ML20058H307: Difference between revisions
StriderTol (talk | contribs) (StriderTol Bot insert) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 2: | Line 2: | ||
| number = ML20058H307 | | number = ML20058H307 | ||
| issue date = 11/30/1990 | | issue date = 11/30/1990 | ||
| title = Rev 1 to Brunswick Unit 2,Cycle 9 Core Operating Limits Rept | | title = Rev 1 to Brunswick Unit 2,Cycle 9 Core Operating Limits Rept | ||
| author name = Devoe M, Westmoreland G | | author name = Devoe M, Westmoreland G | ||
| author affiliation = CAROLINA POWER & LIGHT CO. | | author affiliation = CAROLINA POWER & LIGHT CO. | ||
Latest revision as of 23:56, 6 January 2021
| ML20058H307 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/30/1990 |
| From: | Devoe M, Westmoreland G CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20058H306 | List: |
| References | |
| NUDOCS 9011150168 | |
| Download: ML20058H307 (16) | |
Text
{{#Wiki_filter:, m r
. . , . . _ _ , _ _.- _. ~...,_. n.-
~+ ,
y-y.- ... - . . r w4
,3 .f ,s. ,
.s% .- ._. , .s ..a r', . r~ m. .t m.. - -
s.. m
- m. :. + , s
, 1 , i sr 3 , s a' .
s
.i , m .
* -- t , r YyC i 1' [ W- !.
r
+ - a: JMqU 3
p.- - ; P.F - g -
#, s m - m.> .
V. o
,.,. ,- f. -
. .. y.
(. s <
- a- , ;
<7m n <
g ': :, ! s: . A , t. , L'- -
. s . a . .
, ; _') .; .?',. ',,. ? . { h,
.. 4: .g r 4 ,g,. ,
.'J3. t m ,,
a
, v : - ,
- 3. w _-
,ao. -
r s _ - m> ,
# - n- -
m , , o.
# 1 r
.g .
,41m w -
ro A L f 9 f 4)l $.
~
11 t . . -; d l' q } ENC 148URE l' n X s ,
, x 4 ' t t
,5 .'. < ,
. m o J
(i [. # h s 3- ,s , ,, , . ,; ,
. ,: . . . . . . , s . .n .
, < t + .n A
CORE OPERATING LIMITS REPORTF REVIt10N 1D NOVEMBER 1990',
+, _.
p
- BRUNWICK STEAN= ELECTRIC PIANTJUNIT 20 i e -
6 , ; ( J5f g ' L ( f
/ : c -I }. n- '"*"
s , r t ( . i, s' 4 r.',. 5
p
,pf$f
,g< i , f" ,.,,;i -j i .
i
=,g j ,
g p
.p i 1
,,,'A ,.ty, ;
.g
' f. - , i t
, 4 1
1 y r -- ( j t
*',E,. y , E -_ 4
! n 1,
+
'(
.t
..- L
.'4,.
p t ,I f IU 't- 1
.[ t g
, s 3
s.,3, .f.[1' , , g[0 -t l'
, l
( '4 l g
. }' .-.,~
4 I ( l .l t 1 f,[_,,.* Ie g i, i Q- , ,
.t "I' I O -
f '-b) 4 t :. A , s ' 4 I 4 f 1
+
n+ I I _,_,k_-
)_
yfl-[ t f [
' _f h s g -?
,s' ,s :p o _. (V n
, a y
;. h,;
4' -
, s
. dq' .u.. ,
,e N Y 1 ( .) , ;$ - p"N.
I .i T- i f g ".
.I
,. 1 s..h ,l l Y- ,
t
?,-
1 -( 'II' g
- g j T i Y I 4 . k. ,_ ( ,
4 _, i;
..>r_
.g4.
,i, e
t T l g e,. r, h-" [ uw g,-'
"l
- [ 1 a i ,j , :1,.. 1 m
* i' -
, . - Y}
; . - ->'r f .q };o
.4,, <
, + g:_ wr,--, V s. l
~ ;;.:, .. . yr i A
- b. [. ( , i p i'g t .
,43- -
, &'7 i 4 . .
,.f- ;V;
+ ;J' . ..>. . L-. - "
f.
