Ch0C operation with a +12. *1% deltn I band about the target flux difference.
Becauno significant nargin exists between the analyt1cally deterr.ined max 1:=na P0(z)*Prel values and their lisait, Restricted Arial Flux Difference (RAFDO) operation is not expected to be required for Cycle 5. Por this reason, no W(2) values are supplied for Cycic 5.
Une of this M(L) value for Cycle 5 burnups from 16000 MND/MTU until end of cycle is conservative. Interpolation with the +3%,-12% W(:) values from esalier burnups should not be perf omed. Also included is a W(z)           function that bounds NO the W(=)       curyca based on a +3%,-12% delta-I band for NO all Cycle 5 burnupo. Thie in not appropriate to une t-for delta-I handa other than +M ,-12% about the target flux               ;
RAFDO The Norral Ope. ration W(z) values, W(z) were orig hn11y N3 determined fer three specific burnupc in Cycle 5, accu =ing Cycle 5 operates with the CAOC strategy and unce a +3%,
l                                      difference.
-12% dalta-I band about the target flux dif ference. This permita determination of W(z) at any cycle burnup through the use of three point interpolation. The end of cycle W( ) value has been revised based on Ch0C operation with a +12.
*1% deltn I band about the target flux difference.
Une of this M(L) value for Cycle 5 burnups from 16000 MND/MTU until end of cycle is conservative. Interpolation with the +3%,-12% W(:) values from esalier burnups should not be perf omed. Also included is a W(z) function that bounds NO the W(=)
curyca based on a +3%,-12% delta-I band for NO all Cycle 5 burnupo. Thie in not appropriate to une t -
for delta-I handa other than +M,-12% about the target flux l
difference.
Page 3 of 15 l
Page 3 of 15 l
l I
l l
l


