ML19332C852: Difference between revisions
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{{#Wiki_filter:. , - _ _ _ - __ _ _ _ _ | {{#Wiki_filter:. , - _ _ _ - __ _ _ _ _ | ||
{- | {- | ||
,- 5 , ; ,, , | ,- 5 , ; ,, , | ||
1: | 1: | ||
;; .. | ;; .. | ||
b''. _ . | |||
- DEFINITIONS . | - DEFINITIONS . | ||
- SECTION | - SECTION | ||
| Line 31: | Line 28: | ||
PAGE L | PAGE L | ||
1.1 ACTI0N...................^...................................., | 1.1 ACTI0N...................^...................................., | ||
1-1 1.2 -AVERAGE PLANAR EXP0SURE........................................ 1-1 | 1-1 1.2 -AVERAGE PLANAR EXP0SURE........................................ 1-1 | ||
: 1. 3 | : 1. 3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE..................... 1-1 | ||
AVERAGE PLANAR LINEAR HEAT GENERATION RATE..................... 1-1 | |||
: 1. 4 CHANNEL CALIBRATION............................................ 1-1 | : 1. 4 CHANNEL CALIBRATION............................................ 1-1 | ||
: 1. 5 CHANNEL CHECK........................................,,......... 1-1 - | : 1. 5 CHANNEL CHECK........................................,,......... 1-1 - | ||
: 1. 6 CHANNEL FUNCTIONAL TEST........................................ 1-1 1.7 CORE ALTERATION................................................ 1-2 ' | : 1. 6 CHANNEL FUNCTIONAL TEST........................................ 1-1 1.7 CORE ALTERATION................................................ 1-2 ' | ||
K 1. 8 CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY................ 1-2 1.9' CDRE OPEPATING LIMITS REPORP (COLR). . . . . . . . . . . ~. . | K 1. 8 CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY................ 1-2 1.9' CDRE OPEPATING LIMITS REPORP (COLR). . . . . . . . . . . ~. . | ||
1.10 pf CRITICAL POWER RATI0............................. . . . . . . . . . . . . ;. . 1-2 | 1.10 pf CRITICAL POWER RATI0............................. . . . . . . . . . . . . ;. . 1-2 1 11 3.x,00SE EQUIVALENT I-131. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . | ||
1-2 1.12 p rf DRYWELL INTEGRITY.............................................. 1-2 1.13 3,M l-AVERAGE DISINTEGRATION ENERGY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1.14 J,.El EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME./........... 1-3 1.15 3 4 4 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE 1-3TINE...... | |||
1 11 3.x,00SE EQUIVALENT I-131. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . | |||
1-2 1.12 p rf DRYWELL | |||
INTEGRITY.............................................. 1-2 1.13 3,M l-AVERAGE DISINTEGRATION ENERGY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1.14 J,.El EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME./........... 1-3 1.15 3 4 4 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE 1-3TINE...... | |||
1.16 3,,3 FRACTION OF LIMITING POWER DENSITY............................. 1-3 1.17 g FRACTION OF RATED THERMAL P0WER................................ 1-3 1.18 g FREQUENCY N0TATION............................................. 1-4 1.19 J< d GASEQUS RADWASTE TREATMENT (OFFGAS) SYSTEM..................... 1-4 | 1.16 3,,3 FRACTION OF LIMITING POWER DENSITY............................. 1-3 1.17 g FRACTION OF RATED THERMAL P0WER................................ 1-3 1.18 g FREQUENCY N0TATION............................................. 1-4 1.19 J< d GASEQUS RADWASTE TREATMENT (OFFGAS) SYSTEM..................... 1-4 | ||
: 1. 2o ud IDENTIFIED tEAxAGE. . . . . . . . . . . . . . . . . . . . . . . . . . . . .1-4 ....... | : 1. 2o ud IDENTIFIED tEAxAGE. . . . . . . . . . . . . . . . . . . . . . . . . . . . .1-4 ....... | ||
1.21 3.e5 ISouTION SYSTEM RESPONSE TIME. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.22 J.af LIMITING CONTROL R' 00 PATTERN. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 | 1.21 3.e5 ISouTION SYSTEM RESPONSE TIME. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.22 J.af LIMITING CONTROL R' 00 PATTERN. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.23' ),,4 f LINEAR HEAT GENERATION RATE.................................... 1-4 1.24 | ||
/ LOGIC SYSTEM FUNCTIONAL TEST... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1-4 RIVER BEND - UNIT 1 i 8911290080 891117 , | |||
1.23' ),,4 f LINEAR HEAT GENERATION RATE.................................... 1-4 1.24 | |||
/ LOGIC SYSTEM FUNCTIONAL TEST... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1-4 | |||
RIVER BEND - UNIT 1 i 8911290080 891117 , | |||
PDR ADOCK 0500 | PDR ADOCK 0500 | ||
., P | ., P | ||
-, , - - ..n,, . - - . , , , - - . . - , w.,.,, w , - , . . , , , , ,, , , ,, , . . ,.._ ,.nn, --, , , . , - - , - - , , ---- ,, , - . . .. . - - , , , ,w,,,,, _ , - - ,-. | -, , - - ..n,, . - - . , , , - - . . - , w.,.,, w , - , . . , , , , ,, , , ,, , . . ,.._ ,.nn, --, , , . , - - , - - , , ---- ,, , - . . .. . - - , , , ,w,,,,, _ , - - ,-. | ||
u b .: :* ,. . | u b .: :* ,. . | ||
o ..- | o ..- | ||
p .: , | p .: , | ||
l' l- INDEX 1-l L DEFINITIONS l | l' l- INDEX 1-l L DEFINITIONS l | ||
SECTION | SECTION 1 | ||
DEFINITIONS (Continued) | |||
PAGE | PAGE | ||
. 1,25 ~ | . 1,25 ~ | ||
| Line 77: | Line 58: | ||
: 1. 3 > pdf'PRIMARYCONTAINMENTINTEGRITY-0PERATING...........'............. 1-6 | : 1. 3 > pdf'PRIMARYCONTAINMENTINTEGRITY-0PERATING...........'............. 1-6 | ||
* 1.34 poiPROCESSCONTROLPR0 GRAM.......................................... 1-6 1.35 3,M RATED THERMAL P0WER.............................................. 1-7 1.36 % REACTOR PRUTECTION SYSTEM RESPONSE TINE.......................... 1-7 1.37 % REPORTABLE EVENT............................................... . 1-7 1.38 3,,41R000ENSITY...................................................... 1-7 1.39 JAI SECONDARY CONTAINMENT INTEGRITY - FUEL BUILDING. . . . . . . . . . . . . .1-7 .... | * 1.34 poiPROCESSCONTROLPR0 GRAM.......................................... 1-6 1.35 3,M RATED THERMAL P0WER.............................................. 1-7 1.36 % REACTOR PRUTECTION SYSTEM RESPONSE TINE.......................... 1-7 1.37 % REPORTABLE EVENT............................................... . 1-7 1.38 3,,41R000ENSITY...................................................... 1-7 1.39 JAI SECONDARY CONTAINMENT INTEGRITY - FUEL BUILDING. . . . . . . . . . . . . .1-7 .... | ||
1.40 34sSECONDARYCONTAINMENTINTEGRITY-0PERATING...................... 1-7 1.41 .pc SNuT00wN mRGI N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-s 1.42 1 / SITE B00MDARY.................................................... 1-8 1.c p1 50 u 0 l n CAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 | 1.40 34sSECONDARYCONTAINMENTINTEGRITY-0PERATING...................... 1-7 1.41 .pc SNuT00wN mRGI N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-s 1.42 1 / SITE B00MDARY.................................................... 1-8 1.c p1 50 u 0 l n CAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 1.44 y 50uRCe CuECn..................................................... 1-e 1.45 p44 STAGGERED TEST BASI S. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1-9 1.46 }AS THERMA L P0WE R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1-9 1.47 TINE.............................. 1-9 | ||
1.44 y 50uRCe CuECn..................................................... 1-e 1.45 p44 STAGGERED TEST BASI S. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1-9 1.46 }AS THERMA L P0WE R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1-9 1.47 TINE.............................. 1-9 | |||
% TUR8INE BYPASS SYSTEM RESPONSE RIVER BEND - UNIT 1 11 | % TUR8INE BYPASS SYSTEM RESPONSE RIVER BEND - UNIT 1 11 | ||
. - - _ . - ~ - - - - _ - , . , , - . - .--,m ~. .,- . . ..__,,. - _ . _ - . _ _ _- . - . - _ . . . . , - , , . . - - , , _ , - . . , . - , . , _ , , - . - - , , , . - - , | . - - _ . - ~ - - - - _ - , . , , - . - .--,m ~. .,- . . ..__,,. - _ . _ - . _ _ _- . - . - _ . . . . , - , , . . - - , , _ , - . . , . - , . , _ , , - . - - , , , . - - , | ||
g x . , , . | |||
g | |||
x . , , . | |||
1 RECElv J | 1 RECElv J | ||
.- SEP 0 S 1988 INDEX SDC LIST OF FIGURES FIGURE TITLE PAGE 3.2.1-1 11 ti. - - Fi = = r iir ei ".;;."...r ^in Rate ( 094)..... ............ .............. 3 -2 | |||
.- SEP 0 S 1988 INDEX SDC | |||
LIST OF FIGURES | |||
FIGURE TITLE PAGE 3.2.1-1 11 ti. - - Fi = = r iir ei ".;;."...r ^in Rate ( 094)..... ............ .............. 3 -2 | |||
: 3. -2 eum Avera anar Linear t' Generation EDELE Tg te (BP85 )......... ................. ...... 3 -3 3.2.1- Maxi Average P1 Linear Heat tion (BP85R82 . . .............. ........... ...... 3/4 2-3.2.1-4 Maximum rage Planar Li Heat'Ge on Rat SRS278).... ............ ............. .. 3/4 2- | : 3. -2 eum Avera anar Linear t' Generation EDELE Tg te (BP85 )......... ................. ...... 3 -3 3.2.1- Maxi Average P1 Linear Heat tion (BP85R82 . . .............. ........... ...... 3/4 2-3.2.1-4 Maximum rage Planar Li Heat'Ge on Rat SRS278).... ............ ............. .. 3/4 2- | ||
.2.1 inum Avera anar Line at Generati Rate (BP 99)....... ............. .......... , 3/4 2-t | .2.1 inum Avera anar Line at Generati Rate (BP 99)....... ............. .......... , 3/4 2-t | ||
: 3) -6 Average ar Linear nerati ate (BP85RB . . ......... .......... .......... /4 2-3.2. - MCPR .............. .......... .......... ....' -9 c 2.0-2 p.............................................. 3/4 2-10 l | |||
: 3) -6 Average ar Linear nerati | |||
ate (BP85RB . . ......... .......... .......... /4 2-3.2. - MCPR .............. .......... .......... ....' -9 | |||
c 2.0-2 p.............................................. 3/4 2-10 l | |||
3.4.1.1-1 Thermal Power versus Core Flow..................... 3/4 4-3 l 3.4.6.1-1 Minimum Temperature Required Versus Reactor | 3.4.1.1-1 Thermal Power versus Core Flow..................... 3/4 4-3 l 3.4.6.1-1 Minimum Temperature Required Versus Reactor | ||
: Pressure........................................... 3/4 4-24 4.7.4-1 Sample Plan for Snubber Functional Test............ 3/4 7-15 8 3/4 2.3-1 Power Flow Operating Map..................,........ B 3/4 2-6 B 3/4 3-1 Reactor Vessel Water Leve1......................... B 3/4 3-8 8 3/4.4.6-1 Fast Neutron Fluence (E>l MeV) at 1/4 T as a l Function of Service L1fe........................... B 3/4 4-8 l | : Pressure........................................... 3/4 4-24 4.7.4-1 Sample Plan for Snubber Functional Test............ 3/4 7-15 8 3/4 2.3-1 Power Flow Operating Map..................,........ B 3/4 2-6 B 3/4 3-1 Reactor Vessel Water Leve1......................... B 3/4 3-8 8 3/4.4.6-1 Fast Neutron Fluence (E>l MeV) at 1/4 T as a l Function of Service L1fe........................... B 3/4 4-8 l | ||
5.1.1-1 Exclusion Ares..................................... 5-2 5.1.2-1 Low Population Zone................................ 5-3 5.1.3-1 Nap Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents....... 5-4 | 5.1.1-1 Exclusion Ares..................................... 5-2 5.1.2-1 Low Population Zone................................ 5-3 5.1.3-1 Nap Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents....... 5-4 RIVER BEND - UNIT 1 xxii Amendment No.13,27 | ||
RIVER BEND - UNIT 1 xxii Amendment No.13,27 | |||
,r--,-,ne vas,,,. n.-,w., ,.m. . , . , . , - n,__,ww..,,,,.,,, ,,,.,._,w._,..,_ , _ | ,r--,-,ne vas,,,. n.-,w., ,.m. . , . , . , - n,__,ww..,,,,.,,, ,,,.,._,w._,..,_ , _ | ||
- -w ng: - - - - - - - | - -w ng: - - - - - - - | ||
: .* g j OCI 201988 ') | : .* g j OCI 201988 ') | ||
'., ,k- DEFINITIONS SDC | '., ,k- DEFINITIONS SDC | ||
%e. ~ | %e. ~ | ||
| Line 126: | Line 82: | ||
e.8.- | e.8.- | ||
jpCORE-ALTERATION , | jpCORE-ALTERATION , | ||
4 C-O l | 4 C-O l | ||
@ j 5 t 1.7. CORE ALTERATION shall be the addition, removal, relocation or movement of I | @ j 5 t 1.7. CORE ALTERATION shall be the addition, removal, relocation or movement of I | ||
| Line 132: | Line 87: | ||
T $ r.;.3 press,ure-vesse,l with the vessel head removed and fuel in the vessel. Normal 8 j g ,y movement of the SRMs. IRMs, LPRMs, TIPS or special movable detectors is not ma . o considered a C0RE ALTERATION. Suspension of CORE' ALTERATIONS shall not pre- l u d | T $ r.;.3 press,ure-vesse,l with the vessel head removed and fuel in the vessel. Normal 8 j g ,y movement of the SRMs. IRMs, LPRMs, TIPS or special movable detectors is not ma . o considered a C0RE ALTERATION. Suspension of CORE' ALTERATIONS shall not pre- l u d | ||
* 1 clude completion auf the movement of a component to a safe conservative position. | * 1 clude completion auf the movement of a component to a safe conservative position. | ||
m en - m l 5-{. g CORE MAXINUN FRACTION OF LINITING POWER DENSITY-am.a gy9S 1.8 g The CORE MAXIMUM FRACTION OF LINITING POWER DENSITY (CMFLPD) shall be the s ow > highest value of the FLPD which exists in the core, l 8 .d % INSERT , | m en - m l 5-{. g CORE MAXINUN FRACTION OF LINITING POWER DENSITY-am.a gy9S 1.8 g The CORE MAXIMUM FRACTION OF LINITING POWER DENSITY (CMFLPD) shall be the s ow > highest value of the FLPD which exists in the core, l 8 .d % INSERT , | ||
,@ S 7,$ CRITICAL POWER RATIO ' | ,@ S 7,$ CRITICAL POWER RATIO ' | ||
Om | Om | ||
.S * $ 1. 9 The CRITICAL POWER RATIO (CPR) shall be the ratio of.that power in the | .S * $ 1. 9 The CRITICAL POWER RATIO (CPR) shall be the ratio of.that power in the | ||
.t ,S g ,o assembly.which is calculated by application of the GEXL correlatico to cause ou e some point in the assembly to experience boiling transition, divided by the 8.1 E E actual assembly operating power. | .t ,S g ,o assembly.which is calculated by application of the GEXL correlatico to cause ou e some point in the assembly to experience boiling transition, divided by the 8.1 E E actual assembly operating power. | ||
moo | moo y y;gg DOSE EQUIVALENT I-131 c.o o e - | ||
y y;gg DOSE EQUIVALENT I-131 c.o o e - | |||
A g d ,. 10 DOSE EQUIVALENT I-131 shall be that concentration of I-131, microcuries e wa s per gram, which alone would produce the same thyroid dose as the quantity and 5 -8 m isottvic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. | A g d ,. 10 DOSE EQUIVALENT I-131 shall be that concentration of I-131, microcuries e wa s per gram, which alone would produce the same thyroid dose as the quantity and 5 -8 m isottvic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. | ||
, o g.t The thyroid dose conversion factors used for this calculation shall be those ae si listed in Table III of TID-14844, " Calculation of Distance Factors for Power | , o g.t The thyroid dose conversion factors used for this calculation shall be those ae si listed in Table III of TID-14844, " Calculation of Distance Factors for Power | ||
,_,s5',*-landTestReactor51tes." | ,_,s5',*-landTestReactor51tes." | ||
o ,{ DRWELL INTEGRITY - ' | o ,{ DRWELL INTEGRITY - ' | ||
,4 o a | ,4 o a | ||
$ ggoce5 1.11 DRWELL INTEGRITY shall exist when: . | $ ggoce5 1.11 DRWELL INTEGRITY shall exist when: . | ||
| Line 163: | Line 112: | ||
8B8% | 8B8% | ||
l N$hIVERBEND-UNIT 1 1-2 Amendment No. 29 | l N$hIVERBEND-UNIT 1 1-2 Amendment No. 29 | ||
,_ , , , _ , , , . - . . , , , - - . , , , - . . - - - ~ , ~ . - - - - = - * = - = * - == ###" '*** * * * '' '^ * *' '##"''"'~ ' ~ | ,_ , , , _ , , , . - . . , , , - - . , , , - . . - - - ~ , ~ . - - - - = - * = - = * - == ###" '*** * * * '' '^ * *' '##"''"'~ ' ~ | ||
1' f-l [ | 1' f-l [ | ||
t | t | ||
,ii } ;! , { ,! | ,ii } ;! , { ,! | ||
s t e . | s t e . | ||
n | n | ||
-- o m O a v - | -- o m O a v - | ||
~ | ~ | ||
i . E w S' E' vo oo or br s R | i . E w S' E' vo oo or br s R | ||
. R , | . R , | ||
TR DR be a; : | TR DR be a; : | ||
i DE f EE az z | i DE f EE az z va EW in TO c ._w. RW A ETW g s il ~ | ||
va EW in TO c ._w. RW A ETW g s il ~ | |||
da AP - f 5_ | da AP - f 5_ | ||
O AO i st et d 1 fP RP s enhn e E 5s c R v - o 4 _ | O AO i st et d 1 fP RP s enhn e E 5s c R v - o 4 _ | ||
o phe ce s | o phe ce s | ||
+ cm nm o f4 L & | + cm nm o f4 L & | ||
LS 2 | LS 2 L fL SE i - i m W- .E4 1 oRI 7 nuiul 1l oIM v ir r c AU ML | ||
L fL SE i - i m W- .E4 1 oRI 7 nuiul 1l oIM v ir r c AU ML | |||
/l 2u 5E o , . | /l 2u 5E o , . | ||
: 8. W EWl 9 t 1t 0H r p | : 8. W EWl 9 t 1t 0H r p | ||
, 3 3E 0E 7 s .s OA 2f~ . 1H 2H 9 7. n 2 n % 2 LV 1 2T . a 0.- 1T 1T 1 8i 5i 1 L | , 3 3E 0E 7 s .s OA 2f~ . 1H 2H 9 7. n 2 n % 2 LV 1 2T . a 0.- 1T 1T 1 8i 5i 1 L | ||
A io f | A io f | ||
As* . | As* . | ||
A I | A I | ||
I i >- 1 i | I i >- 1 i R | ||
L S | |||
n' | |||
( | ( | ||
. T N | . T N | ||
| Line 219: | Line 146: | ||
,m | ,m | ||
/ | / | ||
i w D E | i w D E | ||
e* e vo oo v* | e* e vo oo v* | ||
| Line 231: | Line 157: | ||
N O c R d o o phe ce e O P T | N O c R d o o phe ce e O P T | ||
5s' L i . . | 5s' L i . . | ||
fL cm nm s I 2 f4t i u i oAt KM Ep T E 1l r x 7 nuiu o g | |||
fL cm nm s I 2 f4t i u i oAt KM Ep | |||
T E 1l r x 7 nuiu o g | |||
A S /l of l u g a . = 0 4 | A S /l of l u g a . = 0 4 | ||
ir t | ir t | ||
| Line 240: | Line 163: | ||
- T 0u %E p g m1 1E 1 8E l | - T 0u %E p g m1 1E 1 8E l | ||
6 s 0. st c N -P 2f 1 | 6 s 0. st c N -P 2f 1 | ||
5H | 5H 1 . | ||
1 . | |||
1H I 9 7. n 1 n E - | 1H I 9 7. n 1 n E - | ||
I R f 1T s a1T 0, 1T 1T 1 9i 5i 8 | I R f 1T s a1T 0, 1T 1T 1 9i 5i 8 | ||
. 1 M T 5o <- A < A 1 < <- | . 1 M T 5o <- A < A 1 < <- | ||
I | I | ||
- R I 5 >- 3 $ | - R I 5 >- 3 $ | ||
1 T ' | 1 T ' | ||
. S | . S 2 N I | ||