; '.,J ,C ,.. ' " ' mN :.-}.t,... v
' + s I <
4 r 3
.y t
f l ke $. , g i' A 4 i 3 s
,. f. ~
g , + g' k d. l '. ir i
;g- ..-
=
g g t A
, .. 1
,,; V?
[ ,g, ; ' T V' 2 5- g h
< b *l:1 g -'J:, s a
X.
-e y gj ?
' 'g2 '
. , s L '.S i , .. ;
I
-* b E g .!
% ' / 1 >
h. y ._ p
- . , < .g-- .
'h {' .
h -. _, , t.m - - - 5
. j {
I y , m ,- - 1 , ; f J N s N I 5 I
- t ;
,f i _^y,'
ylp i 3' 4 A' g . 'h' /
.. 1
k-ft' i 4 4 .
y ,a % * ;- - \ I1 g ( l 3"q _3 L 1 e t t. q . t ,J
; ,7 q.
- A ^ *
.;s ..
4
; g' '.
b
't 3 :.k.+
(, l / /" g ;3N-3 [ t .e
. 1 l p k 2 ,7c.-
-{Li g
A... . ,
^
5 5 ,_ g 4 ( 7 p 4'-.J _f.....,. i [' g i t d i[' + g
? E ue ..
o . y .< i l
.( - -
,m g7- , 4 ,
-r-g.. t, _
3 i - u= , .q , - ,s t , s, l4,- N .;. 1 10 > 1 re , r , 5 cm
,,s_r n i s-yr #
g i
~w, l
t a - s'.y'.' , .,,, T f
; >, 1 \ x n' g i
k 2. __ , -11 j j 2 l p E. T 4 . p
',7J k'.,'4 3 .t 3
y y ~4 O';N4: $~g -- [!h.j 39,,
.{$9N we n
[ f *r ' -pp g 1 L ., , r
+g
' # 4 4
i II '~ r ) ' iU-; '- - % m m, y' ,',
-"m , ~ b' mJ n
w4,,e .
,1
, 1 v
m my +b, ;1 c.x i t, ,- '. i a 3 a
,7 'u &ve' y . ,.A,
,y . .
.t' 3
.J '
m, m. <t d'..,
, ;r s r '. *, ;6 : < -
an- .-L, e r ,i t-
<+
J r un,. .3
'l; .. ,
.L E U '. Q"W M+ (JY . ,
M , t i-i' -,i , 4 ., i %dc ;:E 4 %- . - 4 # '91 ei .t.. uia _.>lg n.i
,. g ,# i-,..
1, - I6o- i 'm.k,"'..g i.r ' I I s
~~g + .
.--v
('.. >
'[ -h 4 w, d, a
.,e.
{ -E i r k,._4-y ns 1, T ti
.-,2.';'y e.,
)'
- j.
- J
,j i [ g- g-n' q .,g,(. 4 , .
g
~ -- ,
. v . . - . v, u , ~ w . . ,
hhkkk h O. b
^
is h ' ib:
', , i E < >
- L< /;
' i 3 ADOCK 05000324' h f yf , w CP4%M3M_ g" n4 x,'y%gMg'
- PDR : ,
y%;]m p PDC m. r L yy@:@.= nr A .s 4,- e+ >e7t +4 , , hm .,+m m mgm , %; m m+. , % ag
+ ,
avwuw e,mm.t m w& , m.w"I wn _ e& Ly ,v 2; a 6h ippy i 3p i T
~.
Wg 3; n ;r J.Mfh& MQWyh , ( , g
-g i f iM
-r 4 gg7.. 4; -q'q;;. -
J Q gg t.i 1 V# aa
j CP&L Nuclear Fuel Section File: NF-2202.016 [ B2C9 Core Operating Limits Report Page 1, Revision I s t t e BRUNSWICK UNIT 2, CYCLE 9 CORE OPERATING LlhilTS REPORT NOVEhiBER 1990 , Controlled Copy Oi ' i
.i h
i l Revision 0 Prepared By: hi. J. DeVoe - Revision 1 Prepared By: G. R. Westmoreland ! l i
- Approved By
- }Y . . A Date 11 J 7 90 v
hi. J. DeVoe - Project Engineer . -l l Incore Analysis [ r P t
-i
+_
c
. j I
CP&L Nuclear Fuel Section File: NP-2202.016 ! B2C9 Core Operating Limits Report Page 2, Revision ! l i- ! I
'e l LIST OF EFFECTIVE PAGES 1
3 Pane (s) Revision .
'I 1 1..