,JAN 2B '92 17 06     FROM COM NUCLEAR FUEL DIV                               PAGE.004 Rev. 6 INCORE Height             W(Z)           INCORE     Height       W(Z)
,JAN 2B '92 17 06 FROM COM NUCLEAR FUEL DIV PAGE.004 Rev. 6 INCORE Height W(Z)
    - Point- (Feet)~           16000.           Point     (Feat)       16000.
INCORE Height W(Z)
Top _   1. 0.00000
- Point-(Feet)~
* 1.0000           37.       6.0000       1.1974
16000.
: 2. 0.16700
Point (Feat) 16000.
* 1.0000           38.       6.1670       1.2033
Top _
: 3. 0.33300
1.
* 1.0000           39.       6.3330       1.2076
0.00000
: 4. 0.50000
* 1.0000 37.
* 1.0000           40.       6.5000       1.2104
6.0000 1.1974 2.
: 5. 0.66700
0.16700
* 1.0000           41.       6.6670       1.2116
* 1.0000 38.
: 6. 0.83300
6.1670 1.2033 3.
* 1.0000           42.       6.8330       1.2112
0.33300
: 7. 1.0000
* 1.0000 39.
* 1.0000          43.      7.0000      1.2089
6.3330 1.2076 4.
: 8. 1.1670
0.50000
* 1.0000          44.      7.1670      1.2056
* 1.0000 40.
: 9. 1.3330
6.5000 1.2104 5.
* 1.0000          45,      7.3330      1.2032
0.66700
: 10. 1.5000
* 1.0000 41.
* 1.0000          46,      7.5000      1.2030
6.6670 1.2116 6.
: 11. 1.6670
0.83300
* 1.0000          47,      7.6670      1.2045
* 1.0000 42.
: 12. 1.8330            1.1629          48.      7.8330      *
6.8330 1.2112 7.
                                                                            .2057
: 13. 2.0000            1.158E          49.      8.0000      1.2055
: 14. 2.1670            1.1536          50.      8.1670      1.2047 15,    2.3330            1.1483            51        8.3330      1.2044
: 16. 2.5000            1.1426            52.      8.5000      1.2037
: 17. 2.6670            1.1365            53.      8.6670      1.2016 18,    2.8330            1.1300            54.      8.8330      1.1982 19,    3.0000            1.1228            55,      9.0000      1.1958
: 20. 3.1670          1.1162            56.      9.1670      1.1953 21,    3.3330          1.1125            57,      9.3330      1.1964-
      -22,    3.5000          1.1149            58.      9.5000      1.1977
: 23. 3.6670          1.1205            59.      9.6670      1.1999 24,    3.8330          1.1250            60.      9.8330      1.1995
: 25. 4.0000            1.1300          61,      10.000      1.1998 26,    4.1670            1.1360          62.      10.167      1.2007 27,    4.3330            1.1421          63.      10.333  * .
1.0000
1.0000
: 28. 4.5000           1.1476           64,       10.500
* 1.0000 43.
* 1.0000 29,     4.6670           1.1523           65.       'O.667
7.0000 1.2089 8.
* 1.0000
1.1670
: 30. 4.8330           1.1562           66.       .0.833
* 1.0000 44.
* 1.0000
7.1670 1.2056 9.
: 31. 5.0000           1.1597           67,       11.000
1.3330
* 1.0000-
* 1.0000 45, 7.3330 1.2032 10.
: 32. 5.1670           1.1622-         68.       11.167
1.5000
* 1.0000
* 1.0000 46, 7.5000 1.2030 11.
: 33. 5.3330           1.1646           69.     11.333
1.6670
* 1.0000
* 1.0000 47, 7.6670 1.2045 12.
: 34. 5.5000           1.1715           70.       11.500
1.8330 1.1629 48.
* 1.0000 35,   5.6670           1.1813           71,       11.667
7.8330
* 1.0000
.2057 13.
: 36. 5.8330           1.1900           72.       11.833
2.0000 1.158E 49.
* 1.0000
8.0000 1.2055 14.
: 73.     12.000
2.1670 1.1536 50.
* 1.0000 Figure 7 Callaway Unit 1 Cycle 5 W( )   at 16000 MWD /MTU NO Applicable for Delta-I bands of +121,-7t For burnups from 16000 MWD /MTU until end of cycle
8.1670 1.2047 15, 2.3330 1.1483 51 8.3330 1.2044 16.
2.5000 1.1426 52.
8.5000 1.2037 17.
2.6670 1.1365 53.
8.6670 1.2016 18, 2.8330 1.1300 54.
8.8330 1.1982 19, 3.0000 1.1228 55, 9.0000 1.1958 20.
3.1670 1.1162 56.
9.1670 1.1953 21, 3.3330 1.1125 57, 9.3330 1.1964-
-22, 3.5000 1.1149 58.
9.5000 1.1977 23.
3.6670 1.1205 59.
9.6670 1.1999 24, 3.8330 1.1250 60.
9.8330 1.1995 25.
4.0000 1.1300 61, 10.000 1.1998 26, 4.1670 1.1360 62.
10.167 1.2007 27, 4.3330 1.1421 63.
10.333
* 1.0000 28.
4.5000 1.1476 64, 10.500
* 1.0000 29, 4.6670 1.1523 65.
'O.667
* 1.0000 30.
4.8330 1.1562 66.
.0.833
* 1.0000 31.
5.0000 1.1597 67, 11.000
* 1.0000-32.
5.1670 1.1622-68.
11.167
* 1.0000 33.
5.3330 1.1646 69.
11.333
* 1.0000 34.
5.5000 1.1715 70.
11.500
* 1.0000 35, 5.6670 1.1813 71, 11.667
* 1.0000 36.
5.8330 1.1900 72.
11.833
* 1.0000 73.
12.000
* 1.0000 Figure 7 Callaway Unit 1 Cycle 5 W( )
at 16000 MWD /MTU NO Applicable for Delta-I bands of +121,-7t For burnups from 16000 MWD /MTU until end of cycle
* Top and Bottom 15% Excluded as per Tech Spec 4.2.2.2G Page 13 of 15
* Top and Bottom 15% Excluded as per Tech Spec 4.2.2.2G Page 13 of 15