2 N I | |||
g s p , | g s p , | ||
f N | f N | ||
E E m L T 1 B S c' | E E m L T 1 B S c' A Y h h T S g g n w i i l o o N H H i l F | ||
A Y h h T S g g n w i i l o o N H H i l F | |||
O - - - t hg 3 e , | O - - - t hg 3 e , | ||
I x u r : a hg 8 r T | I x u r : a hg 8 r T | ||
| Line 264: | Line 180: | ||
a o e e r | a o e e r | ||
L o w , | L o w , | ||
R t | R t | ||
u n r ; L P o u s o w h | u n r ; L P o u s o w h e | ||
O e u e - | |||
s L g v T N o h : e i C : d T L r - H l | s L g v T N o h : e i C : d T L r - H l | ||
a A | a A | ||
| Line 276: | Line 190: | ||
e a. | e a. | ||
1 C | 1 C | ||
t a M1- P e e l l | t a M1- P e e l l e | ||
V n | |||
i t i n , | |||
t i n , | |||
t at s l | t at s l | ||
u : 9 m o e v v e | u : 9 m o e v v e | ||
o n o h l u; ge o c 1 i . | o n o h l u; ge o c 1 i . | ||
; dgh D L | ; dgh D L o M g r L t 1 M e g l a - | ||
o M g r L t 1 M e g l a - | |||
eM i | eM i | ||
t 1 | t 1 | ||
| Line 296: | Line 206: | ||
i o #. nl l uu eS v W t a W | i o #. nl l uu eS v W t a W | ||
a I / | a I / | ||
3 | 3 R | ||
R l r F s% | |||
a H | a H | ||
l e | l e | ||
g | g | ||
" iF s | " iF s | ||
i l l t e e l | i l l t e e l | ||
| Line 310: | Line 218: | ||
. ) ) o ) a r s s s e 1 s L T | . ) ) o ) a r s s s e 1 s L T | ||
t a w ro o 8 7 | t a w ro o 8 7 | ||
b a | b a | ||
) s s r I i P t w b cr t e e e pV V V e m a | ) s s r I i P t w b cr t e e e pV V V e m a | ||
| Line 317: | Line 223: | ||
N U | N U | ||
d e e e u o u o e i m gN l ) ) e n r r r t F L r a F 1 0 N I o o t t t o S s | d e e e u o u o e i m gN l ) ) e n r r r t F L r a F 1 0 N I o o t t t o S s | ||
e r | e r A c e a c N t e c n O n v a a i s I I A a b | ||
A c e a c N t e c n O n v a a i s I I A a | |||
b | |||
: p. . e e e a a T E fR R R M B C T . , e N . . | : p. . e e e a a T E fR R R M B C T . , e N . . | ||
E d e . . . . e U 1 2 3 4 5 6 S F t " | E d e . . . . e U 1 2 3 4 5 6 S F t " | ||
p e | p e | ||
3 < g am,o U~ | 3 < g am,o U~ | ||
mE | mE | ||
$oC<mc r | $oC<mc r | ||
;j4,[=>, g - - | ;j4,[=>, g - - | ||
8< $ 3e* 2 E | 8< $ 3e* 2 E | ||
) | ) | ||
f | f | ||
( OO | ( OO | ||
,- ,(.(li ! <i;!j l!l j!; ,!! :l,ll j; . :! | ,- ,(.(li ! <i;!j l!l j!; ,!! :l,ll j; . :! | ||
? . | ? . | ||
~'c.:' l | ~'c.:' l | ||
.. 3/4.2- POWER DISTRIBUTION LIMITS | .. 3/4.2- POWER DISTRIBUTION LIMITS | ||
) | ) | ||
$ 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.1 All AVERAGE PLANAR LINEAR HEAT GENERATION RATES-(APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits the- ia ci te :: 3. 2.1-1, 2. 2.1-2, 0. 2.1- 2, 3. 2.1-4, 0. 2.1- L , 3. 2.1- 0, 0. 2.1-7 The it:it; ef figure; .2.1-1, 0.2.1-2, 3.2.1-3, 3.2.1--4, N eM ? ?.1-9.* | $ 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.1 All AVERAGE PLANAR LINEAR HEAT GENERATION RATES-(APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits the- ia ci te :: 3. 2.1-1, 2. 2.1-2, 0. 2.1- 2, 3. 2.1-4, 0. 2.1- L , 3. 2.1- 0, 0. 2.1-7 The it:it; ef figure; .2.1-1, 0.2.1-2, 3.2.1-3, 3.2.1--4, N eM ? ?.1-9.* | ||
3.2.1-5, 3.2.1-0, 0.2.1 7 ..d 3.2.1-6 shall be reduced to a.value of 0.84 times the two recir era limit n n operation. shown in the . e LHiiits prcn,'i in the COIR APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER. | 3.2.1-5, 3.2.1-0, 0.2.1 7 ..d 3.2.1-6 shall be reduced to a.value of 0.84 times the two recir era limit n n operation. shown in the . e LHiiits prcn,'i in the COIR APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER. | ||
ACTIONI provided in the COLR. | ACTIONI provided in the COLR. | ||
With an APLHGR exceeding the limit ef T gere 0. .r l, 3.2.1-2, 3.2.1-3, 3.2.1-4,. 3.2.1-0, 3.2.1-6, 3.2.1-7 or 3.2.1-6, initiate corrective action l within 15 minutes and restore APLHGR to within the required limits within 2 hours or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within i the next 4 hours. | With an APLHGR exceeding the limit ef T gere 0. .r l, 3.2.1-2, 3.2.1-3, 3.2.1-4,. 3.2.1-0, 3.2.1-6, 3.2.1-7 or 3.2.1-6, initiate corrective action l within 15 minutes and restore APLHGR to within the required limits within 2 hours or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within i the next 4 hours. | ||
* 2 . | |||
2 . | |||
\ | \ | ||
l SURVEILLANCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal to or less than the limits determinedyg,Fip;; 2.2.1-1,0.2.1-2,0.2.1-0,0.2.14,0.2.1-5,0.2.1-0, | l SURVEILLANCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal to or less than the limits determinedyg,Fip;; 2.2.1-1,0.2.1-2,0.2.1-0,0.2.14,0.2.1-5,0.2.1-0, | ||
| Line 364: | Line 256: | ||
'T;,. 1 ;. ; i.. vi. F ;,. . 3. 2.1-7 .. 4 3. 2.1 0 .. . te :,e used saiy for r;r.;e1 calce!stiaas. | 'T;,. 1 ;. ; i.. vi. F ;,. . 3. 2.1-7 .. 4 3. 2.1 0 .. . te :,e used saiy for r;r.;e1 calce!stiaas. | ||
I RIVER BEND - UNIT 1 3/4 2-1 Amendment No. 22, 31, 33 I i | I RIVER BEND - UNIT 1 3/4 2-1 Amendment No. 22, 31, 33 I i | ||
l | l e ,.*-----,..r , , , , - - , , . , . . , , , , , , .,.,.....w.,. - | ||
e ,.*-----,..r , , , , - - , , . , . . , , , , , , .,.,.....w.,. - | |||
. ,, . . , - . - - - . - - . . -....~m,..~ .v.-.-, . ., ,..,-~w,--vr...., | . ,, . . , - . - - - . - - . . -....~m,..~ .v.-.-, . ., ,..,-~w,--vr...., | ||
. U. . -v. | . U. . -v. | ||
, mma | , mma | ||
.; | .; | ||
4- It p #b g g | |||
4- It p #b g | |||
g | |||
11 II %g k / | 11 II %g k / | ||
/ | / | ||
\ L | \ L | ||
/ - - | / - - | ||
)k / | )k / | ||
I10 | I10 N - | ||
N - | |||
/ | / | ||
N | N | ||
| Line 401: | Line 274: | ||
N k | N k | ||
\ | \ | ||
N > L | N > L Il N / % | ||
Il N / % | |||
\ / k ' | \ / k ' | ||
k i e I | k i e I | ||
\ / | \ / | ||
\ / | \ / | ||
s | s | ||
\ / 4 | \ / 4 s . | ||
s | |||
\ j | \ j | ||
\ ! | \ ! | ||
/ : | / : | ||
/ \ ' | / \ ' | ||
7 mmmmmmmmmme nummmh summmmmmmmmmmmmmmmum O 10 30 30 46 50 AV AGE PLANAR EXP URE (GWd/t) | 7 mmmmmmmmmme nummmh summmmmmmmmmmmmmmmum O 10 30 30 46 50 AV AGE PLANAR EXP URE (GWd/t) | ||
FIGURE 3.2.1 1 . | FIGURE 3.2.1 1 . | ||
MAXIMUM AV AGE PLANAR LINEAR HEAT GENERATION RAT MAPLNGR) | MAXIMUM AV AGE PLANAR LINEAR HEAT GENERATION RAT MAPLNGR) | ||
. VERSUS AVERAGE PLANAR EXPOSURE BP85RB094 l | . VERSUS AVERAGE PLANAR EXPOSURE BP85RB094 l I | ||
7 river SEND - UNIT 1 3/4 2-2 Amendment No.12 i | |||
river SEND - UNIT 1 3/4 2-2 Amendment No.12 i | |||
. . .a , , . | . . .a , , . | ||
= am .s om m e i | = am .s om m e i | ||
| Line 444: | Line 296: | ||
.,~.....-..,,,.,,..,...,..-..,....~....-.~.---.--...----,-,.----,.,.-----..e - - ~ . . . . - - . . - - - - - - . - , - . | .,~.....-..,,,.,,..,...,..-..,....~....-.~.---.--...----,-,.----,.,.-----..e - - ~ . . . . - - . . - - - - - - . - , - . | ||
^ | ^ | ||
4 r-g , | 4 r-g , | ||
RECElVED : | RECElVED : | ||
nasam m cota i 0CT'2 91987-1 sac 1 13 | nasam m cota i 0CT'2 91987-1 sac 1 13 | ||
,,asumma g i | ,,asumma g i I -# / | ||
I -# / | |||
Y- 12 3 | Y- 12 3 | ||
/ %L / | / %L / | ||
/ | / | ||
1 / | 1 / | ||
3 | 3 | ||
| Line 467: | Line 309: | ||
. $N \ k / | . $N \ k / | ||
/ | / | ||
ji N % | ji N % | ||
k ! | k ! | ||
| Line 483: | Line 324: | ||
. 52 . \ / | . 52 . \ / | ||
g | g | ||
\ / | \ / | ||
3 '3 E / 4 - | 3 '3 E / 4 - | ||
w \ | w \ | ||
/ | / | ||
, $ 9 % | , $ 9 % | ||
/\ | /\ | ||
/ \ | / \ | ||
/ \ | / \ | ||
/ \ | / \ | ||
8- ,,,,,,,,, g,,,,,,,,,\, | 8- ,,,,,,,,, g,,,,,,,,,\, | ||
/ | / | ||
| Line 503: | Line 338: | ||
0 10 20 30 40 50 ERAGE PLANAR EXPOSUR GWd/t) | 0 10 20 30 40 50 ERAGE PLANAR EXPOSUR GWd/t) | ||
; | ; | ||
h | h FIGU RE,3.2.1 2 MAXIMU AVERAGE PLANAR LINEAR HEAT GENERATION RATE (M LHGR) l VERSUS AVERAGE PLANAR EXPOSURE BPBSRB163 RIVER BEND - UNIT 1 3/4 2-3 Amendment No. 12 | ||
FIGU RE,3.2.1 2 MAXIMU AVERAGE PLANAR LINEAR HEAT GENERATION RATE (M LHGR) l VERSUS AVERAGE PLANAR EXPOSURE BPBSRB163 | |||
RIVER BEND - UNIT 1 3/4 2-3 Amendment No. 12 | |||
~ | ~ | ||
-4 | -4 | ||
, -w,- - - - , , - - . , . - , . , . . . , - as,.x., ,,,,,~_,.,,,,.w.,-- - - , , ,,,,,---..--,--,-.---,,,,..-------.n.,. | , -w,- - - - , , - - . , . - , . , . . . , - as,.x., ,,,,,~_,.,,,,.w.,-- - - , , ,,,,,---..--,--,-.---,,,,..-------.n.,. | ||
,g, | ,g, j "..; zJ , x , | ||
j "..; zJ , x , | |||
; | ; | ||
, . . , .;, -. | , . . , .;, -. | ||
- TRANSFER 20 COLR' .j i | - TRANSFER 20 COLR' .j i | ||
h' J | h' J 13_ | ||
13_ | |||
/ | / | ||
/ | / | ||
~/ | ~/ | ||
/ | / | ||
l pp k l ' | |||
l pp | |||
k l ' | |||
t 12 ' / l 3: % | t 12 ' / l 3: % | ||
mE % | mE % | ||
| Line 542: | Line 358: | ||
l 4W E b- % | l 4W E b- % | ||
3& \ | 3& \ | ||
k / | k / | ||
/ i "E 11 J | / i "E 11 J | ||
$9 % h %/ / | $9 % h %/ / | ||
<g \ | <g \ | ||
| Line 554: | Line 368: | ||
\ / % | \ / % | ||
l | l | ||
\ k | \ k lC 10 \ | ||
lC 10 \ | |||
\ / | \ / | ||
a3 m* | a3 m* | ||
\ | \ | ||
\ / | \ / | ||
/ g | / g | ||
\ / % | \ / % | ||
-a .- | -a .- | ||
a 3. $ s / . | a 3. $ s / . | ||
g W | g W | ||
\ / k E g | |||
\ / k | /g d . | ||
E g | |||
/g | |||
d . | |||
p | p | ||
\ | \ | ||
| Line 593: | Line 392: | ||
[ | [ | ||
h | h | ||
.I FIGURE 3.2.1 3 L . | |||
.I | |||
FIGURE 3.2.1 3 L . | |||
APLHGR) | APLHGR) | ||
" IMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE | " IMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE VERSUS AVERAGE PLANAR EXPOSURE BP8 SRB 248 l l | ||
VERSUS AVERAGE PLANAR EXPOSURE BP8 SRB 248 l l | |||
l-3/4 2-4 Amendment No.12 RIVER BEND - UNIT 1 | l-3/4 2-4 Amendment No.12 RIVER BEND - UNIT 1 | ||
,,.,m_,.,,y.,,,,,,,,._,,.,.,.,.y.,y,. . . - , , , , , . , . , . , ,,.._,p.,g.., | ,,.,m_,.,,y.,,,,,,,,._,,.,.,.,.y.,y,. . . - , , , , , . , . , . , ,,.._,p.,g.., | ||
RECEIVED | RECEIVED | ||
:. ' - .m . | :. ' - .m . | ||
t'- | t'- | ||
' OCT 291987 ; | ' OCT 291987 ; | ||
9sm m mm auw l 13 .. | 9sm m mm auw l 13 .. | ||
/ t 4 | / t 4 | ||
f~ "mm, , | f~ "mm, , | ||
| Line 625: | Line 411: | ||
/ ! | / ! | ||
[- | [- | ||
'%' j | '%' j | ||
/ | / | ||
| Line 631: | Line 416: | ||
/ | / | ||
t %s / | t %s / | ||
k g j | k g j | ||
/ | / | ||
/ | / | ||
h N % | h N % | ||
l ' | l ' | ||
| Line 644: | Line 424: | ||
N / | N / | ||
g % | g % | ||
k | k | ||
\ / g g s 4Y a e | \ / g g s 4Y a e l % | ||
l % | |||
4 , | 4 , | ||
>,N . | >,N . | ||
/ | / | ||
j . .. , s | j . .. , s | ||
/ | / | ||
I \ | I \ | ||
| Line 673: | Line 447: | ||
\ | \ | ||
/ | / | ||
\ | \ | ||
/ | / | ||
7 20 30 40 - 50 0 10 AVERAGE PLANAR EXPOSURE (GWd FIGURE 3.2.1_-4 MAXIMUM AVERAGE PLANAR UNEAR HEAT GENERATION RATE (MAPLHCR) VERSUS AVERAGE p | |||
7 20 30 40 - 50 0 10 AVERAGE PLANAR EXPOSURE (GWd | |||
FIGURE 3.2.1_-4 | |||
MAXIMUM AVERAGE PLANAR UNEAR HEAT GENERATION RATE (MAPLHCR) VERSUS AVERAGE p | |||
PLANAR EXPOSURE - BP85R8278 Amendment No. 12 | PLANAR EXPOSURE - BP85R8278 Amendment No. 12 | ||
. RIVER BEND - UNIT 1 3/42-5 9 | . RIVER BEND - UNIT 1 3/42-5 9 | ||
--,,,,,..-,,,,,m. _.-,,-y | --,,,,,..-,,,,,m. _.-,,-y | ||
:ll.- . | :ll.- . | ||
.: :.; mg y . | .: :.; mg y . | ||
34 .- | 34 .- | ||
l l | l l | ||
13 t i | 13 t i | ||
7 . | 7 . | ||
/ | / | ||
* \ , | * \ , | ||
/ | / | ||
12 m , | 12 m , | ||
/ | / | ||
p n"~ %g / | p n"~ %g / | ||
/ | / | ||
> ; | > ; | ||
^- $j# %q , | ^- $j# %q , | ||
9 4g / | 9 4g / | ||
/ | / | ||
| Line 723: | Line 477: | ||
8 - | 8 - | ||
s s / | s s / | ||
/ h | / h s - | ||
s - | |||
\ / | \ / | ||
s | s i l I10 | ||
/ g s | |||
N / | |||
i l I10 | |||
/ g | |||
\ / | \ / | ||
L | L | ||
/ | / | ||
k- \ . | k- \ . | ||
m .g s | m .g s g( | ||
g( | |||
3 9 \ j | 3 9 \ j | ||
/ | / | ||
)( s . | )( s . | ||
/ % 1 | / % 1 | ||
/ % | / % | ||
/ % | / % | ||
/ \ | / \ | ||
g ' | g ' | ||
/ % | / % | ||
/ % . | / % . | ||
/ | / | ||
/ | / | ||
/ | / | ||
" 7 , | " 7 , | ||
30 40 50 10 20 ., | 30 40 50 10 20 ., | ||
; | ; | ||
i | i AVERAGE PLANAR EXPOSURE (GWd l | ||
L l | |||
l-FIGURE 3.2.1-5 MAXIMUM AVERAGE PLANAR UNEAR HEAT CENERATION RATE (MAPLHGR) VERSUS AWRAGE PLANAR EXPOSURE - SPSSR8299 _ | |||
L | |||
FIGURE 3.2.1-5 MAXIMUM AVERAGE PLANAR UNEAR HEAT CENERATION RATE (MAPLHGR) VERSUS AWRAGE PLANAR EXPOSURE - SPSSR8299 _ | |||
12 RIVER BEND - UNIT 1 3/42-8 Amendment No. | 12 RIVER BEND - UNIT 1 3/42-8 Amendment No. | ||
1 | 1 | ||
- ,.-vm---v.,,--,--.....-,w.---,.-ww.w.- | - ,.-vm---v.,,--,--.....-,w.---,.-ww.w.- | ||
is > | is > | ||
l _., | l _., | ||
.z,_., QECEIVED gmma 1 | .z,_., QECEIVED gmma 1 | ||
7 ; | 7 ; | ||
E | E soc 33 | ||
soc 33 | |||
/ 3 | / 3 | ||
,....---- g ' | ,....---- g ' | ||
~ | ~ | ||
f, % | f, % | ||
/ | / | ||
J | J | ||
/ | / | ||
g J | g J | ||
kw l 12- p | kw l 12- p g | ||
g | |||
/ | / | ||
/ | / | ||
| Line 812: | Line 531: | ||
i l p 4 / | i l p 4 / | ||
# / | # / | ||
f | f g | ||
l | |||
/ | / | ||
' %6 s | ' %6 s s | ||
11 ' | |||
s | s | ||
,/ | ,/ | ||
h % | h % | ||
i | i s % | ||
s % | |||
s / | s / | ||
/ | / | ||
| Line 834: | Line 545: | ||
1 | 1 | ||
\ / | \ / | ||
10 s / | |||
/ | / | ||
\ | \ | ||
| Line 850: | Line 560: | ||
# s | # s | ||
/ \ | / \ | ||
/ s s | |||
/ s | l / N l / % | ||
/ s | / s | ||
/ s , | / s , | ||
/ N i | / N i | ||
- 1 t as 4o so l so | - 1 t as 4o so l so o so AVDtAM PLANAR DPOSURE (GWd s | ||
o so AVDtAM PLANAR DPOSURE (GWd | |||
s | |||
^ | ^ | ||
F1 CURE 3.2.1-6 'c., | F1 CURE 3.2.1-6 'c., | ||
I MAXNUM AVULACE PLANAR UNEAR WAT OCNULA10N RATE (MAPLHOR) VUtSUS AvDtAIK PLANAR EXPOSyftg - SPSSRS308 -_ | I MAXNUM AVULACE PLANAR UNEAR WAT OCNULA10N RATE (MAPLHOR) VUtSUS AvDtAIK PLANAR EXPOSyftg - SPSSRS308 -_ | ||
l Amendment No.12 RIVER BEND - UNIT 1 3/4 2-SA | l Amendment No.12 RIVER BEND - UNIT 1 3/4 2-SA O | ||
c- .- ..-,---e,,,.,....-,,_..~.m.,. . . , . . _ . , . . , _ , , , . . . . . , . . - . _ . _ , - , _ . , . . . _ . . . . . . _ , - . . .... ...- . .m. ~ ... | |||
/.; * . gg; TRANSFER 'IO COLR , | |||
/.; * . gg; | |||
TRANSFER 'IO COLR | |||
, ,- e 4 | , ,- e 4 | ||
'- s#ggqh L - | '- s#ggqh L - | ||
, a , | , a , | ||
f i - | f i - | ||
f % | f % | ||
f | f Jlp % | ||
it f '% | |||
Jlp % | |||
it | |||
f '% | |||
%q% | %q% | ||
I | I | ||
% / | % / | ||
4 ' | 4 ' | ||
11 | 11 s ., % | ||
s ., % | |||
s ,- % | s ,- % | ||
s s | s s | ||
to s ., h | |||
,s , g s , g l \ - | |||
to | |||
s ., h | |||
,s , g | |||
s , g | |||
l \ - | |||
,',- N g | ,',- N g | ||
- "N \ | - "N \ | ||
s f } | |||
s | |||
s j e | s j e | ||
x; { l | x; { l | ||
* / | * / | ||
N 7 s j s | |||
N 7 s j | |||
s | |||
's | 's | ||
* \ . | * \ . | ||
| Line 975: | Line 601: | ||
, I t 0 10 20 30 40 80 CEtVED AvtRA(E'PLANMt DIPOSURE (GWd/t) ' | , I t 0 10 20 30 40 80 CEtVED AvtRA(E'PLANMt DIPOSURE (GWd/t) ' | ||
MAR t 41989 FIGURE 3.2.1-7 . | MAR t 41989 FIGURE 3.2.1-7 . | ||
I SOC MAXRAAd ANERACE PLANAR IJNEMt MAT (MNDIAll0N RAlt $dAPLMGI) NERSUS AVUtAGE Punan exPosuR - ssans RIVER BEND - UNIT 1 . | I SOC MAXRAAd ANERACE PLANAR IJNEMt MAT (MNDIAll0N RAlt $dAPLMGI) NERSUS AVUtAGE Punan exPosuR - ssans RIVER BEND - UNIT 1 . | ||
3/4 2-68 | 3/4 2-68 | ||
* Amendment No. 33 l | * Amendment No. 33 l | ||
( | ( | ||
___.__..,._,,,,,....,-,,,..c,...,_ -y,,.,__,. . . . , . . , , , , , , - , . . . . , . . . , . , - , | ___.__..,._,,,,,....,-,,,..c,...,_ -y,,.,__,. . . . , . . , , , , , , - , . . . . , . . . , . , - , | ||
. - R: .hsg g g m** | |||
. - R: .hsg g g | |||
m** | |||
/o | /o | ||
-33 | -33 | ||
=;% | =;% | ||
I N | I N r | ||
r | |||
/ % | / % | ||
k | k | ||
/ s | / s | ||
/ | / | ||
12-m- j f % | 12-m- j f % | ||
: f. 3,- s | : f. 3,- s | ||
'N | 'N | ||
; | ; | ||
s , | s , | ||
1 s % | 1 s % | ||
i | i N % . | ||
N % . | |||
i N '4 - | i N '4 - | ||
s ' % | s ' % | ||
s ' | s ' | ||
6 | 6 | ||
,o. < | ,o. < | ||
N i i | N i i | ||
N h - | N h - | ||
N g < | N g < | ||
N h | N h I, ' | ||
I, ' | |||
N N | N N | ||
%g s ,, | %g s ,, | ||
N N | |||
N | |||
N | |||
\ | \ | ||
N a , | |||
N | |||
a | |||
s s' | s s' | ||
N s | N s | ||
l | l | ||
| Line 1,061: | Line 644: | ||
; | ; | ||
\, | \, | ||
, s | , s 7- l | ||
7- l | |||
\ | \ | ||
I _ | I _ | ||
o to no ao 4o -so I | o to no ao 4o -so I | ||
RECEI ED 1 | RECEI ED 1 RGURE 3.2.1-8 . | ||
RGURE 3.2.1-8 . | |||
I NAR 4 1989 WA)0WUW AVERAW PLANAR UNEAR MAT . | I NAR 4 1989 WA)0WUW AVERAW PLANAR UNEAR MAT . | ||
SDC GENDIA10N RATE OdAPUM) VDtSJS AVUtAM l | SDC GENDIA10N RATE OdAPUM) VDtSJS AVUtAM l Puwwt ExP05UK - SS3220 i | ||
RIVER BEND - UNIT 1 3/4 2-6C Amendnent No. 33 G | |||
Puwwt ExP05UK - SS3220 i | |||
RIVER BEND - UNIT 1 3/4 2-6C Amendnent No. 33 | |||
G | |||
,---w.ee+g.--e w +.,e,.,.-.,,,~.,,,,...,,,-a-. ,,.-,--,,-...,,--,_,em..--.,.._.m.. _,e....m.--..r~m, . . - , . | ,---w.ee+g.--e w +.,e,.,.-.,,,~.,,,,...,,,-a-. ,,.-,--,,-...,,--,_,em..--.,.._.m.. _,e....m.--..r~m, . . - , . | ||
1,s 3 - | 1,s 3 - | ||
Qo t POWER' DISTRIBUTION' LIMITS hwm | |||
Qo t POWER' DISTRIBUTION' LIMITS | |||
hwm | |||
'3/4.2.2' APRM SETP0INTS 9 | '3/4.2.2' APRM SETP0INTS 9 | ||
5o LIMITING CON 0! TION FOR OPERATION L | 5o LIMITING CON 0! TION FOR OPERATION L | ||
.P 3.2.2. The APRM flow biased simulated thermal power-high scras trip setpoint - | .P 3.2.2. The APRM flow biased simulated thermal power-high scras trip setpoint - | ||
y1 (S) and flow biased neutron flux-upscale control rod block tri go i shall be established'according to fthe4 ollowing relationship /:p setpoint (SR $ | y1 (S) and flow biased neutron flux-upscale control rod block tri go i shall be established'according to fthe4 ollowing relationship /:p setpoint (SR $ | ||
e .% . u...s,.a._ . . . . . , | e .% . u...s,.a._ . . . . . , | ||
Oi ci i Allow alue | Oi ci i Allow alue | ||