2 l' ' l 3-14 0. l '15 1 .; l vi
~
SUMMARY
OF CHANGES if > Revision 0 (02/90) r l I Original preparation f Revision I (11/90) , Table 2 ; deleted S symbols from LPSP, IPSP, and HPSP Trip.Setpoints;
.[
i
)
i .* t , i i f
.L
CP&L Nuclear Fuel Section File: NF 2202.016 . B209 Core Operating Limits Report Page 3, Revision 0 ' I INTRODUCTION AND $1M1ARY This report provides the values of the power distribution 11 its and control rod I withdrawal block instrumentation setpoints for Brunswick Unit 2, Cycle 9 as required by Technical Specification 6.9.3.1. The values of the AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) limits, along with associated core flow-and core power adj us tment factors are provided as required by Technical Specification 6.9.3.1.a. The values of the MINIMUM CRITICAL POWER RATIO (MCPR) limits, along with associated core flow and -core power, adjustment factors are provided as required by Technical Specifications 6.9.3.1.b and 6.9.3.1.c. The , control rod block upscale trip setpoints and allowable values are provided'as [ required by Technical Specification 6.9.3.1.d. , Per Technical Specifications 6.9.3.2 and 6.9.3.3, these values have been determined using NRC approved methodology and are . established' such that .all applicable limits of the plant safety analysis are met, Preparation of this report was performed in accordance with CP6L Nuclear Fuel Section Quality Assurance requirements as is documented in Reference 1. t l APLHCR LIMITS l The limiting APLHGR value for the most limiting lattice (excluding natural uranium) of each fuel type as a function of planar average. exposure is given in Figures 1,2,3,4, and 5. These values were determined with the SAFER /GESTR LOCA methodology described in GESTAR II (Reference 2). Figures >1,2,3,4, and 5 are used when hand calculations are required as specified in Technical Specification 3.2.1. r The core flow and core power adjustment factors for use in Technical Specification 3.2.1 are presented in Figures 6 and 7. For any given flow / power state the minimum of MAPLHCR(F) determined from Figure' 6 and : MAPLHGR(P) < determined from Figure 7 is used to determine the governing limit. l l
,i P
.),.
t CP&L Nuclear Fuel Section File: NF-2202.016 B2C9 Core Operating Limits Report Page 4. Revision 0 MCPR LIMITS i The ODYN OPTION A. ODYN OPTION B, and non pressurization transient MCPR limits for use in Technical Specifications 3.2.2.1 and 3.2.2.2 for each. fuel type as a function of cycle average exposure are given in Table'1. These values were determined with the GEMINI methodology and GEXL.PLUS critical power ratio corre-lation described in GESTAR II (Reference 2) and are consistent with the Safety Limit MCPR of 1.06 specified by Technical Specification 2.1.2. The core flow and core power adjus tment factors 'for use in Technical Specification 3.2.2.1 are presented in Figures 8 and 9. For any given flow / power state the maximum of MCPR(F) determined from Figure 8 and MCPR(P) determined from Figure 9 is used to determine the governing limit. i ROD BLOCR INSTRUMENTATION SETPOINTS E The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation for use in Technical Specification 3.3.4 (Table-3.3.4 2)~ : are presented in Table 2. These values were determined consistent with the bases - l of the ARTS program and the determination of MCPR limits with the GEMINI , methodology and CEXL.PLUS critical power ratio correlation described in GESTAR.11 ' (Reference 2) . - i REFERENCE (s) ,
- 1) CP&L Nuclear Fuel Section Quality Assurance File NF 2490.0004, [
" Brunswick Unit 2, Cycle 9 Core Operating Limits Report",
February 1990.