    ,:;, tj EE     'u     . tic 7       rnon Con tssCLE M FLEL Liv                                                                                     HGE.006 lo callaway cycle 5                                                                                                                     Rev. /
,:;, tj EE 'u
                        -- _ _1Z. ..,. . 4 a, .-y< _ . _ %:, C, ._s u
. tic 7 rnon Con tssCLE M FLEL Liv HGE.006 lo callaway cycle 5 Rev. /
_ 2.. y y g                               .
-- _ _1Z...,.. 4 a,.-y< _. _ %:, C, _ 2.. y y g x.
x.
._s u
values are provided for 73 axial The points    W(z) as isuming the core height boundaries of-0 and 12 feet and intervals of .167 feet between the core boundaries.
The W(z) isuming the core height boundaries of-values are provided for 73 axial points as 0 and 12 feet and intervals of.167 feet between the core boundaries.
2.6         Nuclear Enthalov Rise Met Channel Factor -                                                                   F N
2.6 Nuclear Enthalov Rise Met Channel Factor -
(Specification 3.2.3)
F (Specification 3.2.3)
Tg N,p RTP g                    gy ,p7g(y,p))
N T N,p RTP gy,p7g(y,p))
where:                       THERMAL POWER y . ...................
g g
where:
THERMAL POWER y....................
RATED THERF.AL POWER I
RATED THERF.AL POWER I
2.6.1         Fg                - 1.59 2.6.2         PTg = 0.3 2.7         Refuelina Boron __ concentration (Specification 3.9.1) 2.7.1                 The refueling boron concentration to maintain k,ff 5 0.95 shall be 1 2000 ppm.
2.6.1 F
- 1.59 g
2.6.2 PTg = 0.3 2.7 Refuelina Boron __ concentration (Specification 3.9.1) 2.7.1 The refueling boron concentration to maintain k,ff 5 0.95 shall be 1 2000 ppm.
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Latest revision as of 06:25, 13 December 2024

Forwards Rev 6 to Sections 2.4.1,2.5 & Figure 7 of Core Operating Limits Rept.Revised Axial Flux Difference Target Bands Applicable Through End of Cycle 5
ML20100P926
Person / Time
Site: Callaway 
Issue date: 01/29/1992
From: Schnell D
UNION ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ULNRC-2551, NUDOCS 9202030266
Download: ML20100P926 (7)
v • d • e


Text

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w cn wau r vue Pxt 0% e Ra N9 lt im;m Ahnu $3!H

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Eu(. INION

"*" *'" """ ?

crme

'i3 January 29, 1 92 U.S. Nucleas Regulatory Commission Attn: Documes'.c Control Desk Mail Station F1-137 Washington, D.C.

20555 ULNRC-2 551 Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT - CYCLE 5 CORE OPERATING LIMITS REPORT

References:

1) ULNRC-2323 dated November 3 4, 1990
2) ULNRC-2360 dated January 31, 1991
3) ULNRC-2379 dated March 19, 1991
4) ULNRC-2513 dated November 13, 1991
5) ULNRC-2532 dated December 12, 1991 j

Reference 1 transmitted the Callaway Plant Cycle 5 Core Operating Limits Report (COLR).

Attached please find Revision 6 to Sections 2.4.1, 2.5 and Figure 7 of the COLR.

Revision 6-modifies the Axial Flux Difference (AFD) target band and corresponding W(Z) values to +12%, -7% for Normal Operation.

The revised AFD target bands are applicable through the end of Cycle 5.

Should you have any questions concerning this information, please contact us.

Very truly yours, f) lf,J

,- t -. ' f2ff g Art- '< ~

Donald F.

Schnell WEK/ dis Attachment T

?j 9202030266 92C129 i

PDR ADOCK 05000483 g (

l P

PDR 1R y

.. _. _ _ _. _ _. = - -..

cc t _

T. A.. Baxt er, Isq.

Shaw, -- Pittman, Potts & Trowbridge 2300 N.-Street, N.W.