{[ S 1 (O. + 485)T: _ (0.66W + )T | {[ S 1 (O. + 485)T: _ (0.66W + )T | ||
-S . (0.66W + )T | -S . (0.66W + )T SR8.1 (0 +45%)T | ||
: b. Si e Recircu ton Loop eration Tr Setpoint Allowable alue 1 (0.66W 42.7%)T S1 . 6W + 45. i S., 5 .66W + 36.75 T -- ' | |||
SR8.1 (0 +45%)T | |||
: b. Si e Recircu ton Loop eration | |||
Tr Setpoint Allowable alue 1 (0.66W 42.7%)T S1 . 6W + 45. i S., 5 .66W + 36.75 T -- ' | |||
_n. - (0.!!" 7 3a. '':)T | _n. - (0.!!" 7 3a. '':)T | ||
' S and SoI are-in percent of RATED THERMAL POWER, W = Loop recirculation flow as a percentage of the loop recirculation ' | ' S and SoI are-in percent of RATED THERMAL POWER, W = Loop recirculation flow as a percentage of the loop recirculation ' | ||
| Line 1,116: | Line 671: | ||
CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLPD). T is applied only if .less' than or equal to 1.0. | CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLPD). T is applied only if .less' than or equal to 1.0. | ||
APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to zu of RATED THERMAL POWER. | APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to zu of RATED THERMAL POWER. | ||
ACTION: | ACTION: | ||
With the APRM flow biased simulated thermal power-high seras trip setpoint and/or the flow biased neutron flux-upscale control rod block tri p setpoint less conser- l vative than the value shown in the Allowable Value column' Tor S or S gg, :: Ob: { | With the APRM flow biased simulated thermal power-high seras trip setpoint and/or the flow biased neutron flux-upscale control rod block tri p setpoint less conser- l vative than the value shown in the Allowable Value column' Tor S or S gg, :: Ob: { | ||
t' ='=d, initiate correctiv,e action within 15 minutes and adjust 5 and/or S gg | t' ='=d, initiate correctiv,e action within 15 minutes and adjust 5 and/or S gg to be consistant with the Trip Setpoint value | ||
* within 6 hours or reduce THERMAL POWER to less than 255 of RATED THERMAL POWER within the next 4 hours. l nWith CMFLPD greater than the FRTP, rather than adjusting the APRM.;setpoints, the APRM gain may be adjusted such that the APRM readings are greater than or equal to 1005 times CMFLPD, provided that the adjusted APRM reading does not exceed 100% of RATED THERMAL POWER, and a notice of the adjustment is posted on the reactor control panel. | |||
to be consistant with the Trip Setpoint value | |||
* within 6 hours or reduce THERMAL | |||
POWER to less than 255 of RATED THERMAL POWER within the next 4 hours. l | |||
nWith CMFLPD greater than the FRTP, rather than adjusting the APRM.;setpoints, the APRM gain may be adjusted such that the APRM readings are greater than or equal to 1005 times CMFLPD, provided that the adjusted APRM reading does not exceed 100% of RATED THERMAL POWER, and a notice of the adjustment is posted on the reactor control panel. | |||
RECEIVED RIVER BEND - UNIT 1 3/4 2-7 NOV 301988 AmendmentNo.y SDC | RECEIVED RIVER BEND - UNIT 1 3/4 2-7 NOV 301988 AmendmentNo.y SDC | ||
,; | ,; | ||
. .. . 3 | . .. . 3 | ||
.. . s .q. | .. . s .q. | ||
? POWER DISTRIBUTION' LIMITS =. ' | ? POWER DISTRIBUTION' LIMITS =. ' | ||
; | ; | ||
3/4.2.3 MINIMUM CRITICAL POWER RATIO-LIMITING CON 0! TION FOR OPERATION | 3/4.2.3 MINIMUM CRITICAL POWER RATIO-LIMITING CON 0! TION FOR OPERATION | ||
'3.2.3L The MINIMUM CRITICAL POWER RATIO (MCPR) shall be e than both MCPRf and MCPR limits at indicated core flow and TH | '3.2.3L The MINIMUM CRITICAL POWER RATIO (MCPR) shall be e than both MCPRf and MCPR limits at indicated core flow and TH | ||
:t:-. 1. T' s i.e 3.0.0 " .g .2.0 2. | :t:-. 1. T' s i.e 3.0.0 " .g .2.0 2. | ||
; | ; | ||
APPLICABILETY: | APPLICABILETY: | ||
equal to z!( of RATED THERMAL POWER. OPERATIONAL CONDITION 1, w ' | equal to z!( of RATED THERMAL POWER. OPERATIONAL CONDITION 1, w ' | ||
gt{g[:; | gt{g[:; | ||
. With MCPR less than the appitcable tiCPR Ifnit :h:x h T',...; :.". | . With MCPR less than the appitcable tiCPR Ifnit :h:x h T',...; :.". | ||
; ; | ; ; | ||
; .0.0 :, initiate corrective a: tion t:ithin 15 sitmtes and restore MCPR to | ; .0.0 :, initiate corrective a: tion t:ithin 15 sitmtes and restore MCPR to 255 of RATED THERMAL POWER within the next 4 hours.' t'wit 1 | ||
SURVEILLANCE REQUIREMENTS 4.2.3. | |||
255 of RATED THERMAL POWER within the next 4 hours.' t'wit | |||
1 | |||
SURVEILLANCE REQUIREMENTS | |||
4.2.3. | |||
a ..__,MCPR a ,_-- shall.,be ___ . determined | a ..__,MCPR a ,_-- shall.,be ___ . determined | ||
. . . __m to be. equal to or greater than the MCPR limit | . . . __m to be. equal to or greater than the MCPR limit | ||
..............~......-_.. | ..............~......-_.. | ||
provided in the CDIR. - | provided in the CDIR. - | ||
| Line 1,174: | Line 701: | ||
: b. W | : b. W | ||
. ithin 12 hours after completion of a TWERMAL POWER increase of at least 155'of RATED THERMAL POWER, and ' | . ithin 12 hours after completion of a TWERMAL POWER increase of at least 155'of RATED THERMAL POWER, and ' | ||
c. | c. | ||
Initially and at least once per 12 hours when the reactor is operating with a LIMITING Col (TROL R00 PATTERN for MCPR. | Initially and at least once per 12 hours when the reactor is operating with a LIMITING Col (TROL R00 PATTERN for MCPR. | ||
d. | d. | ||
The provisions of Specification 4.0.4 are not applicable. | The provisions of Specification 4.0.4 are not applicable. | ||
RIVER BEND - UNIT 1 3/4 2-8 | RIVER BEND - UNIT 1 3/4 2-8 e e +,w-- w-,,, ,,r.m., ,,....,n.--- . , , _ . . . . - . _ . . . ~ _ . - . . _ _ - ,,-.n | ||
e e +,w-- w-,,, ,,r.m., ,,....,n.--- . , , _ . . . . - . _ . . . ~ _ . - . . _ _ - ,,-.n | |||
: m. -_. .y _m_ 44._. ..,m ..._....._._..%.--um..,.._,.._.. ..m_._-_.m_ m... _ _ _ . . . _ . - _ - - - _ _ . . _ . _ - _ _ - _ __ _ | : m. -_. .y _m_ 44._. ..,m ..._....._._..%.--um..,.._,.._.. ..m_._-_.m_ m... _ _ _ . . . _ . - _ - - - _ _ . . _ . _ - _ _ - _ __ _ | ||
t | t | ||
{ | { | ||
.A | .A | ||
'IRANSPER '20 COLR . | 'IRANSPER '20 COLR . | ||
i | i | ||
. 1.7 | . 1.7 | ||
.+ - j | .+ - j | ||
** : +M* e we >w ; } | ** : +M* e we >w ; } | ||
m-. _ . | m-. _ . | ||
l | l M7 _ . , | ||
+ + | + + | ||
'I { | 'I { | ||
: w. I I | : w. I I 1 | ||
1 | |||
x a,. po g ,_cq | x a,. po g ,_cq | ||
** s - | ** s - | ||
, W:: wCPR,= d -0 6(Cr)+t7 pg , g 6 L - - | |||
, W:: wCPR,= d -0 6(Cr)+t7 pg , g | |||
6 L - - | |||
n ~* | n ~* | ||
.1 sr 7 - | .1 sr 7 - | ||
~ * | ~ * | ||
| Line 1,221: | Line 729: | ||
.X . | .X . | ||
E _ [ , | E _ [ , | ||
1: | 1: | ||
* l | * l | ||
| Line 1,227: | Line 734: | ||
J "g | J "g | ||
, DI I I I i R. , ~{ { | , DI I I I i R. , ~{ { | ||
T | T Y , | ||
Y , | |||
~ l 1 ' f f | ~ l 1 ' f f | ||
" ~ | " ~ | ||
a . . .1 . | a . . .1 . | ||
'L . | 'L . | ||
. i 1 . I i F: | . i 1 . I i F: | ||
| Line 1,240: | Line 743: | ||
I 1 I . ' i .L7 s | I 1 I . ' i .L7 s | ||
* 2 | * 2 | ||
;Y ; I I I I I I t i I :A ! | ;Y ; I I I I I I t i I :A ! | ||
+ | + | ||
b WCPR = -0,6(CT)+t7M e+- -i | b WCPR = -0,6(CT)+t7M e+- -i | ||
* T!. 1 I N1 | * T!. 1 I N1 | ||
. , 1: i . N' _I I T I I I I :M ' . 1 i | . , 1: i . N' _I I T I I I I :M ' . 1 i | ||
' I | ' I | ||
: 'l I E I I f 1 I T I 1,4 ' '. ' | : 'l I E I I f 1 I T I 1,4 ' '. ' | ||
i | i 1 | ||
I . 1 | |||
'E, i Ii i . ! . | 'E, i Ii i . ! . | ||
U. "' | U. "' | ||
' ! 1 | ' ! 1 1 I i r . g, ; 1 1 , , 1 1 1 1 i | ||
1 I i r . g, ; 1 1 , , 1 1 1 1 i | |||
. T . , , s! ' ' | . T . , , s! ' ' | ||
1 . . ; | 1 . . ; | ||
| Line 1,266: | Line 763: | ||
-0.761(CF') + 1 &3R : | -0.761(CF') + 1 &3R : | ||
.":. ! I | .":. ! I | ||
.7 . UN , | .7 . UN , | ||
L: I - I" 'L. I ' I ' i | L: I - I" 'L. I ' I ' i | ||
- : 1: . A .'E. I I . I I E, | - : 1: . A .'E. I I . I I E, r | ||
r | |||
IN I i , , i ! I T I- i 4 - - - . s . . . | IN I i , , i ! I T I- i 4 - - - . s . . . | ||
. F.. ..' 'M Y i , . . ! | . F.. ..' 'M Y i , . . ! | ||
I L i/ .1 W. i1 .1 I I I , | I L i/ .1 W. i1 .1 I I I , | ||
I II | I II | ||
| Line 1,281: | Line 773: | ||
- - ^ | - - ^ | ||
++;7 1 f f l | ++;7 1 f f l | ||
_.W" I - I r _- 1 | _.W" I - I r _- 1 L _ , | ||
L _ , | |||
w ' x t s e < | w ' x t s e < | ||
1.2 | 1.2 | ||
: s. . | : s. . | ||
I | I I ; rte n' ,i m | ||
I ; rte n' ,i m | |||
:g';,. | :g';,. | ||
! - , e, ! ! ! _J | ! - , e, ! ! ! _J | ||
% i ,..- o RA rau hiu m J | |||
Opgy ATBM! Ott i' , . - | |||
% i ,..- o | |||
RA rau hiu m | |||
i' , . - | |||
L | L | ||
-hr | -hr | ||
= | = | ||
-t4+ .... . m , , , | -t4+ .... . m , , , | ||
.r | .r | ||
; | ; | ||
.n , ,. .N.yu . | .n , ,. .N.yu . | ||
.e e ; | .e e ; | ||
n ,. 4v .y.. | n ,. 4v .y.. | ||
1.1 -- | 1.1 -- | ||
; - | ; - | ||
MS. - | MS. - | ||
| Line 1,339: | Line 797: | ||
i | i | ||
'l' 'f f | 'l' 'f f | ||
......; _ | ......; _ | ||
-e;_ a m m. | |||
-e;_ a m | |||
m. | |||
o l n' 11 .- | o l n' 11 .- | ||
t | t | ||
; | ; | ||
;._ ,, | ;._ ,, | ||
. a n , .' | . a n , .' | ||
: l. y4 J [ [ ' Cl a 3 1 x 4 ,,,[, + | : l. y4 J [ [ ' Cl a 3 1 x 4 ,,,[, + | ||
I . . , . | I . . , . | ||
1.0 L . 0 79 40 60 et 100 120 l | |||
1.0 | |||
L . 0 79 40 60 et 100 120 | |||
l | |||
: CORE FLOW, 5 OF RATED CORE FLOW i | : CORE FLOW, 5 OF RATED CORE FLOW i | ||
FIGURE 3.2.3-1 WCPR f | FIGURE 3.2.3-1 WCPR f | ||
RhUtBCNO - UMT1 3/42-9 Amendment No. 33 4 | |||
RhUtBCNO - UMT1 3/42-9 Amendment No. 33 | |||
4 | |||
-sn_,-. . _ - . , , _ . , - --,,,,a--.--,,---,,,-,....,,,,,,.-,---n...,,,n..w.,n, | -sn_,-. . _ - . , , _ . , - --,,,,a--.--,,---,,,-,....,,,,,,.-,---n...,,,n..w.,n, | ||
. _ _ , . .~,...._..mm.... . _ . _ . . . . _ . _ . . , _ _ - . . _ . _ , _ _ . . _______...~.~..m.. . - . . . ~ . _ . . _ _ _ . _ . . _ , . - . | . _ _ , . .~,...._..mm.... . _ . _ . . . . _ . _ . . , _ _ - . . _ . _ , _ _ . . _______...~.~..m.. . - . . . ~ . _ . . _ _ _ . _ . . _ , . - . | ||
r . | r . | ||
l | l | ||
| Line 1,394: | Line 821: | ||
r r ? +-+w e A | r r ? +-+w e A | ||
i 1.7 .-: | i 1.7 .-: | ||
" ; | " ; | ||
! k I f I | ! k I f I | ||
. 1 t . | . 1 t . | ||
T I i 1 7 I I 1 - | T I i 1 7 I I 1 - | ||
7 ' I I I . I Z I. v' l- 1 | 7 ' I I I . I Z I. v' l- 1 | ||
] 1 '" | ] 1 '" | ||
. ./.. | . ./.. | ||
' ' ' I _I I | ' ' ' I _I I | ||
1.s i | 1.s i | ||
y l 1 - I I | y l 1 - I I | ||
/ | / | ||
I i i . . . | I i i . . . | ||
| Line 1,422: | Line 838: | ||
L. | L. | ||
% I1, 1 i i 1 | % I1, 1 i i 1 | ||
1 | 1 | ||
: y. 2 I 1 . . . | : y. 2 I 1 . . . | ||
II, | II, I] .1 | ||
I] .1 | |||
:A | :A | ||
) | ) | ||
.s . 1 | .s . 1 | ||
' : I . | ' : I . | ||
R .~ . I %.. . | R .~ . I %.. . | ||
I . g_ | I . g_ | ||
I : I 1 . | I : I 1 . | ||
: 1 l T~ . i ! I T I I I i; ! | : 1 l T~ . i ! I T I I I i; ! | ||
: g. .T Y | : g. .T Y | ||
}) L. 1 t I I | }) L. 1 t I I | ||
:'s : . . | :'s : . . | ||
' W I | ' W I | ||
' / | ' / | ||
I 4, J N I. II . | I 4, J N I. II . | ||
^ | ^ | ||
^^ | ^^ | ||
. M ,r 1 | . M ,r 1 | ||
' 4 '. . I1' . | ' 4 '. . I1' . | ||
I . ''C N I i | I . ''C N I i | ||
/ I ! . | / I ! . | ||
II 7 .1 | II 7 .1 | ||
) | ) | ||
T I Ii L . I I | T I Ii L . I I | ||
'i I 7< T r I Ii : I II ' .I I1' ! | |||
'i I 7< T r I Ii : I | |||
II ' .I I1' ! | |||
. I | . I | ||
' j I I 'h . | ' j I I 'h . | ||
| Line 1,476: | Line 870: | ||
I I | I I | ||
' I I | ' I I | ||
: 1 : 11 .- '' | : 1 : 11 .- '' | ||
1.4 lL ,' , | 1.4 lL ,' , | ||
.+- , . | .+- , . | ||
! i T 1: | ! i T 1: | ||
i , | i , | ||
1 1 | 1 1 | ||
i | i | ||
.IN I ' | .IN I ' | ||
I I | I I | ||
. I'' i I # | . I'' i I # | ||
I I "^ ' ' | I I "^ ' ' | ||
"' ' M'' . 1 .. | "' ' M'' . 1 .. | ||
+ | + | ||
f. | f. | ||
Q I | Q I | ||
; 1 | ; 1 | ||
; | ; | ||
a+ | a+ | ||
! . T4 | ! . T4 i | ||
i | |||
4 . , . | 4 . , . | ||
, 7 r. . y2 . . | , 7 r. . y2 . . | ||
1 I I 6 1 .I | 1 I I 6 1 .I | ||
[ . | [ . | ||
I I T I | I I T I | ||
3 | 3 | ||
. I | . I | ||
,d gg I I T 1 I m. i 1 . | ,d gg I I T 1 I m. i 1 . | ||
I | |||
_y.' | _y.' | ||
7 1 | 7 1 | ||
.% I i | .% I i | ||
) I _. i 9 . I/ I i | ) I _. i 9 . I/ I i II I T IT 'k t | ||
II I T IT 'k t | |||
''! i | ''! i | ||
[ 1 - n T. 'I 4 ''. | [ 1 - n T. 'I 4 ''. | ||
1 L 'l . .i 1 g '' .I11! t 1 .. . | 1 L 'l . .i 1 g '' .I11! t 1 .. . | ||
iI7 I 'h | iI7 I 'h | ||
| Line 1,535: | Line 909: | ||
>I i '[ | >I i '[ | ||
I] | I] | ||
I I ' % | I I ' % | ||
\g , | \g , | ||
+- W' 4' t M .; , ? i M | +- W' 4' t M .; , ? i M 1 - | ||
1 - | |||
1 L.i , | 1 L.i , | ||
i | i | ||
= y i+ + +=< w e. 21 - ; ^ .- 4 I' .-> = | = y i+ + +=< w e. 21 - ; ^ .- 4 I' .-> = | ||
M a M,-,f f' 1 | M a M,-,f f' 1 | ||
&^ -y ' | &^ -y ' | ||
e 1 . | e 1 . | ||
; AL . | ; AL . | ||
i-.. I } | i-.. I } | ||
.{ | .{ | ||
*1 - ' - | *1 - ' - | ||
, : +.y p. e4vb4%. | , : +.y p. e4vb4%. | ||
* I | * I i +,.+- m ' # , -- -.. | ||
i +,.+- m ' # , -- -.. | |||
,-+- i' | ,-+- i' | ||
.z L'e . - 1 : = ', | .z L'e . - 1 : = ', | ||
I ' w ma ke* | I ' w ma ke* | ||
M &M l | M &M l | ||
\ 4upu' | \ 4upu' | ||
<= >p 1 a. | <= >p 1 a. | ||
- y f ., --+ | - y f ., --+ | ||
A nm.enw ,1 q: :'; | A nm.enw ,1 q: :'; | ||
..r,s | ..r,s n ,. | ||
n ,. | |||
-+ : ; 7, m | -+ : ; 7, m | ||
* Wu | * Wu | ||
= , | = , | ||
. 4. -w _J.,e - | . 4. -w _J.,e - | ||
.W | .W | ||
> ww 4 4. e r 3,y *-m: ,. ..L :: _ | |||
> ww 4 4. e r | |||
3,y *-m: ,. ..L :: _ | |||
7 p. ; | 7 p. ; | ||
.y . ~ ..--w % y; 3 , 3 e+ | .y . ~ ..--w % y; 3 , 3 e+ | ||
,r_- | ,r_- | ||
y e-v . | y e-v . | ||
-,v , '.hd 4 m e .- -q- woJ-r ,h p ionpa | -,v , '.hd 4 m e .- -q- woJ-r ,h p ionpa | ||
; , ' | ; , ' | ||
| Line 1,615: | Line 948: | ||
^; .9 9 - | ^; .9 9 - | ||
,,y4: . wPt ! | ,,y4: . wPt ! | ||
* P ~~-+= c | * P ~~-+= c i M"8 M M Y,+ ^ j t | ||
i M"8 M M Y,+ ^ j t | |||
i;>*("f e * *" Nyp = | i;>*("f e * *" Nyp = | ||
_y '" , | _y '" , | ||
;3 | ;3 | ||
.O, " i | .O, " i | ||
[ | [ | ||
t I_.Q 4,_L ' , , I ' i | t I_.Q 4,_L ' , , I ' i | ||
| Line 1,629: | Line 958: | ||
- -; | - -; | ||
___-{[ l -4% j; ;? j !' I t | ___-{[ l -4% j; ;? j !' I t | ||
- t ' ' ' | - t ' ' ' | ||
1.0 1M 0 at de 80 N 1m | 1.0 1M 0 at de 80 N 1m THERMAL POWER,# OF RATED THERMAL PO POURE S.R.8-8 4 | ||
RIVER 800 - Ull!T 1 3/4 2-10 i | |||
n | |||
THERMAL POWER,# OF RATED THERMAL PO | |||
POURE S.R.8-8 | |||
____-___-______.,,-__-.,,._.-__.-....-_--mm-m--~ - -, .- | ____-___-______.,,-__-.,,._.-__.-....-_--mm-m--~ - -, .- | ||
POWER O!STRIBUTION LIMITS RECElVED f.' | POWER O!STRIBUTION LIMITS RECElVED f.' | ||
iE | iE | ||
.3/4.2.4 LINEAR HEAT GENERATION RATE gg g 4 g 5, LIMITING CON 0! TION FOR OPERATION di | .3/4.2.4 LINEAR HEAT GENERATION RATE gg g 4 g 5, LIMITING CON 0! TION FOR OPERATION di | ||
**4 | **4 g 3.2.4 The LINEAR HEAT GENERATION RATE (LHGR) shall not excee _ ^ ' Er/f t fr | ||
g 3.2.4 The LINEAR HEAT GENERATION RATE (LHGR) shall not excee _ ^ ' Er/f t fr | |||
: a. O!!"!!:* f;;l ud 13.4 L/fi fei eil ett . f I. , | : a. O!!"!!:* f;;l ud 13.4 L/fi fei eil ett . f I. , | ||
APPLICA81LITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25E of RATED THERMAL POWER. | APPLICA81LITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25E of RATED THERMAL POWER. | ||
.f | .f i | ||
ACTION: | |||
{ l With the LHGR of any fuel rod exceeding the lieit, initiate corrective action , | { l With the LHGR of any fuel rod exceeding the lieit, initiate corrective action , | ||
within 15 einutes and restore the LHGR to within the limit within 2 hours or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours. | within 15 einutes and restore the LHGR to within the limit within 2 hours or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours. | ||
l | l SURVEILLANCE REQUIREMENTS 3 | ||
SURVEILLANCE REQUIREMENTS 3 | |||
4.2.4 LHGR's shall be determined to be equal to or less than the limit: i | 4.2.4 LHGR's shall be determined to be equal to or less than the limit: i | ||
: a. At least once per 24 hours, , | : a. At least once per 24 hours, , | ||
| Line 1,675: | Line 980: | ||
: c. Initially and at least once per 12 hours when the reactor is operating on a LIMITING CONTROL R00 PATTERN for LHGR. | : c. Initially and at least once per 12 hours when the reactor is operating on a LIMITING CONTROL R00 PATTERN for LHGR. | ||
, , l J | , , l J | ||
: d. The provisions of Specification 4.0.4 are not applicable. , | : d. The provisions of Specification 4.0.4 are not applicable. , | ||
.o . | .o . | ||
; | ; | ||
TCc m ^G;ese;; N i ;ml e ii r.. ;;;;;; e.-4 00:200. | TCc m ^G;ese;; N i ;ml e ii r.. ;;;;;; e.-4 00:200. | ||
RIVER BEND - UNIT 1 3/4 2-11 Amendment No. 33 | RIVER BEND - UNIT 1 3/4 2-11 Amendment No. 33 0 | ||
0 | |||
, . . _ - - . - , . . _ . _ . _ . . . - - - . . . . . . _ . _ . . . - , . . ..__ .- . _ . _ . . . . _ . . _ . - . _ . . - . . . ~ , . , . . . ~ - . - - , . , . - - | , . . _ - - . - , . . _ . _ . _ . . . - - - . . . . . . _ . _ . . . - , . . ..__ .- . _ . _ . . . . _ . . _ . - . _ . . - . . . ~ , . , . . . ~ - . - - , . , . - - | ||
.c # | .c # | ||
a TABLE 3.3.1 ' | |||
REACTOR PROTECTIL-M SYSTEM RESPONSE TIMES E RESPONSE TIME 7 FUNCTIONAL UNIT (Seconds) | |||
TABLE 3.3.1 ' | |||
REACTOR PROTECTIL-M SYSTEM RESPONSE TIMES | |||
E RESPONSE TIME 7 FUNCTIONAL UNIT (Seconds) | |||
E 1. Intermediate Range Monftors. | E 1. Intermediate Range Monftors. | ||
-e a. Neutron Flux - High ' | -e a. Neutron Flux - High ' | ||
NA 4 | NA 4 | ||
9 b. Inoperative NA | 9 b. Inoperative NA | ||
: 2. Average Power Range k nitor*: | : 2. Average Power Range k nitor*: | ||
: a. Neutron Flux - High, Setdown MA | : a. Neutron Flux - High, Setdown MA | ||
| Line 1,711: | Line 999: | ||
