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| issue date = 01/10/1992
| issue date = 01/10/1992
| title = Nonproprietary Version of CDC-92-014, Peaking Factor Limit Rept Evaluation for Salem Unit 2 Cycle 7 Redesign.
| title = Nonproprietary Version of CDC-92-014, Peaking Factor Limit Rept Evaluation for Salem Unit 2 Cycle 7 Redesign.
| author name = GREEN L, WILEY R A
| author name = Green L, Wiley R
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
| addressee name =  
| addressee name =  
Line 18: Line 18:
=Text=
=Text=
{{#Wiki_filter:*
{{#Wiki_filter:*
* CDC-92-014 Ref. 1: CDC-91-307 2: PNG-92-005 PEAKING FACTOR LIMIT REPORT EVALUATION FOR SALEM UNIT 2 CYCLE 7 REDESIGN VERIFIER:
* CDC-92-014 Ref. 1: CDC-91-307 2: PNG-92-005 PEAKING FACTOR LIMIT REPORT EVALUATION FOR SALEM UNIT 2 CYCLE 7 REDESIGN L. Green Core Design C                   Date:
L. Green Core Design C (J.O. R.. A. Wiley () Core Design C -----c::--------------,--,, ,r-9204160043 920409 I PDR ADOCK 05000311 p PDR Date: Date:
(J.O. W-~
1 of 3 
VERIFIER:    R.. A. Wiley ( )
*
Core Design C                   Date:    /-/o-'f~
* RADIAL PEAKING FACTOR LIMIT REPORT This radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.l.10 of the Salem Unit 2 Nuclear Plant Technical Specifications.
1 of 3
The Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 7 shall be: 1. For all core planes containing Bank "D" control rods: _RTP r--< 2.26 for all core elevations  
  -----c::- -------------,--,,
',INCORE axial points xy -1 through 61, inclusive).
,r- 9204160043 920409 I     PDR ADOCK 05000311 p               PDR
: 2. For all unrodded planes: 1-TP < 1.68 for all core elevations (INCORE axial points xy -1 through 61, inclusive).
 
These F (z) limits were used to confirm that the heat flux hot xy channel factor FQ(z) will be limited to the Technical Specification values of: F (z) < (2*32] (K( )] f P > 0 5 d Q z . or . an , p FQ(z) (4.64] (K(z)J for P < 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of control Banlcs C and D during operation, including the accompanying variations in the axial xenon and power distributions as described in the "Power Distribution Control and Load Following Procedures", WCAP-8385, September, 1974. Therefore, these F limits provide assurance that the initial xy conditions assumed in the I..OCA analysis are met, along the ECCS acceptance criteria of lOCFR.50.46.  
RADIAL PEAKING FACTOR LIMIT REPORT This radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.l.10 of the Salem Unit 2 Nuclear Plant Technical Specifications.
*T See Figure 1 for a plot of (FQ PRel] versus Axial. Core Height. 2 of 3
The Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 7 shall be:
--------------* * **-'* ' ._,' L I I I r 11 6, 2. 321 i I I ! I ! ' ' -I 1 2 .... I I 1 I ! .........  
: 1. For all core planes containing Bank "D" control rods:
.._ 2. 2 I CIC I I r ,, . I\ 10.8,2. 181 I ll '' I I I c : I ' c c c ... .. r"l*C C ape M CJ C CJ I CCC cc *-I ; .... i :I ,., I -2.0 I I I -I I I I I ! i ! --:.1. 8 . I ; I : ! Cl a i I ! \ ' ; I ! ' \ ! i I : I I i I I I I : I I ! 12, 1.5 : I i ! i I 1.4 ' ' ! I I I i c I I I ! I .. i I ' 1.2 i I I .1 ! I I I : 2 4 6 8 10 12 CORE 1&#xa3; I GHT (FEET) FICUU 1 T MAXIMUM (FQ
_RTP r--xy -< 2.26 for all core elevations ',INCORE axial points 1 through 61, inclusive).
: 2. For all unrodded planes:
1-TP < 1.68 for all core elevations (INCORE axial points xy -
1 through 61, inclusive).
These F (z) limits were used to confirm that the heat flux hot xy channel factor FQ(z) will be limited to the Technical Specification values of:
32 F (z) < ( 2 * ]     (K( z )]. f or  P > 0 . 5 and ,
Q           p FQ(z) ~ (4.64]     (K(z)J   for P < 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of control Banlcs C and D during operation, including the accompanying variations in the axial xenon and power distributions as described in the "Power Distribution Control and Load Following Procedures", WCAP-8385, September, 1974.
Therefore, these F         limits provide assurance that the initial xy conditions assumed in the I..OCA analysis are met, along w~th the ECCS acceptance criteria of 10CFR.50.46.
                                  *T See Figure 1 for a plot of (FQ           PRel] versus Axial. Core Height.
2 of 3
 