- 2) NEDE 24011-P A, " General Electric Standard'. Application for Reactor Fuel * (latest approved version). .
t f i b b w r b a f
'. CP&L Nuclear Fuel Sectl:n File: NF-2202.016 f 82C9 Core Operating Umits Report Page 5, Revision 0 I
Figure 1 FUEL TYPE BP8DRB299- (BPBX8R) ; AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR) LIMIT : VERSUS AVERAGE PL(ANAR EXPOSURE l, 13 I i - THIS f1GURE IS REFERRED TC' BY TECHNICAL SPEi;lFICATIOh 3.2'.1 12,2 g sN 12,1 12-7 \ 11 ,5 l 11.C e [- PEFtMISSIBLE w i 6 10.g RE0lON OF g OPl: RATION j 10.a K ; 5 \ 7 i
\
9 , 9.0
.t 5
1 8 , , i , , , 3 0 5 10 15 20 25 30 35 40- 45 : AVERAGE PLANAR EXPOSURE (GWd/ST) l a
'h i
0 i .
.. i CPSL Nuclear Fuel Secti:n File: NF-2202.016 B2C9 Core Operating Umits Report Page 6. Revleion 0 Figure 2 {
FUEL TfPE BD317A (GEBX8EB) AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR LIMIT VERSUS AVERAGE PL(ANAR EX)POSURE 14 THIS FIGL RE SREFEFl RED TO BY TECH ilCA. SF'ECIFICAT ON 3.2. 1 j 13 % I
.1
/1 2.57 3.02
\\
12,65 ; 12.07 1 l.96 i
,/ 11.J0 N\
g 3.,32 i 33 11 23 h ' ( )
,x PERMISSIBLE RiGIOP OF 1C.67
- 10 O- t.MA 10N
( e \- .l l 10.0' g ..20x 5 e
\(
.. 37 y L
-j 6 . -i ,
' 5.91' 5 i '
l l~ 0 5 10 15 20 25 30 35 '40 ~45. 50 l AVERAGE PLANAR EXPOSURE -(GWd/ST)- 1 l k I
)
. CP.* L Nuclear Fuel Section File: NF-2202.016 B2C9 Core Operating Umits Report Page 7. Revision 0 l
l Figure 3 l FUEL TYPE BD323A (GE8X8EB) AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR) LIMIT ~ VERSUS AVERAGE PL(ANAR EXPOSURE ,
~
14 THS FIGLRE SREFEF! RED TO BY l 1 3.14 TECH ilCA. SF'ECIF ICAT ON 3.2. 1 g j% 13.05 i ri 12.79 ;t.72 12.62 12 12<41 h , i 33 f 33 11.38 \ ' PERWi!iSIBLE 10- RiGIOP OF t O"tMA 'lON 10.11 K ,
.[
3 e.3 i x ,- \, , s, vo \ , 7- \ 1 6- , t 6.02 i 5 , , , , 0 5 10 15- 20 25 30. 35 40' 45 50 AVF. RAGE PLANAR EXPOSURE (GWd/ST) . r- , f
. CP?L Nucirr Fudi Section File: ' NF-2202.016 B2C9 Core Operating Umits Report Pege 8. Revision 0 -<
l l l l Figure 4 - FUEL TYPE NBD329A (CE8X8NB AVERAGE PLANAR UNEAR HEAT ) , GENERATION RATE APLHGR LIMIT r VERSUS AVERAGE PL(ANAR EX)POSURE , 13 12.$6 l I 12*,'4 THIS FIGL RE S REFEF: RED TO BY l TECHNICA. SPECIFICAT ON 3.2. I 1 12- ' l \
'O
'I.63 1.4'5 jg / 14 4 ( 1 1.1lt (1 0.70 h \ 0.58 1 2 10-
~
)
x v PERWi$SIBl.E REGION OF OF'ERArlON
\- '
t- S .04 2 9 , J 5 , saa j 8 k 7- , i
.5.90 5.49 h-5 i , , , , , ,
0 5 10 .15 20 25 30- 35 -40 45 50 AVERAGE PLANAR EXPOSURE (GWd/ST) . 21 I i
)
l . CP7L Nuclyr fuel S:cti:n File: NF-2202.016 l B2C9 Core Operating Umits Report Page 9. Revision 0 i Figure 5 FUEL T(PE NBD330A (GEBX8NB AVERAGE PLANAR LINEAR HEAT ) i GENERATION RATE APLHGR)- LIMIT- > VERSUS AVERAGE PL(ANAR EXPOSURE i 13 - THIS FIGL RE SREFEF: RED TO BY 12,24 7ECH 4lCA. SF'ECIFICAT ON 3.2. I
-1 2.16 12 12.07/ \
1' .63 . 11.56 .