: c. Neutron Flux - High <0.09 | : c. Neutron Flux - High <0.09 | ||
: d. Inoperative NA i 3. Reactor Vessel Steam Ocme Pressurc - High <0.35 i R | : d. Inoperative NA i 3. Reactor Vessel Steam Ocme Pressurc - High <0.35 i R | ||
: 4. Reactor Vessel Water level - Low Level 3 71.05 i | : 4. Reactor Vessel Water level - Low Level 3 71.05 i | ||
: 5. Reactor Vessel Water Lesel - High, Leve? 8 71.05 i T | : 5. Reactor Vessel Water Lesel - High, Leve? 8 71.05 i T | ||
: 6. Main Steam Line Isniation Valve - C %sure 70.09 l 7. Main Steam Line Radiation - High NA | : 6. Main Steam Line Isniation Valve - C %sure 70.09 l 7. Main Steam Line Radiation - High NA | ||
: 8. Drywell Pressure - High NA | : 8. Drywell Pressure - High NA | ||
: 9. Scram Discharge Volume Water Level - High l a. Level Transmitter NA ' | : 9. Scram Discharge Volume Water Level - High l a. Level Transmitter NA ' | ||
| Line 1,722: | Line 1,007: | ||
: 10. Turbine Stop Valve - Closure -<0.06 l 11. Turbine Control Valve Fast Closure, W1ve Trip System | : 10. Turbine Stop Valve - Closure -<0.06 l 11. Turbine Control Valve Fast Closure, W1ve Trip System | ||
! Oil Pressure - Low <0. 0M i 12. Reactor hde Switch Shutdown Position NA i | ! Oil Pressure - Low <0. 0M i 12. Reactor hde Switch Shutdown Position NA i | ||
: 13. Manual Scram NA | : 13. Manual Scram NA I | ||
I | |||
; | ; | ||
* Neutron detectors are e.weept irem response time testing. Response time shall be measured | * Neutron detectors are e.weept irem response time testing. Response time shall be measured | ||
; from the detector output or from the input of the first electronic component in the channel. | ; from the detector output or from the input of the first electronic component in the channel. | ||
l **Not including simulated therati power time constant, 5 1 0.0 x x.-C .g | l **Not including simulated therati power time constant, 5 1 0.0 x x.-C .g | ||
: #Heasured from start of turbine controt valse fast closure. L_ _ g g g g | : #Heasured from start of turbine controt valse fast closure. L_ _ g g g g e | ||
I __ .-. _ _ . ~ . . . _ _ _ . _ _ - _ | |||
; ..: | ; ..: | ||
~ | ~ | ||
is within the limits provided in the Com.j ' | is within the limits provided in the Com.j ' | ||
TABLE 4.3.1.1-1 (Cu tinued) i M N REACTOR PROTECT 10It 5YSTEM lit $TilWElffAT1011 $URVEILLAIICE REQUIREIEllT5 | TABLE 4.3.1.1-1 (Cu tinued) i M N REACTOR PROTECT 10It 5YSTEM lit $TilWElffAT1011 $URVEILLAIICE REQUIREIEllT5 i es i G i " (f) The LPRMs shall be calileated'at least once per 1000 effective full p hours (EFPII) | ||
i es i G i " (f) The LPRMs shall be calileated'at least once per 1000 effective full p hours (EFPII) | |||
; using the TIP systee. | ; using the TIP systee. | ||
j E j Z (g) Calibrate Rosemount tr4 unit :Walpoint at leest once per 31 days. | j E j Z (g) Calibrate Rosemount tr4 unit :Walpoint at leest once per 31 days. | ||
(h) Verify measured drive flow te be less then er equel to established drive flow at the existing flow control valve position. | (h) Verify measured drive flow te be less then er equel to established drive flow at the existing flow control valve position. | ||
l (1) This calibration | l (1) This calibration | ||
_ , ,____ m shall conshr. | _ , ,____ m shall conshr. | ||
| Line 1,759: | Line 1,031: | ||
4 (n) Theinstruments. CHAINIEL FUIICTICIIAL TEST and MML CALIORATICII shall include the tusine first stage pressure (o) The CHAIINEL CALIBItATI0ll shall esclude the fisw' reference transmitters; these transmitters shell.be i calibrated at least once per 18 months. | 4 (n) Theinstruments. CHAINIEL FUIICTICIIAL TEST and MML CALIORATICII shall include the tusine first stage pressure (o) The CHAIINEL CALIBItATI0ll shall esclude the fisw' reference transmitters; these transmitters shell.be i calibrated at least once per 18 months. | ||
i (p) This period may be extew$ed to the first refueling estage, not to exceed 9-15-87. | i (p) This period may be extew$ed to the first refueling estage, not to exceed 9-15-87. | ||
l 1 | l 1 | ||
* gO i F s n =a + | * gO i F s n =a + | ||
| Line 1,770: | Line 1,039: | ||
" 32 e j Om m | " 32 e j Om m | ||
{w .IE ,,, | {w .IE ,,, | ||
y 5 ,E O- w m * | |||
[ | [ | ||
c, l ? E O l == | c, l ? E O l == | ||
t | t | ||
! TABLE 3.3.6-2 " | ! TABLE 3.3.6-2 " | ||
CGisTICL A00 SLOCNTION SE1Polnis , | CGisTICL A00 SLOCNTION SE1Polnis , | ||
| Line 1,795: | Line 1,054: | ||
.. . Blased .m_ | .. . Blased .m_ | ||
. Neut.res Flur. Hoscale* { ~- | . Neut.res Flur. Hoscale* { ~- | ||
i 0. "" : O i 2. "" : 455*- | i 0. "" : O i 2. "" : 455*- | ||
u . . , . . .h.eudstion | u . . , . . .h.eudstion j L ; " :-.t h --- 1 0. "" e %.T ' i 3."" ; 39.7E* | ||
j L ; " :-.t h --- 1 0. "" e %.T ' i 3."" ; 39.7E* | |||
l b. Insperative NA IIA l c. hale >SE of RATED THENthL POER | l b. Insperative NA IIA l c. hale >SE of RATED THENthL POER | ||
- -> E of RATED TE NIAL POWER l d. Ileutron Flum - 71p.,cale | - -> E of RATED TE NIAL POWER l d. Ileutron Flum - 71p.,cale | ||
~ | ~ | ||
Start , $ 1 3 of RATES INEst4L PO K R 1 145 of AATED THEMIAL POWER 1:' 3. SOURCE RAIIGE ImMIT985 | Start , $ 1 3 of RATES INEst4L PO K R 1 145 of AATED THEMIAL POWER 1:' 3. SOURCE RAIIGE ImMIT985 | ||
* a. Detector not full in IIA IIA | * a. Detector not full in IIA IIA Y b. 45 scale < 1 x 10 cps 5 | ||
< 1.6 x 105 c,, | < 1.6 x 105 c,, | ||
C c. Insperative ilA R4 | C c. Insperative ilA R4 | ||
: d. Osunscale > 0.7 cps > 0.5 cys** | : d. Osunscale > 0.7 cps > 0.5 cys** | ||
: 4. INTENEDIATE RAIIGE IEDNITOR$ | : 4. INTENEDIATE RAIIGE IEDNITOR$ | ||
c_ m a. Detector not, full la NA IIA l gmO b. 15 scale i 108/125 division of full scale 1 110/125 division of full scale l U) | c_ m a. Detector not, full la NA IIA l gmO b. 15 scale i 108/125 division of full scale 1 110/125 division of full scale l U) | ||
{ O y0 c. Insperative tiA IIA | { O y0 c. Insperative tiA IIA | ||
> 3/125 divisier of full | > 3/125 divisier of full O __ < d. Beunscale > 5/125 division of full | ||
O __ < d. Beunscale > 5/125 division of full | |||
; 3m scale scale i | ; 3m scale scale i | ||
* O 4 5. SCRAft DISCNAPGE VOLT 31E I k= a. Water Level-Migh - Li51i602A < 18.00" < 21.12" | * O 4 5. SCRAft DISCNAPGE VOLT 31E I k= a. Water Level-Migh - Li51i602A < 18.00" < 21.12" | ||
! LI$nSeis -i 18.00" -i 21.60" | ! LI$nSeis -i 18.00" -i 21.60" | ||
: g 1 2 6. REACTOR C00LAIIT SYSTOI REC 1000LATI0ii Flohi | : g 1 2 6. REACTOR C00LAIIT SYSTOI REC 1000LATI0ii Flohi | ||
! a. 45 scale i IS E of rated flow $ 111% of rated flew i i | ! a. 45 scale i IS E of rated flow $ 111% of rated flew i i | ||
*1 *The Average Power Eange Monitor red him.k fu6ection is varied as a function of recirculation loop flow (w). | *1 *The Average Power Eange Monitor red him.k fu6ection is varied as a function of recirculation loop flow (w). | ||
M i | M i | ||
The trip setting c! this fonctice e st be maintained in accordance with Specification 3.2.2'q j U **Provided signal to colse ratio is > 2. etherwise setpoint of 3 cps and allowable 1.8 cys. l. | The trip setting c! this fonctice e st be maintained in accordance with Specification 3.2.2'q j U **Provided signal to colse ratio is > 2. etherwise setpoint of 3 cps and allowable 1.8 cys. l. | ||
k r | k r | ||
> ard limits provided in the GXR. " | > ard limits provided in the GXR. " | ||
4 kv | |||
4 | |||
kv | |||
DESIGN FEATURES | DESIGN FEATURES | ||
. m = | . m = | ||
| Line 1,845: | Line 1,085: | ||
r= = = : = - | r= = = : = - | ||
l | l | ||
.1 he reac core s 1 cont n 624 f asse tes. ch ass ly | .1 he reac core s 1 cont n 624 f asse tes. ch ass ly cons ts of zi onium a ey fuel nd water rods ar nged i a nomi 1 8x8 . | ||
cons ts of zi onium a ey fuel nd water rods ar nged i a nomi 1 8x8 | |||
arr y. The el rods ntain anium di ide f peller with tive len hs rally nging be en 1 and 150 hes. hose f- asse ies are imited those t t have een anal ed wit RC app ved c es and hods , | arr y. The el rods ntain anium di ide f peller with tive len hs rally nging be en 1 and 150 hes. hose f- asse ies are imited those t t have een anal ed wit RC app ved c es and hods , | ||
and ha been s to c ly with 11 of crite a in latest pproved revi on of GE AR (NED 24011-P- -US). | and ha been s to c ly with 11 of crite a in latest pproved revi on of GE AR (NED 24011-P- -US). | ||
k ONTROL ASSE IES > | k ONTROL ASSE IES > | ||
[ 5.3.2 he te or core all e tain 14 cont of crucif rod ass lies, ach con sting ' | [ 5.3.2 he te or core all e tain 14 cont of crucif rod ass lies, ach con sting ' | ||
array stain ss stee tubes urrounde by a er iform aped b' s | array stain ss stee tubes urrounde by a er iform aped b' s inless s eel shea . Ea tube s 11 co in 143. inches boron arbide l | ||
inless s eel shea . Ea tube s 11 co in 143. inches boron arbide l | |||
4 C X::. , | 4 C X::. , | ||
5.4 REACTOR COOLANT SYSTEN | 5.4 REACTOR COOLANT SYSTEN | ||
/ , | / , | ||
0ESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained: | 0ESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained: | ||
: a. In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal tiegradation pursuant to .he a | : a. In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal tiegradation pursuant to .he a appitcable Surveillance Requirements, a | ||
appitcable Surveillance Requirements, a | |||
h, For a pressure ef: | h, For a pressure ef: | ||
: 1. 1250 psig ca the suctien ofde of the recireuhtion pump. < | : 1. 1250 psig ca the suctien ofde of the recireuhtion pump. < | ||
: 2. 165C psig from the mircuhtfort pump discharge to tre outlet ! | : 2. 165C psig from the mircuhtfort pump discharge to tre outlet ! | ||
side of the discharge shutaff valve.- | side of the discharge shutaff valve.- | ||
p 3. 1550 psig free the discharge shutoff n1ve to the jnt pumps. | p 3. 1550 psig free the discharge shutoff n1ve to the jnt pumps. | ||
l | l | ||
: c. For a temperature of 57 P F l VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 16.000 cubic feet. | : c. For a temperature of 57 P F l VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 16.000 cubic feet. | ||
l RIVER BEND - UNIT 1 5-5 Amendment No.33 1 | l RIVER BEND - UNIT 1 5-5 Amendment No.33 1 | ||
l'; c- .L , | l'; c- .L , | ||
n-7 ~ | n-7 ~ | ||
: g. , p l | : g. , p l | ||
> i | > i i. | ||
i. | |||
-l | -l | ||
. Replacement paragraphs for Technical Specifications 5.3.1, lum ASSDELIES and 5.3.2, CWra0L JOD ASSDeLIES. i MJEL ASSDELIES , | |||
. Replacement paragraphs for Technical Specifications 5.3.1, lum ASSDELIES and 5.3.2, CWra0L JOD ASSDeLIES. i | |||
MJEL ASSDELIES , | |||
t 5.3.1' %e reactor-shall contain 624 fuel assemblies. Each assenbly shall consist of.. | t 5.3.1' %e reactor-shall contain 624 fuel assemblies. Each assenbly shall consist of.. | ||
a matrix of Zircalloy clad fuel rods with an initial camposition of slightly enriched | a matrix of Zircalloy clad fuel rods with an initial camposition of slightly enriched | ||
| Line 1,901: | Line 1,116: | ||
l- fuel designs apptwed by the NIC Staff for use in WR's. l | l- fuel designs apptwed by the NIC Staff for use in WR's. l | ||
;. 6 i | ;. 6 i | ||
i | i 0:NTROL RCD ASSDELIES r 5.3.2 2e reactor oore shall contain 145 cruciform shaped control rod assemblies. ; | ||
0:NTROL RCD ASSDELIES r | |||
5.3.2 2e reactor oore shall contain 145 cruciform shaped control rod assemblies. ; | |||
We control material shall be boron carbide powder (B4C ) ' and/or hafniunt netal. %e ' | We control material shall be boron carbide powder (B4C ) ' and/or hafniunt netal. %e ' | ||
: r. control rod assemblies shall be full length. , | : r. control rod assemblies shall be full length. , | ||
a t | a t | ||
[ | [ | ||
t | t | ||
( | ( | ||
; | ; | ||
U. . | U. . | ||
h i | h i | ||
h I | |||
h | |||
I | |||
e | e | ||
. . .v ,- | . . .v ,- | ||
~ | ~ | ||
ADMINISTRATIVE CONTROLS SEMIANNUAL EFFLUENT RELEASE REPORT (Continued) - | |||
ADMINISTRATIVE CONTROLS | |||
SEMIANNUAL EFFLUENT RELEASE REPORT (Continued) - | |||
I to MEMERS OF THE PUBLIC due to their activities inside the SITE Si (Figure 5.1.3) during the report period. All assumptions used in making these ' | I to MEMERS OF THE PUBLIC due to their activities inside the SITE Si (Figure 5.1.3) during the report period. All assumptions used in making these ' | ||
ciuded in these reports. assessments (i.e., specific activity, exposure time and! | ciuded in these reports. assessments (i.e., specific activity, exposure time and! | ||
| Line 1,943: | Line 1,139: | ||
and direct radiation)ycle sources (including doses from primary effluent pathways ' | and direct radiation)ycle sources (including doses from primary effluent pathways ' | ||
for the previous calendar year to show conformance with i | for the previous calendar year to show conformance with i | ||
40 CFR Operation. Part 190 Environmental Radiation Protection Standards for N J and gsseous offluents are given in Regulatory Guide 1.109,il 1 | 40 CFR Operation. Part 190 Environmental Radiation Protection Standards for N J and gsseous offluents are given in Regulatory Guide 1.109,il 1 | ||
The Semiannual Radioactive Effluent Release Reports shall include a list and 1 description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period. { l | The Semiannual Radioactive Effluent Release Reports shall include a list and 1 description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period. { l a The Semiannual Radioactive Effluent Release Reports shall include any changes ' | ||
a The Semiannual Radioactive Effluent Release Reports shall include any changes ' | |||
) made= during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the 00CM, as well as a listing of new locations for dose calculations and/or environmental. | ) made= during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the 00CM, as well as a listing of new locations for dose calculations and/or environmental. | ||
cation 3.12.2 monitoring identified by the land use census pursuant to Specifi- ;i | cation 3.12.2 monitoring identified by the land use census pursuant to Specifi- ;i gPECIALREPORTS C. 9. 2 Special reports shall be submitted in the following manner: , | ||
gPECIALREPORTS | |||
C. 9. 2 Special reports shall be submitted in the following manner: , | |||
i J. | i J. | ||
Spnial reports shall be submitted to the U.S. Nuclear Regulatory jn Commission, Document Control Desk, Washington, DC 205SS, with 6 - | Spnial reports shall be submitted to the U.S. Nuclear Regulatory jn Commission, Document Control Desk, Washington, DC 205SS, with 6 - | ||
| Line 1,959: | Line 1,148: | ||
1 dent Inspector, within the time period specified for each report. | 1 dent Inspector, within the time period specified for each report. | ||
i h b. | i h b. | ||
Spacial reports in reperd to C6rbicula will be submitted to the NRC g y ')) within "s0 dsys of identifit.ation of infestation. In setordance with | Spacial reports in reperd to C6rbicula will be submitted to the NRC g y ')) within "s0 dsys of identifit.ation of infestation. In setordance with | ||
){s 3 | ){s 3 | ||
g the settlevent agreement dated October 10, 1984, these reports shall describe the level of. infestation, affected systems and ceasures taken l | g the settlevent agreement dated October 10, 1984, these reports shall describe the level of. infestation, affected systems and ceasures taken l | ||
g to prevent further infestation. l l 6.10 RECORD RETENTION | g to prevent further infestation. l l 6.10 RECORD RETENTION | ||
^ ' | ^ ' | ||
| Line 1,972: | Line 1,159: | ||
: a. 1 | : a. 1 | ||
[ Records power and logs of unit operation covering time interval at each level. | [ Records power and logs of unit operation covering time interval at each level. | ||
RECEIVED RIVER BEND - UNIT 1 6-19 DEC 151987 ^**"d*'"t * *17 8QC | RECEIVED RIVER BEND - UNIT 1 6-19 DEC 151987 ^**"d*'"t * *17 8QC | ||
..--.,,.m.. | ..--.,,.m.. | ||
CORE OPERATING LIMITS REPORT 6.9.3.1 Core operating limits shall be established prior to startup from each reload cycle, or prior to any remaining portion of a reload cycle, for the following: | |||
CORE OPERATING LIMITS REPORT | |||
6.9.3.1 Core operating limits shall be established prior to startup from each reload cycle, or prior to any remaining portion of a reload cycle, for the following: | |||
E | E | ||
: a. The AVERAGE POWER RANGE MONITOR (APRM) setpoints for Specifications 2.2.1, 3.2.2 and 3.3.6. | : a. The AVERAGE POWER RANGE MONITOR (APRM) setpoints for Specifications 2.2.1, 3.2.2 and 3.3.6. | ||
: b. The AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGR) for | : b. The AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGR) for Specification 3.2.1. | ||
Specification 3.2.1. | |||
: c. The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.3. ; | : c. The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.3. ; | ||
! d. The LINEAR HEAT GENERATION RATE (LHGR) of Specification 3.2.4. | ! d. The LINEAR HEAT GENERATION RATE (LHGR) of Specification 3.2.4. | ||
| Line 2,000: | Line 1,175: | ||
G.9.3.4 The Conf OPERATING LIMITS RCFORT., including any mid eycle revision or supplements shall be providec, upon issuance for each reload cycle, to - | G.9.3.4 The Conf OPERATING LIMITS RCFORT., including any mid eycle revision or supplements shall be providec, upon issuance for each reload cycle, to - | ||
the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. | the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. | ||