  **-'* ' ._,' L 2....
I         I I       r             11 6, 2. 321                         i I           I             !
I         !
                                                                                  -                             I                           1 I         I       1                               ~
                                                                                                ......... .._   I                            !
I CIC               I                 I                                 ~
: 2. 2
                                      ~
                                            ~
                                              ,,                                     .                                               r I \ 10.8,2. 181 I
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                                  ' c I             c c c ...
                                                                .. r"l*C C ape CJ I        M   CJ   C   CCC cc
                                                                                                                                  '          I I
2.0        ;
                                                                                      .... ~
i I
                                                                                                                    *-  :I ,.,
                                                                                                                                --           I I                                   I                                       I I
I I             I
                                                                                                                                    ~
                                !                                   i                                       !
I
                                                                      ;                                      I                      :    ~
                  --:.1. 8                                                                                                               Cl
                  ~
                                                                                                              !                                I
                  .         a                                       i                                       !                       '          \
                                ;                                     I                                       !                       '         \
i                                       I
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I                                     I                                       i I
I                                                                             I                       :
I 12, 1.5 I                                                                              I                        !
:                                     I                                       i                       !
1.4 i                        I I
                              !'                                     I                                       I                       i c I                                     I                                                                 I
                                                                                                                                      !       I ..
1.2 I
                                                                                              ~
i i                                                                                                       I I                                                                                                   .1 I                                     I                                       I 2                   4               6                     8             10                           12 CORE 1&#xa3; IGHT (FEET)
FICUU 1 MAXIMUM (FQT
* Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3}}
* Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3}}

Latest revision as of 06:35, 3 February 2020

Nonproprietary Version of CDC-92-014, Peaking Factor Limit Rept Evaluation for Salem Unit 2 Cycle 7 Redesign.
ML18096A623
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/10/1992
From: Green L, Wiley R
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML18096A622 List:
References
CDC-92-014, CDC-92-14, NUDOCS 9204160043
Download: ML18096A623 (3)


Text

  • CDC-92-014 Ref. 1: CDC-91-307 2: PNG-92-005 PEAKING FACTOR LIMIT REPORT EVALUATION FOR SALEM UNIT 2 CYCLE 7 REDESIGN L. Green Core Design C Date:

(J.O. W-~

VERIFIER: R.. A. Wiley ( )

Core Design C Date: /-/o-'f~

1 of 3


c::- -------------,--,,

,r- 9204160043 920409 I PDR ADOCK 05000311 p PDR

RADIAL PEAKING FACTOR LIMIT REPORT This radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.l.10 of the Salem Unit 2 Nuclear Plant Technical Specifications.

The Fxy limits for RATED THERMAL POWER within specific core planes for Cycle 7 shall be:

1. For all core planes containing Bank "D" control rods:

_RTP r--xy -< 2.26 for all core elevations ',INCORE axial points 1 through 61, inclusive).

2. For all unrodded planes:

1-TP < 1.68 for all core elevations (INCORE axial points xy -

1 through 61, inclusive).

These F (z) limits were used to confirm that the heat flux hot xy channel factor FQ(z) will be limited to the Technical Specification values of:

32 F (z) < ( 2 * ] (K( z )]. f or P > 0 . 5 and ,

Q p FQ(z) ~ (4.64] (K(z)J for P < 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of control Banlcs C and D during operation, including the accompanying variations in the axial xenon and power distributions as described in the "Power Distribution Control and Load Following Procedures", WCAP-8385, September, 1974.

Therefore, these F limits provide assurance that the initial xy conditions assumed in the I..OCA analysis are met, along w~th the ECCS acceptance criteria of 10CFR.50.46.

  • T See Figure 1 for a plot of (FQ PRel] versus Axial. Core Height.

2 of 3

    • -'* ' ._,' L 2....

I I I r 11 6, 2. 321 i I I  !

I  !

- I 1 I I 1 ~

......... .._ I  !

I CIC I I ~

2. 2

~

~

,, . r I \ 10.8,2. 181 I

I ll I

' c I c c c ...

.. r"l*C C ape CJ I M CJ C CCC cc

' I I

2.0  ;

.... ~

i I

  • - :I ,.,

-- I I I I I

I I I

~

! i  !

I

I
~

--:.1. 8 Cl

~

! I

. a i  ! ' \

I  ! ' \

i I

~'

I I i I

I I  :

I 12, 1.5 I I  !

I i  !

1.4 i I I

!' I I i c I I I

! I ..

1.2 I

~

i i I I .1 I I I 2 4 6 8 10 12 CORE 1£ IGHT (FEET)

FICUU 1 MAXIMUM (FQT

  • Pael J VERSUS AXIAL CORE HEIGHT DURING NORMAL OPERATION 3 of 3