Washinoton, D.C. 20037 Dr. J. O. Cermak CFA, Inc.

18225-A~ Flower Hill Way.

Gaithersburg, MD 20879-5334 R.

C.

Knop.

Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 1

799 Roosevelt Road J

Glen Ellyn, Illinois 60137 Bruce Bartlett Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077 L. R. Wharton (2)

Office of' Nuclear Reactor Regulation U.S. Nuclear: Regulatory Commission 1 White Flint,. North, Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20852 Manager,fElectric Department Missouri Public Service Commission P.O.-Box 360 Jefferson City, MO 65102

' I e

bc'c:-D.-Shafer/A160.761

/QA Record (CA-758)

Nuclear Date E210.01-

.DFS/ Chrono D..F.

Schnell J. E..B12:k J. V.

Laux M.- A. Stiller-G.

L. Randolph

.R.

J.

Irwin P.

Barrett C. D. Naslund.

A.

C.

Passwater D.

E.

Shafer.

W.-E.

Kahl(4 S. Wideman (WCNOC)

R. C. Slovic (Bechtel)

T.

P. Sharkey NSRB (Sandra Dale) s I

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

r JAN 26 '92 17:06' FROM COM HUCLEAR FUEL D!V PAGE.003 Westinghouse Proprietary Cass 3 -

f catim, cwe 5 g,yy 1.4 - - Arial hr Difference (Specification 3.2.1) _

2.4.1 The Axial Rux Difference (AFD) taryct bands are,

+l'LT a._

48%, 7% for Normal Operation b.

3% for Restricted AFD Operation 2A.2 The Acceptable Operation Lindts are shown in Figure 3.

2A.3 The minimum allowable power level for Restricted AFD Operation. APLN, is 90% of RATED THERMAL POWER.

x l

1 Page 7 of 15 i

~ - - - - --

"'1

.)AN.EG '92 17:07 FROM COM NUCLEAR FUEL DIV PAGE.005 Callaway Cycle 5 Rev. /

2.5 ' Hant' El'ur Hot channel Factgr - F (Z)

^

(specification 3.2.2) 9 RTP Y

F (2) 5 E---

g K(Z) for P > 0.5 P

RTP T

T (Z) $ A--

  • K(Z) for P $ 0.5 g

o.s THERMAL POWER where P = ----------

RATED THERFAL POWER RTP 2.5.1 F

= 2.50 0

2.5.2 K(c) is providad in Figure 4.

2.5.3 The W(z) functions that are to be used in Technical Specifications 4.2.2.2, 4.2.2.3, and 4.2.2.4 for FQ surveillance are shown in.^1gures 5 through 8.

Becauno significant nargin exists between the analyt1cally deterr.ined max 1:=na P0(z)*Prel values and their lisait, Restricted Arial Flux Difference (RAFDO) operation is not expected to be required for Cycle 5. Por this reason, no W(2) values are supplied for Cycic 5.

RAFDO The Norral Ope. ration W(z) values, W(z) were orig hn11y N3 determined fer three specific burnupc in Cycle 5, accu =ing Cycle 5 operates with the CAOC strategy and unce a +3%,

-12% dalta-I band about the target flux dif ference. This permita determination of W(z) at any cycle burnup through the use of three point interpolation. The end of cycle W( ) value has been revised based on Ch0C operation with a +12.

  • 1% deltn I band about the target flux difference.

Une of this M(L) value for Cycle 5 burnups from 16000 MND/MTU until end of cycle is conservative. Interpolation with the +3%,-12% W(:) values from esalier burnups should not be perf omed. Also included is a W(z) function that bounds NO the W(=)

curyca based on a +3%,-12% delta-I band for NO all Cycle 5 burnupo. Thie in not appropriate to une t -

for delta-I handa other than +M,-12% about the target flux l

difference.