'''' Pcga 13 of 22 i RBS CYCLE 3 COLRi RW. 0 SAMPLE. | |||
'''' Pcga 13 of 22 i RBS CYCLE 3 COLRi RW. 0 | |||
SAMPLE. | |||
13 I I | 13 I I | ||
,, gs'a mma | ,, gs'a mma pM g'k | ||
/ \ j a | |||
pM g'k | 12 I/ / I | ||
/ \ j | |||
%k 1 | %k 1 | ||
s& i IE k - | s& i IE k - | ||
lg 11 g | lg 11 g | ||
k : | k : | ||
r* s 4 : | r* s 4 : | ||
<8 1. (, - | <8 1. (, - | ||
g 1-l ll | g 1-l ll g% | ||
g% | |||
g 85 4 ' | g 85 4 ' | ||
g | g | ||
. a 8 l | |||
. a 8 | |||
l | |||
; | ; | ||
I ? | I ? | ||
I m u m m m mm m m m m mm m m m m m m m m m m m mmm mm mm m mmmmlemmel 0 10 . 20 30 40 00 AVERAGE PLANA 9 EXPOSURE (GWd/t) | I m u m m m mm m m m m mm m m m m m m m m m m m mmm mm mm m mmmmlemmel 0 10 . 20 30 40 00 AVERAGE PLANA 9 EXPOSURE (GWd/t) l i | ||
l i | |||
I FIGURE 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATIGN MATE (MAPLHGR) | I FIGURE 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATIGN MATE (MAPLHGR) | ||
VERSUS AVERAGE PLANAR EXPOSURE BP85RB163 Ii I | VERSUS AVERAGE PLANAR EXPOSURE BP85RB163 Ii I | ||
L | L | ||
- \ | - \ | ||
j | j | ||
. . . . _ . . . . _ . . _ . - - _ . . .~ | . . . . _ . . . . _ . . _ . - - _ . . .~ | ||
i | i Pago 14 of 22 I SAMPLE RBS CYCLE 3 COLR] | ||
Pago 14 of 22 I | |||
SAMPLE RBS CYCLE 3 COLR] | |||
Rev. 0 ' | Rev. 0 ' | ||
l 13 i | l 13 i | ||
m 12 L 7 j j | m 12 L 7 j j | ||
; | ; | ||
as | as | ||
$ % ; | $ % ; | ||
| Line 2,072: | Line 1,216: | ||
> g ul | > g ul | ||
= | = | ||
\ | \ | ||
b | b I ' . ,- | ||
I ' . ,- | |||
. .....a...s ................... .. | . .....a...s ................... .. | ||
10 20 30 40 50 - | 10 20 30 40 50 - | ||
| Line 2,087: | Line 1,227: | ||
!- MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLhGR) | !- MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLhGR) | ||
VERSUS AVERAGE PLANAR EXPOSURE RP85R8248 i' . | VERSUS AVERAGE PLANAR EXPOSURE RP85R8248 i' . | ||
o | o | ||
. ~- ,---,.-,,,...,.,-----,,,,v-,-- -.-,r,--,.,ew,w,,,,,,e owe..r---,ve--;c,e-,,-,-w-w, av-,-- ,,v.,+-,- --e ,,- . - , - , , ,y | . ~- ,---,.-,,,...,.,-----,,,,v-,-- -.-,r,--,.,ew,w,,,,,,e owe..r---,ve--;c,e-,,-,-w-w, av-,-- ,,v.,+-,- --e ,,- . - , - , , ,y | ||
Paga 15 of 22 l RBS CYCLE 3 COLR' | Paga 15 of 22 l RBS CYCLE 3 COLR' | ||
- S A M P t. E Rev. 0 13 e=.. ...,'e i | |||
- S A M P t. E Rev. 0 | |||
13 | |||
e=.. ...,'e i | |||
)/a m, | )/a m, | ||
( ' | ( ' | ||
| Line 2,108: | Line 1,237: | ||
; | ; | ||
/ _ | / _ | ||
11 | 11 | ||
\, | \, | ||
I g 4 5 | I g 4 5 | ||
1 % | 1 % | ||
3 I10 k 9 | 3 I10 k 9 | ||
Il.. | Il.. | ||
%g\ | %g\ | ||
; ; | ; ; | ||
i | i | ||
, s i t | , s i t | ||
l | l i | ||
L i | |||
i | |||
.y _, | .y _, | ||
' i | ' i | ||
! l il ' | ! l il ' | ||
o to ao su 40 2 l | o to ao su 40 2 l | ||
l - | l - | ||
AVOLACE FLANAR EXPoruRE (GWd/t) | AVOLACE FLANAR EXPoruRE (GWd/t) | ||
: l. . | : l. . | ||
FIGURE 4 MAXIMUM AWRAGE PLANAR UNEAR HEAT GENERATION RATE (MAPLHGR) W.RSUS AVERAGE PLANAR EXPOSURE - SPSSRS278 0 | |||
FIGURE 4 MAXIMUM AWRAGE PLANAR UNEAR HEAT | |||
GENERATION RATE (MAPLHGR) W.RSUS AVERAGE PLANAR EXPOSURE - SPSSRS278 | |||
0 | |||
___________.__.s-.____. ,_ _ _ _ _ - . . . .__,_,.,._,,_._.._,,,._,.,_,.,_,ym.,_. _ , . . , , , , , , , , , , _ , , _ , . , . , . _ . _ _ . , , _ . _ _ , _ _ , , , | ___________.__.s-.____. ,_ _ _ _ _ - . . . .__,_,.,._,,_._.._,,,._,.,_,.,_,ym.,_. _ , . . , , , , , , , , , , _ , , _ , . , . , . _ . _ _ . , , _ . _ _ , _ _ , , , | ||
- -_ ~ - . . .. - - - . - . . . . . . . _ - . . - - - . . - - - . - . - - - - . . . | - -_ ~ - . . .. - - - . - . . . . . . . _ - . . - - - . . - - - . - . - - - - . . . | ||
Page 16 or 22 S A M P t. E ass cycts a cota | |||
Page 16 or 22 | |||
S A M P t. E ass cycts a cota | |||
, Rev. O I | , Rev. O I | ||
13 | 13 | ||
'M'um l | 'M'um l | ||
,pW g | ,pW g | ||
| Line 2,171: | Line 1,268: | ||
9g ig p 8" | 9g ig p 8" | ||
*4 | *4 | ||
# g | # g g ' | ||
g ' | |||
11 | 11 | ||
: n. 1\ , | : n. 1\ , | ||
l 7 | |||
l | |||
7 | |||
30 40 So l | 30 40 So l | ||
0 10 20 | 0 10 20 | ||
: A'4 RACE PLANAR EXPOSUE (GW6/t) | : A'4 RACE PLANAR EXPOSUE (GW6/t) | ||
I L . | |||
I | |||
L . | |||
FIGURE 5 MAXIWUW AVERAGE PLANAR UNEAR MCAT GENERATION RATE (MAPLHOR) VERSUS AWGE PLANAR EXPOSURE - BPSSRS299 ,m. _ | FIGURE 5 MAXIWUW AVERAGE PLANAR UNEAR MCAT GENERATION RATE (MAPLHOR) VERSUS AWGE PLANAR EXPOSURE - BPSSRS299 ,m. _ | ||
,- --..w,-,~,. , , , . - , . - - - ~ . . _ - . . . . . . ~ , . . , . . - . . . , , , - - - - , , - - - , . . - - - - , , , . - , - - , , . - , . , , , , , ,-,,-,------...,-,n. | ,- --..w,-,~,. , , , . - , . - - - ~ . . _ - . . . . . . ~ , . . , . . - . . . , , , - - - - , , - - - , . . - - - - , , , . - , - - , , . - , . , , , , , ,-,,-,------...,-,n. | ||
~ | ~ | ||
** a - | ** a - | ||
Page 17 of 22 | Page 17 of 22 | ||
~ | ~ | ||
SAMPLE ass cycts 3 cota Rev. 0 | SAMPLE ass cycts 3 cota Rev. 0 l '. | ||
l '. | |||
l ! | l ! | ||
13 l | 13 l | ||
,,,===== .. | ,,,===== .. | ||
l l l | l l l | ||
| Line 2,224: | Line 1,291: | ||
g | g | ||
,a _ | ,a _ | ||
'4 g | '4 g | ||
,, 8 Ir" \ | ,, 8 Ir" \ | ||
\ . | \ . | ||
I- .. i f | I- .. i f | ||
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'Il. g 4 | 'Il. g 4 | ||
i | i | ||
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4 s | 4 s | ||
j < | j < | ||
a 1 | |||
a | |||
1 | |||
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:l r | :l r t , | ||
t , | |||
< l h {, | < l h {, | ||
y . 4 =: | y . 4 =: | ||
| Line 2,258: | Line 1,311: | ||
~ | ~ | ||
AVUtAet M.ANAR EMP00WRE (SWd/t) | AVUtAet M.ANAR EMP00WRE (SWd/t) | ||
' ''d ' | ' ''d ' | ||
pggg. 6 | pggg. 6 | ||
' 3 3 MA30MWW AVULAet PLANAR UNEAR WAT l OENDIAM RAlt (MAPLMOR) VUtSWS AWRAGE a | ' 3 3 MA30MWW AVULAet PLANAR UNEAR WAT l OENDIAM RAlt (MAPLMOR) VUtSWS AWRAGE a PLANAR EXPOSURE = SPSSRS308 i | ||
PLANAR EXPOSURE = SPSSRS308 i | |||
1 1 | 1 1 | ||
._.._.____.__.--_---.a-___w,m upwwwgeu.,*p,,-e--=y-e-y my w n-m vre + mm w c __ gm g.'M'Wh#9''*9-"9Y M * | ._.._.____.__.--_---.a-___w,m upwwwgeu.,*p,,-e--=y-e-y my w n-m vre + mm w c __ gm g.'M'Wh#9''*9-"9Y M * | ||
. r SAMPLE Page 18 of 22 RBS CYCLE 3 COLR | |||
. r | |||
SAMPLE Page 18 of 22 RBS CYCLE 3 COLR | |||
{ | { | ||
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; ll | ; ll | ||
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; ; , | ; ; , | ||
: h. i d n , l s 6 | |||
: h. i d n , l | |||
s 6 | |||
[ 13 - | [ 13 - | ||
p q | p q | ||
| Line 2,299: | Line 1,331: | ||
i. | i. | ||
) | ) | ||
; | ; | ||
9 % | 9 % | ||
,+ | ,+ | ||
I 4 | I 4 | ||
g : | g : | ||
k i' h | k i' h | ||
ho r il | ho r il it , | ||
l' I | |||
it , | \ h to l-11 I l | ||
l' | |||
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k g . | k g . | ||
4 | 4 g | ||
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f i j h ,l j' il i . | |||
f | |||
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,l | ,l 0 0 :i , | ||
l 0 7 | |||
0 0 :i , | t b | ||
o e a a # # | |||
t | |||
AvtRME'PLAMAR DPOWRs (GW(M RGURE 7 ,, | AvtRME'PLAMAR DPOWRs (GW(M RGURE 7 ,, | ||
MANRAAd AvUtMR PLAMAR 835AR MAT EMRA110N RAlt W NUtWS AVUtME puMAR cposuns - esses ,4 | MANRAAd AvUtMR PLAMAR 835AR MAT EMRA110N RAlt W NUtWS AVUtME puMAR cposuns - esses ,4 | ||
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I Page 19 of 22 | I Page 19 of 22 | ||
. SAMPLE ass cycts 3 cotR | . SAMPLE ass cycts 3 cotR | ||
, Rev. O i | , Rev. O i | ||
I | I | ||
/ % g i 13 r , | / % g i 13 r , | ||
; | ; | ||
| Line 2,394: | Line 1,370: | ||
/ \6 > | / \6 > | ||
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/ % | / % | ||
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I 11 | I 11 | ||
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l li l | l li l | ||
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l l t | l l t | ||
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( | ( | ||
1 o to so se e ao AWDIAN PLANAR CMA M FIGURE 8 wueWUW AvetAGE PuMAR m HEAT cENDIADON RAlt 08APLHol0 vetsuS AvtRAGE PuMAR DPCdWRE - 883220 . | |||
1 o to so se e ao AWDIAN PLANAR CMA M FIGURE 8 wueWUW AvetAGE PuMAR m HEAT cENDIADON RAlt 08APLHol0 vetsuS AvtRAGE | |||
PuMAR DPCdWRE - 883220 . | |||
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Page 20 of 22 I SAMPLE ass-crete 3 cotai | |||
Page 20 of 22 I | , . 1.7 Rev. 0 i i 1 j g inen h 1 1 . I I I I I ' ' * *4 | ||
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RI [[ [ | RI [[ [ | ||
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I WCPR = | I WCPR = | ||
-0.761(CT) + ' E3k | -0.761(CT) + ' E3k i _ . | ||
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1 f | 1 f | ||
1.3 | |||
'I I 1 | 'I I 1 | ||
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| Line 2,551: | Line 1,459: | ||
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p._, | p._, | ||
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7 . | 7 . | ||
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, , 4 . +.+, ' | , , 4 . +.+, ' | ||
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m,- s. I i | m,- s. I i w. | ||
w. | |||
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11 | 11 | ||
+1 9 | |||
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9 | |||
j # | j # | ||
cy | cy | ||
, m ' | , m ' | ||
t- t I r ,u 1.0 m .] 7 i | t- t I r ,u 1.0 m .] 7 i p 3 40 00 00 100 120 CORE FLOW 5 0F RATED CORE FLOW MIRIRE 9 WCMt f | ||
p 3 40 00 00 100 120 | |||
CORE FLOW 5 0F RATED CORE FLOW MIRIRE 9 WCMt f | |||
1 l | 1 l | ||
{ | { | ||
k_: ---- - | k_: ---- - | ||
SAMPLE P*9 RBS CYCLE 3 COLR 21 or 22 Rev. 0 i I [ | |||
[ .. 1 t I I!I II I . ' - I i T : I I I I I I 'I I'I ' ' | |||
SAMPLE P*9 RBS CYCLE 3 COLR 21 or 22 | |||
Rev. 0 | |||
i I [ | |||
[ .. 1 t I | |||
I!I II I . ' - I i T : I I I I I I 'I I'I ' ' | |||
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1 , , T r T _ j ,If I, [^ iT I I ' fI [[ | 1 , , T r T _ j ,If I, [^ iT I I ' fI [[ | ||
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I I I . | |||
I 7. I .. I | I 7. I .. I | ||
. ;Y hhI h I I r | |||
. ;Y hhI h | |||
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7 | 7 | ||
'' 1 I I I I - - | '' 1 I I I I - - | ||
I I T I 1 I 1.4 < > | I I T I 1 I 1.4 < > | ||
I~ | I~ | ||
I i - 1 i 1 I . . | I i - 1 i 1 I . . | ||
i I I . . I . I | i I I . . I . I I I I I I ii . | ||
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I I ' | I I ' | ||
.1 I -+ | .1 I -+ | ||
| Line 2,697: | Line 1,530: | ||
I I I I | I I I I | ||
: I I . i % - | : I I . i % - | ||
w : . I I . | w : . I I . | ||
I i r | I i r | ||
i C I T I t | i C I T I t | ||
. 1 I NI ^ | . 1 I NI ^ | ||
I I ! % | I I ! % | ||
I . . m - | I . . m - | ||
' I I N- I ;q I . | ' I I N- I ;q I . | ||
, - . , ^+ W l | , - . , ^+ W l | ||
I T i I y- -++++ | I T i I y- -++++ | ||
ar wwn 7 ; . . | ar wwn 7 ; . . | ||
- I ; m=4&<> {% | - I ; m=4&<> {% | ||
7, I: , . | 7, I: , . | ||
1 I I | 1 I I I | ||
T T 1 . | |||
I I I i | I I I i | ||
I _ | I _ | ||
I I i 1 | I I i 1 | ||
7 | 7 I I I i | ||
I I I i | |||
* r | * r | ||
; . . | ; . . | ||
i | i | ||
. I I . | . I I . | ||
I i i | I i i | ||
_..- ) | _..- ) | ||
= - . | = - . | ||
Mm T h | Mm T h T 3k | ||
'4 I | |||
T 3k | |||
'4 | |||
I | |||
y , q I 'E. 1 l | y , q I 'E. 1 l | ||
, j d . y 'L' [ | |||
, j | |||
d . y 'L' [ | |||
,.t4k = M aj m . | ,.t4k = M aj m . | ||
m.; | m.; | ||
1J - 4- 1 a | 1J - 4- 1 a | ||
.s 4 | |||
.s | ,w 7 | ||
4 | |||
,w | |||
7 | |||
; | ; | ||
[- -- -- | [- -- -- | ||
I ) | I ) | ||
- I . 1 1 | - I . 1 1 | ||
I .. Man L , | I .. Man L , | ||
n h, , | n h, , | ||
n h1 J >= M MMM' | |||
n | |||
h1 J >= M MMM' | |||
', ,,,,wm, >h p=a > (- | ', ,,,,wm, >h p=a > (- | ||
e , | e , | ||
1,1 - '. mw. i.9 1 i . | |||
I : I _L 7 na>mumr< s | |||
I : I _L | |||
7 na>mumr< s | |||
"-'- h | "-'- h | ||
, , ; | , , ; | ||
,g *f- - -j' . , y 4na ..e an H pr$4 = f-- r -- | ,g *f- - -j' . , y 4na ..e an H pr$4 = f-- r -- | ||
1- t. I | 1- t. I 11 J p,. , , , ^ | ||
11 J p,. , , , ^ | |||
e a .s- > > = e - | e a .s- > > = e - | ||
fr | fr | ||
-.w "_p . -> | -.w "_p . -> | ||
, ,,; | , ,,; | ||
: y1 =r> - | : y1 =r> - | ||
, ' 1 1 1 | , ' 1 1 1 | ||
, , z _4 | , , z _4 | ||
: f. , <9 --- | : f. , <9 --- | ||
1 l | 1 l | ||
t g | t g | ||
; | ; | ||
1 | 1 1.8 e - | ||
1.8 e - | |||
3 e et 8 1st ist | 3 e et 8 1st ist | ||
; THERMAL POWM, # OF RATED THERMAL POWWI l l | ; THERMAL POWM, # OF RATED THERMAL POWWI l l | ||
1 pigygg 10 h *c'** . | 1 pigygg 10 h *c'** . | ||
| Line 2,816: | Line 1,598: | ||
I i | I i | ||
1 1 | 1 1 | ||
. _ . _ . _ _ _ _ . . . , . _ . . _ _ . - - ~ . - _ _ . . _ _ _ , _ . . ' . . . _ - - _ - - - _ | . _ . _ . _ _ _ _ . . . , . _ . . _ _ . - - ~ . - _ _ . . _ _ _ , _ . . ' . . . _ - - _ - - - _ | ||
S A M P t. E RB C L 3 COLR-n- ECOEECCE | |||
S A M P t. E RB C L 3 COLR- | |||
n- ECOEECCE | |||
:: eMMMMMMMo : | :: eMMMMMMMo : | ||
oMMMMMMMMM. | oMMMMMMMMM. | ||
:: eMMMMMMMMME% | :: eMMMMMMMMME% | ||
| Line 2,834: | Line 1,607: | ||
::-DMMMMMMMMMMMMMo - | ::-DMMMMMMMMMMMMMo - | ||
:::EMEMMMMMMMMMMME : | :::EMEMMMMMMMMMMME : | ||
:::!MMMMMMMMMMMMME | :::!MMMMMMMMMMMMME | ||
:::8MMMMMMMMMMMMME | :::8MMMMMMMMMMMMME | ||
!' *MMMMMMMMMMMMM" L :: MMMMMMMMMMMMM l | |||
!' *MMMMMMMMMMMMM" L :: MMMMMMMMMMMMM | |||
l | |||
MMMMMMMMMMM" | MMMMMMMMMMM" | ||
: MMMMMMMMM" MMMMMMM" l : | |||
: MMMMMMMMM" | l 2 DDDDDDDD ! | ||
MMMMMMM" | |||
l : | |||
l | |||
2 DDDDDDDD ! | |||
IIIIIIIl , , | IIIIIIIl , , | ||
1 3 5 7 91113151719212325272931233537384143454749515355 | 1 3 5 7 91113151719212325272931233537384143454749515355 Fu.1 Typ. | ||
1 A = 383228 E = SP85RB248 8 = 88322C F = SP85RS299 | |||
Fu.1 Typ. | |||
::fl'li'; | ::fl'li'; | ||
l n ur. | l n ur. | ||
e 11. a.r.r.ne. cor. to. dins P.et.rn l | e 11. a.r.r.ne. cor. to. dins P.et.rn l | ||
e e .ee | e e .ee | ||
* me o -- , 4 e . . . e. . e | * me o -- , 4 e . . . e. . e | ||
| Line 2,870: | Line 1,624: | ||
:= , .. ! | := , .. ! | ||
, ENCLOSURE II | , ENCLOSURE II CORE' OPERATING LIMITS REPORT SUBMITTAL I 89-03 ! | ||
CORE' OPERATING LIMITS REPORT SUBMITTAL I 89-03 ! | |||
Page 1 of 22 i RBS CYCLE 3 COLR' l' Rev. 0 SAMPLE , | Page 1 of 22 i RBS CYCLE 3 COLR' l' Rev. 0 SAMPLE , | ||
RIVER BEND STATION, OYCLE 3 ! | RIVER BEND STATION, OYCLE 3 ! | ||
; | ; | ||
CORE OPERATING LIMITS REPORT (COLR) i I | CORE OPERATING LIMITS REPORT (COLR) i I | ||
OCTOBER 1989 j | OCTOBER 1989 j l | ||
l | |||
1 | 1 | ||
, CONTROLLED COPY 1 | |||
I l | |||
PREPARED BY DATE: | PREPARED BY DATE: | ||
Supervisor, Core Analysis l i River Bend Nuclear Station j l | Supervisor, Core Analysis l i River Bend Nuclear Station j l | ||
l l | l l | ||
l A | l A APPROVED BY: DATE: ' | ||
Manager, Engineering River Bend Nuclear Station l 1 | |||
APPROVED BY: DATE: ' | APPROVED -BY : DATE: l Facilities Review Committee l River Bend Nuclear Station ; | ||
Manager, Engineering River Bend Nuclear Station l | |||
l l | l l | ||
APPROVED BY: DATE: | APPROVED BY: DATE: | ||
| Line 2,903: | Line 1,646: | ||
l l | l l | ||
1 | 1 | ||
4 . . | |||
Page 2 of 22 RBS CYCLE 3 COLR SAMPLE Rev. o LIST OF EFFECTIVE PAGES Page (s) Revision 1-22 0 lr l | |||
Page 2 of 22 RBS CYCLE 3 COLR SAMPLE Rev. o | l l | ||
LIST OF EFFECTIVE PAGES Page (s) Revision 1-22 0 | |||
lr l | |||
l | |||
l | |||
p ea y+. | p ea y+. | ||
Page 3 of 22 Ras CYCtE 3 Cota SAMPLE Rev. O INTRODUCTION AND | Page 3 of 22 Ras CYCtE 3 Cota SAMPLE Rev. O INTRODUCTION AND | ||
==SUMMARY== | ==SUMMARY== | ||
o This report provides the values of the Average Power Range Monitor (APRM) scram and rod block setpoints, the 3 | o This report provides the values of the Average Power Range Monitor (APRM) scram and rod block setpoints, the 3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) limits, the core flow dependent MINIMUM CRITICAL POWER RATIO (MCPR) limits, MCPR , the thermal power dependent MCPR limits MCPR and the LINEkR HEAT GENERATION RATE (LHGR) limits for River Bend Station, Cycle 3 as required by Technical Specification 6.9.3.1. 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. | ||
AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) limits, the core flow dependent MINIMUM CRITICAL POWER RATIO (MCPR) limits, MCPR , the thermal power dependent MCPR limits MCPR and the LINEkR HEAT GENERATION RATE (LHGR) limits for River Bend Station, Cycle 3 as required by Technical Specification 6.9.3.1. 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. | |||
f i | f i | ||
w | w L'. , | ||
L'. , | |||
Page 4 of 22 L SAMPLE RBS CYCLE 3 COLR Rev. 0 l | Page 4 of 22 L SAMPLE RBS CYCLE 3 COLR Rev. 0 l | ||
TECilNICAL SPECIFICATION 2.2.1 LIMITING SAFETY SYSTEM SETTINGS | TECilNICAL SPECIFICATION 2.2.1 LIMITING SAFETY SYSTEM SETTINGS REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS The APRM flow biased simulated thermal power-high scram trip setpoints for use in Technical Specification 2.2.1, Table 2.2.1-1 are as follows: | ||
REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS The APRM flow biased simulated thermal power-high scram trip setpoints for use in Technical Specification 2.2.1, Table 2.2.1-1 are as follows: | |||
ALLOWABLE I | ALLOWABLE I | ||
FUNCTIONAL UNIT TRIP SETPOINT VALUES | FUNCTIONAL UNIT TRIP SETPOINT VALUES | ||
: 2. Average Power Range Monitort | : 2. Average Power Range Monitort | ||
: b. Flow Biased Simulated Thermal Powcr-High ' | : b. Flow Biased Simulated Thermal Powcr-High ' | ||