- 11. 40 11. 10
[ 10.77 10.60 \ 10.57 2 10 '
)
a PERMi!iStBLE REGION OF [ v ! t-0F'ERArl0N \ i 2 9_ \ - 8.9<5' t 3 m f% 8:
\ '
7.92 7-- -- i
\
6 5.91 I 5.40 , 5 , i ! O 5 10 15 20 -25 30 ~ 35 40: 45 50-AVERAGE PLANAR EXPOSURE (GWd/ST) h l-- s,-
W
- f 1
CP&L Nuclear Fuel Section File: NF 2202.016 ! B2C9 Core Operating Limits Report Page 10. Revision 0 ; Figure 6 ! I Flow - Dependent MAPUICR Limit, MAPulGR(F) ; i
~;
t 1.0 =
+ .
s0 4 >* p . g* - 0.9 - s O" ; a i I 8
=
t I k 0.8 - f 3 MAPLHOR(F)= MAPFACF
- MAPLHOR$TD MAPLHORSTD = 5TANDARD MAPLHOR LIMITS .
v f 0.7 MAPFACp(F)= MINIMUM (1.0. A F WC /100+ BFI ; f WC % RATED CORE FLOW f~ IU 0.6 MAxlMUM .! CORE FLOW . (% toteel As 87 '. 102.5 0.6784 0.4861 0'6 - 107.0 0.6750 0.4574 112.0 0.0007 0.4214 i 117.0 :0.6800 0.3528 I I I I I I I 0.4 t 30 40 SO 60 70 50 .90 100 110 l CORE FLOW t% rated) 1 l i This-figure is referred to by-
~ Technical Specification 3.2.1 :
1
+
b k
. - - - . . - . - - .- - -- . . - ~ . __.
.- i e
CP&L Nuclear Fuel Section File: NF 2202.016 I B2C9 Core Operating Limits Report Page 11. Revision 0 i Figure 7 Power Dependent MAPLHCR Limit, MAPLHCR(P) 9 1,0 1 0.9 - ? N e k ' 8 0.8 - G .
- 5 !
M APLHGRIP) e MAPFACp'MAPLHGRSTO ' g l $ 0.7 " s 50% CORE FLOW MAPLHGR$TO = STANDARD MAPLHOR LIMIT 5 $ 3 FOR 25% >P; NO THERMAL LIMITS MONITORING ! E REOUiRED
}
s 2 FOR 25% sP< 30%: 0.5 - 1 b MAPFACp = 0.585 + 0.005224 (P- 30%) k O FOR 550% CORE FLOW i W MAPFACp = 0,433 + 0.005224 (P- 30%) l > $0% CORE FLOW FOR > 50% CORE FLOW g 0.5 - l e , l e FOR 30% s P: , 1 MAPFACp. 1,0 + 0.005224 (P- 100%) 1 0.4 I I I I l I l 20 25 30 40 50 60 70 80 90 100 POWER 1% tetodi l r i This figure is referred to by Technical Specification 3.2.1 i s
. . . , ,. .~ , . - .