Page 3 of 15 l

l l

,JAN 2B '92 17 06 FROM COM NUCLEAR FUEL DIV PAGE.004 Rev. 6 INCORE Height W(Z)

INCORE Height W(Z)

- Point-(Feet)~

16000.

Point (Feat) 16000.

Top _

1.

0.00000

  • 1.0000 37.

6.0000 1.1974 2.

0.16700

  • 1.0000 38.

6.1670 1.2033 3.

0.33300

  • 1.0000 39.

6.3330 1.2076 4.

0.50000

  • 1.0000 40.

6.5000 1.2104 5.

0.66700

  • 1.0000 41.

6.6670 1.2116 6.

0.83300

  • 1.0000 42.

6.8330 1.2112 7.

1.0000

  • 1.0000 43.

7.0000 1.2089 8.

1.1670

  • 1.0000 44.

7.1670 1.2056 9.

1.3330

  • 1.0000 45, 7.3330 1.2032 10.

1.5000

  • 1.0000 46, 7.5000 1.2030 11.

1.6670

  • 1.0000 47, 7.6670 1.2045 12.

1.8330 1.1629 48.

7.8330

.2057 13.

2.0000 1.158E 49.

8.0000 1.2055 14.

2.1670 1.1536 50.

8.1670 1.2047 15, 2.3330 1.1483 51 8.3330 1.2044 16.

2.5000 1.1426 52.

8.5000 1.2037 17.

2.6670 1.1365 53.

8.6670 1.2016 18, 2.8330 1.1300 54.

8.8330 1.1982 19, 3.0000 1.1228 55, 9.0000 1.1958 20.

3.1670 1.1162 56.

9.1670 1.1953 21, 3.3330 1.1125 57, 9.3330 1.1964-

-22, 3.5000 1.1149 58.

9.5000 1.1977 23.

3.6670 1.1205 59.

9.6670 1.1999 24, 3.8330 1.1250 60.

9.8330 1.1995 25.

4.0000 1.1300 61, 10.000 1.1998 26, 4.1670 1.1360 62.

10.167 1.2007 27, 4.3330 1.1421 63.

10.333

  • 1.0000 28.

4.5000 1.1476 64, 10.500

  • 1.0000 29, 4.6670 1.1523 65.

'O.667

  • 1.0000 30.

4.8330 1.1562 66.

.0.833

  • 1.0000 31.

5.0000 1.1597 67, 11.000

  • 1.0000-32.

5.1670 1.1622-68.

11.167

  • 1.0000 33.

5.3330 1.1646 69.

11.333

  • 1.0000 34.

5.5000 1.1715 70.

11.500

  • 1.0000 35, 5.6670 1.1813 71, 11.667
  • 1.0000 36.

5.8330 1.1900 72.

11.833

  • 1.0000 73.

12.000

  • 1.0000 Figure 7 Callaway Unit 1 Cycle 5 W( )

at 16000 MWD /MTU NO Applicable for Delta-I bands of +121,-7t For burnups from 16000 MWD /MTU until end of cycle

,:;, tj EE 'u

. tic 7 rnon Con tssCLE M FLEL Liv HGE.006 lo callaway cycle 5 Rev. /

-- _ _1Z...,.. 4 a,.-y< _. _ %:, C, _ 2.. y y g x.

._s u

The W(z) isuming the core height boundaries of-values are provided for 73 axial points as 0 and 12 feet and intervals of.167 feet between the core boundaries.

2.6 Nuclear Enthalov Rise Met Channel Factor -

F (Specification 3.2.3)

N T N,p RTP gy,p7g(y,p))

g g

where:

THERMAL POWER y....................

RATED THERF.AL POWER I

2.6.1 F

- 1.59 g

2.6.2 PTg = 0.3 2.7 Refuelina Boron __ concentration (Specification 3.9.1) 2.7.1 The refueling boron concentration to maintain k,ff 5 0.95 shall be 1 2000 ppm.

1 Page 15 of 15

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