: 1) Two Recirculation 0.66W+48% 0.66W+51% | : 1) Two Recirculation 0.66W+48% 0.66W+51% | ||
| Line 2,951: | Line 1,671: | ||
tion Loop Operation The relationships for two recirculation loop operation are taken from Reference 4. The relationships for single recirculation loop operation are taken from Reference 5, which is based on Reference 6. | tion Loop Operation The relationships for two recirculation loop operation are taken from Reference 4. The relationships for single recirculation loop operation are taken from Reference 5, which is based on Reference 6. | ||
l l | l l | ||
q l | |||
q | |||
l | |||
s= | s= | ||
c e oe , | c e oe , | ||
-c Page 5 of 22 RBS CYCLE 3 COLR Rev. O SAMPLE t | -c Page 5 of 22 RBS CYCLE 3 COLR Rev. O SAMPLE t | ||
TECHNICAL SPECIFICATION 3.2.1 i | TECHNICAL SPECIFICATION 3.2.1 i | ||
POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINFAR HEAT GENERATION RATE The limiting APLHGR value for'the most limiting lattice > | POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINFAR HEAT GENERATION RATE The limiting APLHGR value for'the most limiting lattice > | ||
| Line 2,970: | Line 1,684: | ||
l l | l l | ||
1 | 1 | ||
f( c i | |||
f( c | Page 6 of 22 RBS CYCLE 3 COLR SAMPLE Rev. 0 , | ||
TECHNICAL SPECIFICATION 3.2.2 POWER DISTRIBUTION LIMITS ' | |||
TECHNICAL SPECIFICATION 3.2.2 | |||
POWER DISTRIBUTION LIMITS ' | |||
t APRM SETPOINTS ' | t APRM SETPOINTS ' | ||
L The APRM flow biased simulated thermal power-high scram trip setpoint (S) and flow biased neutron flux-upscale R fr use in Technical control rod block trip setpoint-(SSpecification 3.2.2 are as follows:B) , | L The APRM flow biased simulated thermal power-high scram trip setpoint (S) and flow biased neutron flux-upscale R fr use in Technical control rod block trip setpoint-(SSpecification 3.2.2 are as follows:B) , | ||
j a) Two Recirculation Loop Operation y ' Trip Setpoint, Allowable Value S (0.66W + 48%)T S (0.66W + Sl%)T , | j a) Two Recirculation Loop Operation y ' Trip Setpoint, Allowable Value S (0.66W + 48%)T S (0.66W + Sl%)T , | ||
S RB (0.66W + 42%)T S RB (0.66W + 4 5%) T b) Sing)e Recirculation Loop Operation Trip Setpoint Allowable Value S (0.66W + 42.7%)T S (0.66W + 45.7%)T S | S RB (0.66W + 42%)T S RB (0.66W + 4 5%) T b) Sing)e Recirculation Loop Operation Trip Setpoint Allowable Value S (0.66W + 42.7%)T S (0.66W + 45.7%)T S | ||
RB (0. 66W + 36.7%) T S RB ( . 6W + 39.70 T where: S and S RB are in percent of RATED THERMAL POWER, | RB (0. 66W + 36.7%) T S RB ( . 6W + 39.70 T where: S and S RB are in percent of RATED THERMAL POWER, W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated core flow of 84.5 million lbs/hr. | ||
W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated | |||
core flow of 84.5 million lbs/hr. | |||
T = The ratio of FRACTION OF RATED THERMAL POWER (FRTP) divided by the CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLPD). T is applied only if less than or equal to 1.0. | T = The ratio of FRACTION OF RATED THERMAL POWER (FRTP) divided by the CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLPD). T is applied only if less than or equal to 1.0. | ||
The relationships for two recirculation loop operation are taken from Reference 4. The relationships for single recirculation loop- operation are taken from Reference 5, which is based on Reference 6. | The relationships for two recirculation loop operation are taken from Reference 4. The relationships for single recirculation loop- operation are taken from Reference 5, which is based on Reference 6. | ||
I',' | I',' | ||
o m e . , | o m e . , | ||
4 e | 4 e | ||
t | t Page 7 of 22 RBS CYCLE 3 COLR S A ht P L E Rev. O T,ECHNICAL SPECIFICATION 3.2.3 t, POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO The MCPR limits for use in Technical Specification 3.2.3 for MCPR and MCPR are shown in Figures 9 and 10. These values wkre determiEed with the GEMINI methodology and GEXL-PLUS critical power ratio correlation described in GESTAR-II (Reference 1) and are consistent with a Safety Limit MCPR of 1.07. | ||
l i | |||
Page 7 of 22 RBS CYCLE 3 COLR | l i | ||
I | |||
S A ht P L E Rev. O T,ECHNICAL SPECIFICATION 3.2.3 t, POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO | |||
The MCPR limits for use in Technical Specification 3.2.3 for MCPR and MCPR are shown in Figures 9 and 10. These values wkre determiEed with the GEMINI methodology and GEXL-PLUS critical power ratio correlation described in GESTAR-II (Reference 1) and are consistent with a Safety Limit MCPR of 1.07. | |||
l | |||
i | |||
l | |||
w o , . , | w o , . , | ||
-t Page 8 of 22 SAMPLE RBS C CLE 3 COLR | -t Page 8 of 22 SAMPLE RBS C CLE 3 COLR | ||
!? TECHNICAL SPECIFICATION 3.2.4 POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE The LHGR limits for use in Technical Specification 3.2.4 are 14.4 kw/ft for GE8x8EB fuel and 1.3.4 kw/ft for all other 4 fuel. The GE8x8EB fuel consists of fuel types BS322B and BS322C. Core location by fuel type is provided in Figure 11. | !? TECHNICAL SPECIFICATION 3.2.4 POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE The LHGR limits for use in Technical Specification 3.2.4 are 14.4 kw/ft for GE8x8EB fuel and 1.3.4 kw/ft for all other 4 fuel. The GE8x8EB fuel consists of fuel types BS322B and BS322C. Core location by fuel type is provided in Figure 11. | ||
The higher limit for GE8X8EB fuel is proprietary to GE and does not appear in Reference 1. The NRC SER on the GE8B design (Reference 2) recognizes the chango to the LHGR limit, ' | The higher limit for GE8X8EB fuel is proprietary to GE and does not appear in Reference 1. The NRC SER on the GE8B design (Reference 2) recognizes the chango to the LHGR limit, ' | ||
and the proprietary value is found in References 18 and 19 of Reference 2. | and the proprietary value is found in References 18 and 19 of Reference 2. | ||
k . | k . | ||
r"~", . , 'en g . | r"~", . , 'en g . | ||
f, "<?( . | f, "<?( . | ||
pgp};+&I% %; | pgp};+&I% %; | ||
ig g ,g | ig g ,g | ||
*- #r' < | *- #r' < | ||
(l. . Page 9 of 22 l[ S AL M P L E "88CjCLE3COLR I ' | |||
(l. . Page 9 of 22 l[ S AL M P L E "88CjCLE3COLR | |||
I ' | |||
g. | g. | ||
):;; | ):;; | ||
TECHNICAL SPECIFICATION TABLES 3.3.1-2 and 4.3.1.1-1 | TECHNICAL SPECIFICATION TABLES 3.3.1-2 and 4.3.1.1-1 TheLsimulated thermal power time constant for use in Technical Specification Table 3.3.1-2, Footnote ** ist v. | ||
TheLsimulated thermal power time constant for use in Technical Specification Table 3.3.1-2, Footnote ** ist v. | |||
, 6 + 0.6 seconds, o The maximum simulated thermal power time constant for | , 6 + 0.6 seconds, o The maximum simulated thermal power time constant for | ||
~ | ~ | ||
g use in Technical Specification surveillance Table 4.3.1.1-1 | g use in Technical Specification surveillance Table 4.3.1.1-1 is: | ||
is: | |||
i 6.6 seconds | i 6.6 seconds | ||
, See Reference 7 for the basis of the time constant. | , See Reference 7 for the basis of the time constant. | ||
t | t | ||
t r , . | t r , . | ||
c .- .\*; | c .- .\*; | ||
'1 | '1 | ||
:s o ;c p Page 10-of-22 | :s o ;c p Page 10-of-22 | ||
: S A M P L E. RBS CYCLE 3 COLR t- Rev. 0 | : S A M P L E. RBS CYCLE 3 COLR t- Rev. 0 TECHNICAL SPECIFICATION 3.3.6 INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATI'N O The APRM flow biased neutron flux-upscale control rod block trip setpoints for use in Technical Specification . | ||
TECHNICAL SPECIFICATION 3.3.6 | |||
INSTRUMENTATION | |||
CONTROL ROD BLOCK INSTRUMENTATI'N O The APRM flow biased neutron flux-upscale control rod block trip setpoints for use in Technical Specification . | |||
3.3.6, Table 3.3.6-2 are as follows: | 3.3.6, Table 3.3.6-2 are as follows: | ||
TRIP FUNCTION l | TRIP FUNCTION l | ||
| Line 3,092: | Line 1,746: | ||
9 | 9 | ||
ll | ll | ||
;. | ;. | ||
.w# | .w# | ||
,= | ,= | ||
o !. | o !. | ||
Page 11 of 22 t | Page 11 of 22 t SAMPLE RsS CYCLE 3 COLR Rev. O REFERENCES | ||
SAMPLE RsS CYCLE 3 COLR Rev. O | |||
REFERENCES | |||
: 1) NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version). | : 1) NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version). | ||
: 2) ' Letter, C.O. Thomas to J.S. Charnley, " Acceptance for. 6 Referencing of Licensing Topical Report," | : 2) ' Letter, C.O. Thomas to J.S. Charnley, " Acceptance for. 6 Referencing of Licensing Topical Report," | ||
| Line 3,116: | Line 1,762: | ||
1 6)- " Single-Loop Operation Analysis for River Bend Station, Unit 1," NEDO-31441, May 1987. | 1 6)- " Single-Loop Operation Analysis for River Bend Station, Unit 1," NEDO-31441, May 1987. | ||
: 7) Later | : 7) Later | ||
L: . | L: . | ||
Page 12 of 22 S A M P L.E | Page 12 of 22 S A M P L.E ass cycte 3 cota j 13' Rev. 0 gM Ng l | ||
ass cycte 3 cota j 13' Rev. 0 | |||
gM Ng l | |||
t m | t m | ||
g 11 ) \ 1 | g 11 ) \ 1 | ||
^ | ^ | ||
k 10 s. | |||
k | k | ||
*.I L % - | |||
*.I | |||
L % - | |||
%L . | %L . | ||
k , | k , | ||
s | s I. N . | ||
I. N . | |||
7 ,,,mmm ,,mmmmmmm mmmmmmmm mmmmmmmm mmmmmmmmu ; | 7 ,,,mmm ,,mmmmmmm mmmmmmmm mmmmmmmm mmmmmmmmu ; | ||
9 10 . | 9 10 . | ||
30 38 de 50 1 | 30 38 de 50 1 | ||
AVERAGE PLANAR EXPOSURE (GWd/t) -) | AVERAGE PLANAR EXPOSURE (GWd/t) -) | ||
- ~ | - ~ | ||
J l | J l | ||
I riOuRE 1 . | I riOuRE 1 . | ||
MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHOR) vtasus AytitAst Puuwt Exposults sPasitsos4 l | MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHOR) vtasus AytitAst Puuwt Exposults sPasitsos4 l em en a e e | ||
em en a e e | |||
y - - | y - - | ||
i2 o 1-4 . , | i2 o 1-4 . , | ||
g .a,'' | g .a,'' | ||
t | t ENCLOSURE.III CORE OPERATING LIMITS REPORT SUBMITTAL 89-03 BASES REVISION | ||
ENCLOSURE.III CORE OPERATING LIMITS REPORT SUBMITTAL 89-03 BASES REVISION | |||
==SUMMARY== | ==SUMMARY== | ||
Subject (Section) Revision Limiting Safety System Remove reference to the 6 second simulated Settings (B2.0) thermal time constant and .setpoint formula, i | Subject (Section) Revision Limiting Safety System Remove reference to the 6 second simulated Settings (B2.0) thermal time constant and .setpoint formula, i | ||
' Average Planar Linear Heat Provide APLHGR' references to COLR | ' Average Planar Linear Heat Provide APLHGR' references to COLR Generator Rate (3/4.2.1) , | ||
Generator Rate (3/4.2.1) , | |||
Minimum Critical Power Provide MCPR reference to COLR Ratio (B 3/4.2.3) | Minimum Critical Power Provide MCPR reference to COLR Ratio (B 3/4.2.3) | ||
I i | I i | ||
4 | 4 t | ||
t | |||
A ;( | A ;( | ||
;1 t 'T 3 POWER DISTRIBUTION-LXMITS 8ASE5 g -- | ;1 t 'T 3 POWER DISTRIBUTION-LXMITS 8ASE5 g -- | ||
472 MUM CRITICAL 00WER RATIO The'requiredoperatinglimitMCPAs at steady state operating conditions o | 472 MUM CRITICAL 00WER RATIO The'requiredoperatinglimitMCPAs at steady state operating conditions o | ||
| Line 3,196: | Line 1,804: | ||
For any abnormal operating transient analysis, with the initial condition of the reactor being at the steady state operating limit, it is required that the resulting MCPR does not decrease below the Safety Limit MCPR at any time in Specification during the transient assuming instrument trip settings given. | For any abnormal operating transient analysis, with the initial condition of the reactor being at the steady state operating limit, it is required that the resulting MCPR does not decrease below the Safety Limit MCPR at any time in Specification during the transient assuming instrument trip settings given. | ||
2.2. | 2.2. | ||
L To assure that the fuel cladding integrity Safety Limit is not exceeded | L To assure that the fuel cladding integrity Safety Limit is not exceeded during any anticipated abnormal operational transient, the most limiting tran-sients have been analyzed to determine which result in the largest reduction in CRITICAL POWER RATIO CPR . The t flow, increase in'pressur(e an)d power,ype of transients positive reactivity evaluated insertion, were loss o and coolant provided ' temperature decrease. | ||
during any anticipated abnormal operational transient, the most limiting tran-sients have been analyzed to determine which result in the largest reduction in CRITICAL POWER RATIO CPR . The t flow, increase in'pressur(e an)d power,ype of transients positive reactivity evaluated insertion, were loss o and coolant provided ' temperature decrease. | |||
The limiting transient yields the largest delta MCPR. | The limiting transient yields the largest delta MCPR. | ||
in the CULR When added to the Safety Limit MCPR ef 1.07, the required einimum operating - | in the CULR When added to the Safety Limit MCPR ef 1.07, the required einimum operating - | ||
| Line 3,208: | Line 1,814: | ||
The MCPR the correspone,s were calculated such that, for the maximum core the limiting bundle's relative power was adjusted until the MCPR was slightly abcve the Safety Limit. Using this relative bundle power, the MCPRs were calcu-lated at different points along the 10$%-of-rated steam flow control line corresponding to different core flows. The calculated MCPR at a given point of core flow is defined as MCPRf . | The MCPR the correspone,s were calculated such that, for the maximum core the limiting bundle's relative power was adjusted until the MCPR was slightly abcve the Safety Limit. Using this relative bundle power, the MCPRs were calcu-lated at different points along the 10$%-of-rated steam flow control line corresponding to different core flows. The calculated MCPR at a given point of core flow is defined as MCPRf . | ||
RECElVED NOV 301988 RIVER BEND - UNIT 1 8 3/4 2-4 soc Amendment No.12, 31 | RECElVED NOV 301988 RIVER BEND - UNIT 1 8 3/4 2-4 soc Amendment No.12, 31 | ||
L Wy - | L Wy - | ||
l | l | ||
.( . - | .( . - | ||
y Loi LIMITING SAFETY SYSTEM SETTINGS e , | y Loi LIMITING SAFETY SYSTEM SETTINGS e , | ||
; | ; | ||
BASES- l | BASES- l | ||
? | ? | ||
| Line 3,223: | Line 1,825: | ||
, 1 Average Power Ranae Monitor (Continued) | , 1 Average Power Ranae Monitor (Continued) | ||
~ | ~ | ||
, .The'APRM trip system is calibrated using' heat balance data taken during steady state conditions. Fission chambers provide the basic input to the system and therefore the monitors respond directly and quickly to changes due ; | , .The'APRM trip system is calibrated using' heat balance data taken during steady state conditions. Fission chambers provide the basic input to the system and therefore the monitors respond directly and quickly to changes due ; | ||
to transient operation for the case of the Neutron Flux-High setpoint; i.e., 1 for a power increase, the THERMAL POWER of the fuel will he less than that , | to transient operation for the case of the Neutron Flux-High setpoint; i.e., 1 for a power increase, the THERMAL POWER of the fuel will he less than that , | ||
| Line 3,231: | Line 1,831: | ||
.i' - | .i' - | ||
setpoint, a time constant Of S ::: 0.0 :e:er.h is introduced into' the flow ' | setpoint, a time constant Of S ::: 0.0 :e:er.h is introduced into' the flow ' | ||
biased APRM in order to simulate the fuel thermal transient characteristics. | biased APRM in order to simulate the fuel thermal transient characteristics. | ||
A more conservative maximum value is used for the flow biased setpoint as , | A more conservative maximum value is used for the flow biased setpoint as , | ||
d r:- h T dl; 2.2.1-1. - "N w | d r:- h T dl; 2.2.1-1. - "N w | ||
nrovided in the CORE OPERATING LIMITS REPORI' ^ | nrovided in the CORE OPERATING LIMITS REPORI' ^ | ||
| Line 3,241: | Line 1,838: | ||
The APRM setpoints ' fiE'irgiluft'eWp?H'vTdeMiif^foItTi" Safety L Limits and yet allow operating margin that reduces the possibility of unneces-sary shutdown. The flow referenced trip setpoint must be adjusted by the specified formula,i- b;if t::ti - 3.2.0 in order to maintain these margins j when CHFLPD is & to FRTP. e<b e . | The APRM setpoints ' fiE'irgiluft'eWp?H'vTdeMiif^foItTi" Safety L Limits and yet allow operating margin that reduces the possibility of unneces-sary shutdown. The flow referenced trip setpoint must be adjusted by the specified formula,i- b;if t::ti - 3.2.0 in order to maintain these margins j when CHFLPD is & to FRTP. e<b e . | ||
: 3. Reactor Vessel Steam Do[me'P^fe'iislTre4fTdPprovidedintheCOLR.J | : 3. Reactor Vessel Steam Do[me'P^fe'iislTre4fTdPprovidedintheCOLR.J | ||
' High pressure in the nuclear system could cause a rupture to the nuclear | ' High pressure in the nuclear system could cause a rupture to the nuclear | ||
'f system process barrier resulting in the release of fission products. A pressure increase while operating will also tend to increase the power of the reactor by compressing voids thus adding reactivity. The trip will quickly reduce ;he neutron flux, counteracting the pressure incrsase. The trip setting is slightly higher than the operating pressure to permit normal operation without spurious trips. The setting provides for a wide margin to the maximum allowable design pressure and takes into account the location of the pressure measurement-compared to-the highest pressure that occurs in the system during a transient. | 'f system process barrier resulting in the release of fission products. A pressure increase while operating will also tend to increase the power of the reactor by compressing voids thus adding reactivity. The trip will quickly reduce ;he neutron flux, counteracting the pressure incrsase. The trip setting is slightly higher than the operating pressure to permit normal operation without spurious trips. The setting provides for a wide margin to the maximum allowable design pressure and takes into account the location of the pressure measurement-compared to-the highest pressure that occurs in the system during a transient. | ||