_ _ -______mm.m -
r b a p 9 h CP&L Nuclear Fuel Section File: NF 2202.016 i B2C9 Core Operating Limits Report Page 12, Revision 0 t i TABLE 1 e MCPR LIMITS ; i Non. Pressurization Transient MCPR - 1.19 (CE8X8NB, GE8X8EB, and BP8X8R fuel types) # Pressurization Transient MCPR t MCPR MCPR Option A Option B : Fuel Tvee Fuel Tyne . Exnosure Ranne CEBX8NB GE8X8EB BPBX8R GEBX8NB GE8X8EB AE8X1R BOC9 to EOC9-2000 MVD/ST 1.32 1.31 1.31 1.25 1.24 1.24 ; l EOC9-2000 MWD /ST to EOC9 1.33 l'.32 1.32 1.29. 1.28: 1.28 ' \ i l This table is referred to by . Technical Specifications ; 3.2.2,1 and 3.2.2.2 ' P r k I f
-[
t
., t
.. r
, CP&L Nuclear Fuel Section -File: NF.2202.016 i B2C9 Core Operating Limits Report Page 13 Revision 0 ,
P Figure 8 . l Flow Dependent MCPR Limit, MCPR(F) I l I FOR WC (% RATED CORE FLOW) < 40% FOR WC (% RATED CORE FLOW) a 40% j MCPRIF). MAX (1.20, A FWC/100 + SF)
=
MCPRtFl=IAFWC1100+8F)
,'7 . *l1 + 0.0032140-WC ll -
MAX FLOW AF BF ; I 117.0 -0.632 1.809' l 112.0 - 0.602 1.747 , l 1.6 - 107.0 - 0.586 1.697 102.5 - 0.571 1.656 l
~
1.6 - MAXIMUM FLOW RATE = 117.0% 112.0 % 107.0% 102.6% 1.4 -
}
't 1.3 -
i j 1.2 - l i I i,3 I I I I i 1 1 I I [ 20 30 40 60 60 70 to 90 100 110 120 CORE FLOW (% reteel t t t This figure is referred to.by-- , Technical Specification 3.2.2.1 _l 5 l l l r
< , v , , +, , , , - , - - . _ - - -
- - . .- -- - -- --- ~
= ,
I f r
. CP&L Nuclear Fuel Section File: NF-2202.016 [
B2C9 Core Operating Limits Report Page 14, Revision 0 Figure 9 f Power Dependent MCPR Limit,'MCPR(P) i RATED MCPR MQ.TIPLIER IKpl r
, 2.3 -
- OPERATING LIMlf MCPR y)= Kp' OPfRATING LIMIT MCPR 11001
" ! a 60% CORE FLOW
$22
~-
l FOR Pc 26%: NO THERMAL LIMITS MONITORING REOutRED
, l l NO LIMITS SPECIFIED 2.1 -
l l FOR 26% s P < PgypAgg: (PsypAgg. 30%) I i g l i y 2.0 - l KP " (K8YP + 0.02 (30% - Pil!OLMCPR 4100) I s 50% CORT rLOw 5 e g,y,, i., pon , gog oon, ptoy, I g 1.g - I = 2.2 FOR > 60% CORE FLOW , l I FOR 30% sPC46%t - g Kp m 1.28 + 0.0134 (4 6% - P) ai < 3 A 1.5 - FOR 46% sPc60%: , g L..
. l Kp = 1.15 + 0.00867 (60% - P) l .i l
- 1. 1.4 -
l l 16 FOR 60% s P; ; e l l 1.3 - l- KP= 1.0 + 0.00375 (100% -P) . l 1.2 - g
$ l l l 5 1.1 -
l l l ' S I i I I l I
]1.020 25 30 40
'I 50 - 60 --
l' 70 80 90 -100 PaypAgg . powgg q% ratee) . This figure is referred to by' Technical Specification 3.2.2.1~ , i: . J
~
1 j. i L i I.. . _ c , . . . _ . _ ..
o' , CP&L Nuclear Fuel Section File: NF-2202.016 1 B2C9 Core Operating Limits Report Page 15 Revision 1 i , e l l l TABLE 2 - ! RBM SYSTEM SETPOINTS ! i l Setoolnt Trio Setooint ' Allowable Value l l Low Power Setpoint (LPSP') 27.0 1 29.0 Intermediate Power Setpoint (IPSP') 62.0 1 64.0 High Power Setpoint (HPSP') 82.0 1 84.0 ' Low Trip Setpoint (LTSP') 1 115.1 1.115.5-Intermediate Trip Setpoint (ITSI*) 1 109.3 ' i 109.7 ! High Trip Setpoint (HTSP") 1 105.5' : 1 105.9' ; l l i to 12.0 seconds 12.0 seconds i f
- Setpoints in percent of Rated Thermal Power.
6 Setpoints relative to a full scale reading of 125. For example,1115.1 means 1115.1/125.0 of full scale.
't l
l l l l -l This table is referred to_by 1 -- Technical Specification j
~3.3.4 (Table 3.3.4 2) ,
-t I
f}}