This trip setpoint is effective at low power / flow conditions when the turbine i control valve fast closure and turbine stop valve closure trips are bypassed. | |||
This trip setpoint is effective at low power / flow conditions when the turbine i | |||
control valve fast closure and turbine stop valve closure trips are bypassed. | |||
For a load rejection or turbine trip under these conditions, the transient analysis indicated an adequate margin to the thermal hydraulic limit. | For a load rejection or turbine trip under these conditions, the transient analysis indicated an adequate margin to the thermal hydraulic limit. | ||
: 4. Reactor Vessel Water Level-Low i The reactor vessel water level trip setpoint has been used in transient analyses dealing with coolant inventory decrease. The scram setting was chosen far enough below the normal operating level to avoid spurious trips but high | : 4. Reactor Vessel Water Level-Low i The reactor vessel water level trip setpoint has been used in transient analyses dealing with coolant inventory decrease. The scram setting was chosen far enough below the normal operating level to avoid spurious trips but high enough above the fuel to assure that there is adequate protection for the fuel and pressure limits. | ||
l' RIVER BEND - UNIT 1 B 2-7 1 . | |||
l' RIVER BEND - UNIT 1 B 2-7 | |||
1 . | |||
L I | L I | ||
w w , . | w w , . | ||
. + 1 | . + 1 | ||
-. O 3/4.2 POWER DISTRIBUTION LIMITS- | -. O 3/4.2 POWER DISTRIBUTION LIMITS- | ||
^ 1 BASES | ^ 1 BASES | ||
: The specifications of this section assure that the peak cladding temper-ature following the postulated design basis loss-of-coolant accident will not | : The specifications of this section assure that the peak cladding temper-ature following the postulated design basis loss-of-coolant accident will not i | ||
i | |||
excaed the 2200*F limit specified in 10 CFR 50.46. | excaed the 2200*F limit specified in 10 CFR 50.46. | ||
3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE ! | 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE ! | ||
| Line 3,286: | Line 1,869: | ||
- -- - -. , . - - . . . - , . . - . - - . - . . - . , - . . _ . . . . - . . - . ~ . - . . - - . . - | - -- - -. , . - - . . . - , . . - . - - . - . . - . , - . . _ . . . . - . . - . ~ . - . . - - . . - | ||
E 4k -#3 e REC ElV E C q - | E 4k -#3 e REC ElV E C q - | ||
: POWER DISTRIBUTION LIMITS | : POWER DISTRIBUTION LIMITS BASES 6UO j | ||
BASES 6UO j | |||
AVERAGE PLANAR LINEAR' HEAT GENERATION RATE (Continued) | AVERAGE PLANAR LINEAR' HEAT GENERATION RATE (Continued) | ||
: 3. Corrected guide tube thermal resistance. , | : 3. Corrected guide tube thermal resistance. , | ||
: 4. Correct heat capacity of reactor internals heat nodes, | : 4. Correct heat capacity of reactor internals heat nodes, | ||
| Line 3,300: | Line 1,879: | ||
l i | l i | ||
A few of the changes affect the accident calculation irrespective of CCFL. | A few of the changes affect the accident calculation irrespective of CCFL. | ||
These changes are listed below. i | These changes are listed below. i a, ' Input Change l | ||
a, ' Input Change l | |||
l 1 | l 1 | ||
: 1. Break Areas'- The DBA break area was calculated more accurately. | : 1. Break Areas'- The DBA break area was calculated more accurately. | ||
1 I | 1 I | ||
| Line 3,320: | Line 1,894: | ||
.. fuel cladding safety limit or that > 1% plastic strain does not occur in the degraded situation. The scram settTngs and rod block settings are adjusted in accordance with the formula in this specification, when the combination of THERMAL POWER and CMFLPD indicates a peak power distribution, to ensure that L an LHGR transient would not be increased in degraded conditions. | .. fuel cladding safety limit or that > 1% plastic strain does not occur in the degraded situation. The scram settTngs and rod block settings are adjusted in accordance with the formula in this specification, when the combination of THERMAL POWER and CMFLPD indicates a peak power distribution, to ensure that L an LHGR transient would not be increased in degraded conditions. | ||
RIVER BEND - UNIT 1 B 3/4 2-2 Amendment No. 22, II, 33 l | RIVER BEND - UNIT 1 B 3/4 2-2 Amendment No. 22, II, 33 l | ||
l i' | l i' | ||
' s ._ .._. _ . _ _ . _ , _ _ _}} | ' s ._ .._. _ . _ _ . _ , _ _ _}} | ||
Revision as of 16:14, 31 January 2020
| ML19332C852 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/17/1989 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML19332C850 | List: |
| References | |
| NUDOCS 8911290080 | |
| Download: ML19332C852 (53) | |
Text
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- DEFINITIONS .
- SECTION
- 1. 0 DEFINITIONS L . .
PAGE L 1.1 ACTI0N...................^...................................., 1-1 1.2 -AVERAGE PLANAR EXP0SURE........................................ 1-1
- 1. 3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE..................... 1-1
- 1. 4 CHANNEL CALIBRATION............................................ 1-1
- 1. 5 CHANNEL CHECK........................................,,......... 1-1 -
- 1. 6 CHANNEL FUNCTIONAL TEST........................................ 1-1 1.7 CORE ALTERATION................................................ 1-2 '
K 1. 8 CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY................ 1-2 1.9' CDRE OPEPATING LIMITS REPORP (COLR). . . . . . . . . . . ~. . 1.10 pf CRITICAL POWER RATI0............................. . . . . . . . . . . . . ;. . 1-2 1 11 3.x,00SE EQUIVALENT I-131. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . 1-2 1.12 p rf DRYWELL INTEGRITY.............................................. 1-2 1.13 3,M l-AVERAGE DISINTEGRATION ENERGY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1.14 J,.El EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME./........... 1-3 1.15 3 4 4 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE 1-3TINE...... 1.16 3,,3 FRACTION OF LIMITING POWER DENSITY............................. 1-3 1.17 g FRACTION OF RATED THERMAL P0WER................................ 1-3 1.18 g FREQUENCY N0TATION............................................. 1-4 1.19 J< d GASEQUS RADWASTE TREATMENT (OFFGAS) SYSTEM..................... 1-4
- 1. 2o ud IDENTIFIED tEAxAGE. . . . . . . . . . . . . . . . . . . . . . . . . . . . .1-4 .......
1.21 3.e5 ISouTION SYSTEM RESPONSE TIME. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.22 J.af LIMITING CONTROL R' 00 PATTERN. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.23' ),,4 f LINEAR HEAT GENERATION RATE.................................... 1-4 1.24
/ LOGIC SYSTEM FUNCTIONAL TEST... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1-4 RIVER BEND - UNIT 1 i 8911290080 891117 ,
PDR ADOCK 0500
., P
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u b .: :* ,. . o ..- p .: , l' l- INDEX 1-l L DEFINITIONS l SECTION 1 DEFINITIONS (Continued) PAGE
. 1,25 ~
MEMER(S) 0F THE PUB LIC. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1-5 .... 1.26 I g NINIMUM CRITICAL POWER RATI0..................................... 1-5 1.27 g 0FFSITE 00SE CALCULATION MANUAL.................................. 1-5 1.28 1/ OPERA 8 LE - OPERA 81 LITY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1-5 ........ 1.29 CPERATIONAL CONDITION - CON 0! TION................................ 1-5 1.30 1 p m SICS TESTS.................................................... 15 1.31 kS6PRESSUREBOUNDARYLEAKAGE........................................ 1-6 1.32 ~
)#1PRIMARYCONTAINMENTINTEGRITY-FUELHAN0 LING..............."..... 1-6
- 1. 3 > pdf'PRIMARYCONTAINMENTINTEGRITY-0PERATING...........'............. 1-6
- 1.34 poiPROCESSCONTROLPR0 GRAM.......................................... 1-6 1.35 3,M RATED THERMAL P0WER.............................................. 1-7 1.36 % REACTOR PRUTECTION SYSTEM RESPONSE TINE.......................... 1-7 1.37 % REPORTABLE EVENT............................................... . 1-7 1.38 3,,41R000ENSITY...................................................... 1-7 1.39 JAI SECONDARY CONTAINMENT INTEGRITY - FUEL BUILDING. . . . . . . . . . . . . .1-7 ....
1.40 34sSECONDARYCONTAINMENTINTEGRITY-0PERATING...................... 1-7 1.41 .pc SNuT00wN mRGI N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-s 1.42 1 / SITE B00MDARY.................................................... 1-8 1.c p1 50 u 0 l n CAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 1.44 y 50uRCe CuECn..................................................... 1-e 1.45 p44 STAGGERED TEST BASI S. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1-9 1.46 }AS THERMA L P0WE R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1-9 1.47 TINE.............................. 1-9
% TUR8INE BYPASS SYSTEM RESPONSE RIVER BEND - UNIT 1 11 . - - _ . - ~ - - - - _ - , . , , - . - .--,m ~. .,- . . ..__,,. - _ . _ - . _ _ _- . - . - _ . . . . , - , , . . - - , , _ , - . . , . - , . , _ , , - . - - , , , . - - ,
g x . , , . 1 RECElv J
.- SEP 0 S 1988 INDEX SDC LIST OF FIGURES FIGURE TITLE PAGE 3.2.1-1 11 ti. - - Fi = = r iir ei ".;;."...r ^in Rate ( 094)..... ............ .............. 3 -2
- 3. -2 eum Avera anar Linear t' Generation EDELE Tg te (BP85 )......... ................. ...... 3 -3 3.2.1- Maxi Average P1 Linear Heat tion (BP85R82 . . .............. ........... ...... 3/4 2-3.2.1-4 Maximum rage Planar Li Heat'Ge on Rat SRS278).... ............ ............. .. 3/4 2-
.2.1 inum Avera anar Line at Generati Rate (BP 99)....... ............. .......... , 3/4 2-t
- 3) -6 Average ar Linear nerati ate (BP85RB . . ......... .......... .......... /4 2-3.2. - MCPR .............. .......... .......... ....' -9 c 2.0-2 p.............................................. 3/4 2-10 l
3.4.1.1-1 Thermal Power versus Core Flow..................... 3/4 4-3 l 3.4.6.1-1 Minimum Temperature Required Versus Reactor
- Pressure........................................... 3/4 4-24 4.7.4-1 Sample Plan for Snubber Functional Test............ 3/4 7-15 8 3/4 2.3-1 Power Flow Operating Map..................,........ B 3/4 2-6 B 3/4 3-1 Reactor Vessel Water Leve1......................... B 3/4 3-8 8 3/4.4.6-1 Fast Neutron Fluence (E>l MeV) at 1/4 T as a l Function of Service L1fe........................... B 3/4 4-8 l
5.1.1-1 Exclusion Ares..................................... 5-2 5.1.2-1 Low Population Zone................................ 5-3 5.1.3-1 Nap Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents....... 5-4 RIVER BEND - UNIT 1 xxii Amendment No.13,27
,r--,-,ne vas,,,. n.-,w., ,.m. . , . , . , - n,__,ww..,,,,.,,, ,,,.,._,w._,..,_ , _
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- .* g j OCI 201988 ')
'., ,k- DEFINITIONS SDC
%e. ~
- E%?. -
o:'c m The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential,
.- d overlapping or. total channel steps such that the entire channel is tested.
e.8.- jpCORE-ALTERATION , 4 C-O l
@ j 5 t 1.7. CORE ALTERATION shall be the addition, removal, relocation or movement of I
. e' me fuel sources incore instruments or reactivity controls within the reactor '
T $ r.;.3 press,ure-vesse,l with the vessel head removed and fuel in the vessel. Normal 8 j g ,y movement of the SRMs. IRMs, LPRMs, TIPS or special movable detectors is not ma . o considered a C0RE ALTERATION. Suspension of CORE' ALTERATIONS shall not pre- l u d
- 1 clude completion auf the movement of a component to a safe conservative position.
m en - m l 5-{. g CORE MAXINUN FRACTION OF LINITING POWER DENSITY-am.a gy9S 1.8 g The CORE MAXIMUM FRACTION OF LINITING POWER DENSITY (CMFLPD) shall be the s ow > highest value of the FLPD which exists in the core, l 8 .d % INSERT ,
,@ S 7,$ CRITICAL POWER RATIO '
Om
.S * $ 1. 9 The CRITICAL POWER RATIO (CPR) shall be the ratio of.that power in the
.t ,S g ,o assembly.which is calculated by application of the GEXL correlatico to cause ou e some point in the assembly to experience boiling transition, divided by the 8.1 E E actual assembly operating power.
moo y y;gg DOSE EQUIVALENT I-131 c.o o e - A g d ,. 10 DOSE EQUIVALENT I-131 shall be that concentration of I-131, microcuries e wa s per gram, which alone would produce the same thyroid dose as the quantity and 5 -8 m isottvic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
, o g.t The thyroid dose conversion factors used for this calculation shall be those ae si listed in Table III of TID-14844, " Calculation of Distance Factors for Power
,_,s5',*-landTestReactor51tes."
o ,{ DRWELL INTEGRITY - '
,4 o a
$ ggoce5 1.11 DRWELL INTEGRITY shall exist when: .
2 e $ 8' a. All drywell penetrations required to be closed during accident M $@8e conditions are either: o -mu i5 s8c8 1. Capable of being closed by an OPERABLE drywell automatic isola-y o 'd e - tion system, or m mcem M " 0 o .E 2. Closed by at least one manual valve, blind flange, or deactivated
$ $ y &# automatic valve secured in its closed position, except as pro-pa go ,
c . vided in Specification 3.6.4.
,o gem.c a f ,S .d ' b. All drywell equipment hatches are closed and sealed.
l- I.L c.$. E. e :s
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- c. The drywell airlock is in compliance with the requirements of Specification 3.6.2.3.
8B8% l N$hIVERBEND-UNIT 1 1-2 Amendment No. 29
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)
$ 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.1 All AVERAGE PLANAR LINEAR HEAT GENERATION RATES-(APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits the- ia ci te :: 3. 2.1-1, 2. 2.1-2, 0. 2.1- 2, 3. 2.1-4, 0. 2.1- L , 3. 2.1- 0, 0. 2.1-7 The it:it; ef figure; .2.1-1, 0.2.1-2, 3.2.1-3, 3.2.1--4, N eM ? ?.1-9.*
3.2.1-5, 3.2.1-0, 0.2.1 7 ..d 3.2.1-6 shall be reduced to a.value of 0.84 times the two recir era limit n n operation. shown in the . e LHiiits prcn,'i in the COIR APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER. ACTIONI provided in the COLR. With an APLHGR exceeding the limit ef T gere 0. .r l, 3.2.1-2, 3.2.1-3, 3.2.1-4,. 3.2.1-0, 3.2.1-6, 3.2.1-7 or 3.2.1-6, initiate corrective action l within 15 minutes and restore APLHGR to within the required limits within 2 hours or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within i the next 4 hours.
- 2 .
\
l SURVEILLANCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal to or less than the limits determinedyg,Fip;; 2.2.1-1,0.2.1-2,0.2.1-0,0.2.14,0.2.1-5,0.2.1-0,
....,........m
- a. At least once per 24 hours,
- b. Within 12 hours after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and
- c. Initially and at least once per 12 hours when the reacter is operating l with a LIMITING CONTROL R00 PATTERN for APLHGR. )
RECC;yED l di The provisions of Specification 4.0.4 are not applicable. l g 051989 ' 5Dc j
'T;,. 1 ;. ; i.. vi. F ;,. . 3. 2.1-7 .. 4 3. 2.1 0 .. . te :,e used saiy for r;r.;e1 calce!stiaas.
I RIVER BEND - UNIT 1 3/4 2-1 Amendment No. 22, 31, 33 I i l e ,.*-----,..r , , , , - - , , . , . . , , , , , , .,.,.....w.,. -
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. RIVER BEND - UNIT 1 3/42-5 9
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MAR t 41989 FIGURE 3.2.1-7 . I SOC MAXRAAd ANERACE PLANAR IJNEMt MAT (MNDIAll0N RAlt $dAPLMGI) NERSUS AVUtAGE Punan exPosuR - ssans RIVER BEND - UNIT 1 . 3/4 2-68
- Amendment No. 33 l
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'3/4.2.2' APRM SETP0INTS 9
5o LIMITING CON 0! TION FOR OPERATION L
.P 3.2.2. The APRM flow biased simulated thermal power-high scras trip setpoint -
y1 (S) and flow biased neutron flux-upscale control rod block tri go i shall be established'according to fthe4 ollowing relationship /:p setpoint (SR $ e .% . u...s,.a._ . . . . . , Oi ci i Allow alue {[ S 1 (O. + 485)T: _ (0.66W + )T
-S . (0.66W + )T SR8.1 (0 +45%)T
- b. Si e Recircu ton Loop eration Tr Setpoint Allowable alue 1 (0.66W 42.7%)T S1 . 6W + 45. i S., 5 .66W + 36.75 T -- '
_n. - (0.!!" 7 3a. :)T
' S and SoI are-in percent of RATED THERMAL POWER, W = Loop recirculation flow as a percentage of the loop recirculation '
flow which produces a rated core flow of 84.5 million 1bs/hr. T = The ratio of FRACTION OF RATED THERMAL POWER (FRTP) divided by the. CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLPD). T is applied only if .less' than or equal to 1.0. APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to zu of RATED THERMAL POWER. ACTION: With the APRM flow biased simulated thermal power-high seras trip setpoint and/or the flow biased neutron flux-upscale control rod block tri p setpoint less conser- l vative than the value shown in the Allowable Value column' Tor S or S gg, :: Ob: { t' ='=d, initiate correctiv,e action within 15 minutes and adjust 5 and/or S gg to be consistant with the Trip Setpoint value
- within 6 hours or reduce THERMAL POWER to less than 255 of RATED THERMAL POWER within the next 4 hours. l nWith CMFLPD greater than the FRTP, rather than adjusting the APRM.;setpoints, the APRM gain may be adjusted such that the APRM readings are greater than or equal to 1005 times CMFLPD, provided that the adjusted APRM reading does not exceed 100% of RATED THERMAL POWER, and a notice of the adjustment is posted on the reactor control panel.
RECEIVED RIVER BEND - UNIT 1 3/4 2-7 NOV 301988 AmendmentNo.y SDC
,;
. .. . 3
.. . s .q.
? POWER DISTRIBUTION' LIMITS =. '
;
3/4.2.3 MINIMUM CRITICAL POWER RATIO-LIMITING CON 0! TION FOR OPERATION
'3.2.3L The MINIMUM CRITICAL POWER RATIO (MCPR) shall be e than both MCPRf and MCPR limits at indicated core flow and TH
- t:-. 1. T' s i.e 3.0.0 " .g .2.0 2.
;
APPLICABILETY: equal to z!( of RATED THERMAL POWER. OPERATIONAL CONDITION 1, w ' gt{g[:;
. With MCPR less than the appitcable tiCPR Ifnit :h:x h T',...; :.".
; ;
; .0.0 :, initiate corrective a: tion t:ithin 15 sitmtes and restore MCPR to 255 of RATED THERMAL POWER within the next 4 hours.' t'wit 1
SURVEILLANCE REQUIREMENTS 4.2.3. a ..__,MCPR a ,_-- shall.,be ___ . determined
. . . __m to be. equal to or greater than the MCPR limit
..............~......-_..
provided in the CDIR. - p
- a. i At least once per 24 hours,
- b. W
. ithin 12 hours after completion of a TWERMAL POWER increase of at least 155'of RATED THERMAL POWER, and '
c. Initially and at least once per 12 hours when the reactor is operating with a LIMITING Col (TROL R00 PATTERN for MCPR. d. The provisions of Specification 4.0.4 are not applicable. RIVER BEND - UNIT 1 3/4 2-8 e e +,w-- w-,,, ,,r.m., ,,....,n.--- . , , _ . . . . - . _ . . . ~ _ . - . . _ _ - ,,-.n
- m. -_. .y _m_ 44._. ..,m ..._....._._..%.--um..,.._,.._.. ..m_._-_.m_ m... _ _ _ . . . _ . - _ - - - _ _ . . _ . _ - _ _ - _ __ _
t {
.A
'IRANSPER '20 COLR .
i
. 1.7
.+ - j
** : +M* e we >w ; }
m-. _ . l M7 _ . ,
+ +
'I {
- w. I I 1
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** s -
, W:: wCPR,= d -0 6(Cr)+t7 pg , g 6 L - -
n ~*
.1 sr 7 -
~ *
- i
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- l
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b WCPR = -0,6(CT)+t7M e+- -i
- T!. 1 I N1
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1 . . ; 1 I I T: . I I 1 % . I I I . . L III ' I i I .I . I 4. . I I I T I I 'L'~ 1 I WCPR =
-0.761(CF') + 1 &3R :
.":. ! I
.7 . UN ,
L: I - I" 'L. I ' I ' i
- : 1: . A .'E. I I . I I E, r
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=
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o l n' 11 .- t
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- l. y4 J [ [ ' Cl a 3 1 x 4 ,,,[, +
I . . , . 1.0 L . 0 79 40 60 et 100 120 l
- CORE FLOW, 5 OF RATED CORE FLOW i
FIGURE 3.2.3-1 WCPR f RhUtBCNO - UMT1 3/42-9 Amendment No. 33 4
-sn_,-. . _ - . , , _ . , - --,,,,a--.--,,---,,,-,....,,,,,,.-,---n...,,,n..w.,n,
. _ _ , . .~,...._..mm.... . _ . _ . . . . _ . _ . . , _ _ - . . _ . _ , _ _ . . _______...~.~..m.. . - . . . ~ . _ . . _ _ _ . _ . . _ , . - .
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&^ -y '
e 1 .
; AL .
i-.. I }
.{
*1 - ' -
, : +.y p. e4vb4%.
- I i +,.+- m ' # , -- -..
,-+- i'
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I ' w ma ke* M &M l
\ 4upu'
<= >p 1 a.
- y f ., --+
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-+ : ; 7, m
- Wu
= ,
. 4. -w _J.,e -
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> ww 4 4. e r 3,y *-m: ,. ..L :: _
7 p. ;
.y . ~ ..--w % y; 3 , 3 e+
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-,v , '.hd 4 m e .- -q- woJ-r ,h p ionpa
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- P ~~-+= c i M"8 M M Y,+ ^ j t
i;>*("f e * *" Nyp = _y '" ,
;3
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[ t I_.Q 4,_L ' , , I ' i
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1.0 1M 0 at de 80 N 1m THERMAL POWER,# OF RATED THERMAL PO POURE S.R.8-8 4 RIVER 800 - Ull!T 1 3/4 2-10 i n ____-___-______.,,-__-.,,._.-__.-....-_--mm-m--~ - -, .-
POWER O!STRIBUTION LIMITS RECElVED f.' iE
.3/4.2.4 LINEAR HEAT GENERATION RATE gg g 4 g 5, LIMITING CON 0! TION FOR OPERATION di
**4 g 3.2.4 The LINEAR HEAT GENERATION RATE (LHGR) shall not excee _ ^ ' Er/f t fr
- a. O!!"!!:* f;;l ud 13.4 L/fi fei eil ett . f I. ,
APPLICA81LITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25E of RATED THERMAL POWER.
.f i
ACTION: { l With the LHGR of any fuel rod exceeding the lieit, initiate corrective action , within 15 einutes and restore the LHGR to within the limit within 2 hours or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours. l SURVEILLANCE REQUIREMENTS 3 4.2.4 LHGR's shall be determined to be equal to or less than the limit: i
- a. At least once per 24 hours, ,
- b. W' thin 12 houts 4fter completion of a THERMAL POWER increase of et east 155 of RATED THERMAL POWER, and
- c. Initially and at least once per 12 hours when the reactor is operating on a LIMITING CONTROL R00 PATTERN for LHGR.
, , l J
- d. The provisions of Specification 4.0.4 are not applicable. ,
.o .
;
TCc m ^G;ese;; N i ;ml e ii r.. ;;;;;; e.-4 00:200. RIVER BEND - UNIT 1 3/4 2-11 Amendment No. 33 0
, . . _ - - . - , . . _ . _ . _ . . . - - - . . . . . . _ . _ . . . - , . . ..__ .- . _ . _ . . . . _ . . _ . - . _ . . - . . . ~ , . , . . . ~ - . - - , . , . - -
.c #
a TABLE 3.3.1 ' REACTOR PROTECTIL-M SYSTEM RESPONSE TIMES E RESPONSE TIME 7 FUNCTIONAL UNIT (Seconds) E 1. Intermediate Range Monftors.
-e a. Neutron Flux - High '
NA 4 9 b. Inoperative NA
- 2. Average Power Range k nitor*:
- a. Neutron Flux - High, Setdown MA
- b. Flew Biased Sieulated Thermal Power - High <0.09**
- c. Neutron Flux - High <0.09
- d. Inoperative NA i 3. Reactor Vessel Steam Ocme Pressurc - High <0.35 i R
- 4. Reactor Vessel Water level - Low Level 3 71.05 i
- 5. Reactor Vessel Water Lesel - High, Leve? 8 71.05 i T
- 6. Main Steam Line Isniation Valve - C %sure 70.09 l 7. Main Steam Line Radiation - High NA
- 8. Drywell Pressure - High NA
- 9. Scram Discharge Volume Water Level - High l a. Level Transmitter NA '
l b. Float Switches MA i
- 10. Turbine Stop Valve - Closure -<0.06 l 11. Turbine Control Valve Fast Closure, W1ve Trip System
! Oil Pressure - Low <0. 0M i 12. Reactor hde Switch Shutdown Position NA i
- 13. Manual Scram NA I
- Neutron detectors are e.weept irem response time testing. Response time shall be measured
- from the detector output or from the input of the first electronic component in the channel.
l **Not including simulated therati power time constant, 5 1 0.0 x x.-C .g
- #Heasured from start of turbine controt valse fast closure. L_ _ g g g g e
I __ .-. _ _ . ~ . . . _ _ _ . _ _ - _
- ..
~
is within the limits provided in the Com.j ' TABLE 4.3.1.1-1 (Cu tinued) i M N REACTOR PROTECT 10It 5YSTEM lit $TilWElffAT1011 $URVEILLAIICE REQUIREIEllT5 i es i G i " (f) The LPRMs shall be calileated'at least once per 1000 effective full p hours (EFPII)
- using the TIP systee.
j E j Z (g) Calibrate Rosemount tr4 unit :Walpoint at leest once per 31 days. (h) Verify measured drive flow te be less then er equel to established drive flow at the existing flow control valve position. l (1) This calibration _ , ,____ m shall conshr. f Of verifying the simulated themel peuer time constant to be less (j) ihis' f M on li not requires ta ba OPEP.ASLE when the reacter pressure vessel head is removed per Specification 3.10.1. (k) With any control red withdraun. ht applic41e to control rods removed per Specification 3.9.10.1 or 3.9.10.2. (1) This function is not requiswl to be OPERABLE ene DEVIELL IllTEGRITY is not required per Specifica-tion 3.10.1 i w
- 1 (m) Verify the Tusine THElptAL POWER. typass Valves are closed when T6ElBI4L POWER .is greater then er equel to 4GK RATED i w
{ 4 (n) Theinstruments. CHAINIEL FUIICTICIIAL TEST and MML CALIORATICII shall include the tusine first stage pressure (o) The CHAIINEL CALIBItATI0ll shall esclude the fisw' reference transmitters; these transmitters shell.be i calibrated at least once per 18 months. i (p) This period may be extew$ed to the first refueling estage, not to exceed 9-15-87. l 1
- gO i F s n =a +
- i. a. > . .o , e i$ h 1 g c-On m m o
e p
. -r 2 W,
a.-
" 32 e j Om m
{w .IE ,,, y 5 ,E O- w m * [ c, l ? E O l ==
t ! TABLE 3.3.6-2 " CGisTICL A00 SLOCNTION SE1Polnis , 4
, TRIP FIAICTION TRIP SETPOINfc ALLeimBLE VALUE i
;5i 1. ROD PATTENI CONTROL SYSTih
" a. Law Power Setpelat 27.5 i E of RATED TEWIAL POWER 27.517.5E of RATED T10Est4L
, E POWER l 5 b. High Power 5dpoint i 67.95 of RATED TE WthL POER 168.5 of RATED INEstAL POWER ; As provided in the COIR i ; Flow
.. . Blased .m_
. Neut.res Flur. Hoscale* { ~-
i 0. "" : O i 2. "" : 455*- u . . , . . .h.eudstion j L ; " :-.t h --- 1 0. "" e %.T ' i 3."" ; 39.7E* l b. Insperative NA IIA l c. hale >SE of RATED THENthL POER
- -> E of RATED TE NIAL POWER l d. Ileutron Flum - 71p.,cale
~
Start , $ 1 3 of RATES INEst4L PO K R 1 145 of AATED THEMIAL POWER 1:' 3. SOURCE RAIIGE ImMIT985
- a. Detector not full in IIA IIA Y b. 45 scale < 1 x 10 cps 5
< 1.6 x 105 c,,
C c. Insperative ilA R4
- d. Osunscale > 0.7 cps > 0.5 cys**
- 4. INTENEDIATE RAIIGE IEDNITOR$
c_ m a. Detector not, full la NA IIA l gmO b. 15 scale i 108/125 division of full scale 1 110/125 division of full scale l U) { O y0 c. Insperative tiA IIA
> 3/125 divisier of full O __ < d. Beunscale > 5/125 division of full
- 3m scale scale i
- O 4 5. SCRAft DISCNAPGE VOLT 31E I k= a. Water Level-Migh - Li51i602A < 18.00" < 21.12"
! LI$nSeis -i 18.00" -i 21.60"
- g 1 2 6. REACTOR C00LAIIT SYSTOI REC 1000LATI0ii Flohi
! a. 45 scale i IS E of rated flow $ 111% of rated flew i i
- 1 *The Average Power Eange Monitor red him.k fu6ection is varied as a function of recirculation loop flow (w).
M i The trip setting c! this fonctice e st be maintained in accordance with Specification 3.2.2'q j U **Provided signal to colse ratio is > 2. etherwise setpoint of 3 cps and allowable 1.8 cys. l. k r
> ard limits provided in the GXR. "
4 kv
DESIGN FEATURES
. m =
0 5.3 REACTOR CORE NIAN l SDC ' r= = = : = - l
.1 he reac core s 1 cont n 624 f asse tes. ch ass ly cons ts of zi onium a ey fuel nd water rods ar nged i a nomi 1 8x8 .
arr y. The el rods ntain anium di ide f peller with tive len hs rally nging be en 1 and 150 hes. hose f- asse ies are imited those t t have een anal ed wit RC app ved c es and hods , and ha been s to c ly with 11 of crite a in latest pproved revi on of GE AR (NED 24011-P- -US). k ONTROL ASSE IES > [ 5.3.2 he te or core all e tain 14 cont of crucif rod ass lies, ach con sting ' array stain ss stee tubes urrounde by a er iform aped b' s inless s eel shea . Ea tube s 11 co in 143. inches boron arbide l 4 C X::. , 5.4 REACTOR COOLANT SYSTEN
/ ,
0ESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
- a. In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal tiegradation pursuant to .he a appitcable Surveillance Requirements, a
h, For a pressure ef:
- 1. 1250 psig ca the suctien ofde of the recireuhtion pump. <
- 2. 165C psig from the mircuhtfort pump discharge to tre outlet !
side of the discharge shutaff valve.- p 3. 1550 psig free the discharge shutoff n1ve to the jnt pumps. l
- c. For a temperature of 57 P F l VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 16.000 cubic feet.
l RIVER BEND - UNIT 1 5-5 Amendment No.33 1
l'; c- .L , n-7 ~
- g. , p l
> i i.
-l
. Replacement paragraphs for Technical Specifications 5.3.1, lum ASSDELIES and 5.3.2, CWra0L JOD ASSDeLIES. i MJEL ASSDELIES ,
t 5.3.1' %e reactor-shall contain 624 fuel assemblies. Each assenbly shall consist of.. a matrix of Zircalloy clad fuel rods with an initial camposition of slightly enriched [_ uranium dioxide (002 ) as fuel material. - Fuel assenblies shall be Imited to those ; l- fuel designs apptwed by the NIC Staff for use in WR's. l
- . 6 i
i 0:NTROL RCD ASSDELIES r 5.3.2 2e reactor oore shall contain 145 cruciform shaped control rod assemblies. ; We control material shall be boron carbide powder (B4C ) ' and/or hafniunt netal. %e '
- r. control rod assemblies shall be full length. ,
a t [ t (
;
U. . h i h I e
. . .v ,-
~
ADMINISTRATIVE CONTROLS SEMIANNUAL EFFLUENT RELEASE REPORT (Continued) - I to MEMERS OF THE PUBLIC due to their activities inside the SITE Si (Figure 5.1.3) during the report period. All assumptions used in making these ' ciuded in these reports. assessments (i.e., specific activity, exposure time and! in accordance with the methodology and p,arameters of the 0FFS ; TION MANUAL (ODCM). The Semiannual Radioactive Effluent Release Report to be submitted 60 days i January 1 of each year shall also include an assessment of radiation doses to the likely nearby most exposed uranium fuel c ME M ER OF THE PUBLIC from reactor releases and other ; and direct radiation)ycle sources (including doses from primary effluent pathways ' for the previous calendar year to show conformance with i 40 CFR Operation. Part 190 Environmental Radiation Protection Standards for N J and gsseous offluents are given in Regulatory Guide 1.109,il 1 The Semiannual Radioactive Effluent Release Reports shall include a list and 1 description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period. { l a The Semiannual Radioactive Effluent Release Reports shall include any changes '
) made= during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the 00CM, as well as a listing of new locations for dose calculations and/or environmental.
cation 3.12.2 monitoring identified by the land use census pursuant to Specifi- ;i gPECIALREPORTS C. 9. 2 Special reports shall be submitted in the following manner: , i J. Spnial reports shall be submitted to the U.S. Nuclear Regulatory jn Commission, Document Control Desk, Washington, DC 205SS, with 6 - i (, copy to the Regional Office of the NRC and a copy to the NRC Resi- , 1 dent Inspector, within the time period specified for each report. i h b. Spacial reports in reperd to C6rbicula will be submitted to the NRC g y ')) within "s0 dsys of identifit.ation of infestation. In setordance with
){s 3
g the settlevent agreement dated October 10, 1984, these reports shall describe the level of. infestation, affected systems and ceasures taken l g to prevent further infestation. l l 6.10 RECORD RETENTION
^ '
6.10.1 L l-Code of Federal Regulations, the following records shall be r least the minimum period indicated. p i 6.10.2 l- The following records shall be retained for at least 5 years: l
- a. 1
[ Records power and logs of unit operation covering time interval at each level. RECEIVED RIVER BEND - UNIT 1 6-19 DEC 151987 ^**"d*'"t * *17 8QC
..--.,,.m..
CORE OPERATING LIMITS REPORT 6.9.3.1 Core operating limits shall be established prior to startup from each reload cycle, or prior to any remaining portion of a reload cycle, for the following: E
- a. The AVERAGE POWER RANGE MONITOR (APRM) setpoints for Specifications 2.2.1, 3.2.2 and 3.3.6.
- b. The AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGR) for Specification 3.2.1.
- c. The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.3. ;
! d. The LINEAR HEAT GENERATION RATE (LHGR) of Specification 3.2.4. , e, The REACTOR PROTECTION SYSTEM (RPS) response time for APRM thermal time constant for Specification 3.3.1. , and shall be documented in the CORE OPERATING LIMITS REPORT (COLR). , 6.9.3.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in ti.e NEDE-24011-P-A, " General Electric Sfandard
, Application for Reactor Fuel" (latest approved version).
6.9.3.3 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-nydraulic limits, ECCS limits and nuclear transient / accident analysis limits) of the safety enalysis are met. G.9.3.4 The Conf OPERATING LIMITS RCFORT., including any mid eycle revision or supplements shall be providec, upon issuance for each reload cycle, to - the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
' Pcga 13 of 22 i RBS CYCLE 3 COLRi RW. 0 SAMPLE.
13 I I
,, gs'a mma pM g'k
/ \ j a
12 I/ / I
%k 1
s& i IE k - lg 11 g k : r* s 4 :
<8 1. (, -
g 1-l ll g% g 85 4 ' g
. a 8 l
;
I ? I m u m m m mm m m m m mm m m m m m m m m m m m mmm mm mm m mmmmlemmel 0 10 . 20 30 40 00 AVERAGE PLANA 9 EXPOSURE (GWd/t) l i I FIGURE 2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATIGN MATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE BP85RB163 Ii I L
- \
j
. . . . _ . . . . _ . . _ . - - _ . . .~
i Pago 14 of 22 I SAMPLE RBS CYCLE 3 COLR] Rev. 0 ' l 13 i m 12 L 7 j j
;
as
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i A ' L 11 g
%g .
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10 ,
> g ul
=
\
b I ' . ,-
. .....a...s ................... ..
10 20 30 40 50 - 0. AVERAGE PLANAR EXPOSURE (GWd/t) . 9
. l L
FIGURE 3 L !- MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLhGR) VERSUS AVERAGE PLANAR EXPOSURE RP85R8248 i' . o
. ~- ,---,.-,,,...,.,-----,,,,v-,-- -.-,r,--,.,ew,w,,,,,,e owe..r---,ve--;c,e-,,-,-w-w, av-,-- ,,v.,+-,- --e ,,- . - , - , , ,y
Paga 15 of 22 l RBS CYCLE 3 COLR'
- S A M P t. E Rev. 0 13 e=.. ...,'e i
)/a m,
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%g\
- ;
i
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l i L i
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o to ao su 40 2 l l - AVOLACE FLANAR EXPoruRE (GWd/t)
- l. .
FIGURE 4 MAXIMUM AWRAGE PLANAR UNEAR HEAT GENERATION RATE (MAPLHGR) W.RSUS AVERAGE PLANAR EXPOSURE - SPSSRS278 0 ___________.__.s-.____. ,_ _ _ _ _ - . . . .__,_,.,._,,_._.._,,,._,.,_,.,_,ym.,_. _ , . . , , , , , , , , , , _ , , _ , . , . , . _ . _ _ . , , _ . _ _ , _ _ , , ,
- -_ ~ - . . .. - - - . - . . . . . . . _ - . . - - - . . - - - . - . - - - - . . .
Page 16 or 22 S A M P t. E ass cycts a cota
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I L . FIGURE 5 MAXIWUW AVERAGE PLANAR UNEAR MCAT GENERATION RATE (MAPLHOR) VERSUS AWGE PLANAR EXPOSURE - BPSSRS299 ,m. _
,- --..w,-,~,. , , , . - , . - - - ~ . . _ - . . . . . . ~ , . . , . . - . . . , , , - - - - , , - - - , . . - - - - , , , . - , - - , , . - , . , , , , , ,-,,-,------...,-,n.
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Page 17 of 22
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l 2 DDDDDDDD ! IIIIIIIl , , 1 3 5 7 91113151719212325272931233537384143454749515355 Fu.1 Typ. 1 A = 383228 E = SP85RB248 8 = 88322C F = SP85RS299
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, ENCLOSURE II CORE' OPERATING LIMITS REPORT SUBMITTAL I 89-03 !
Page 1 of 22 i RBS CYCLE 3 COLR' l' Rev. 0 SAMPLE , RIVER BEND STATION, OYCLE 3 !
;
CORE OPERATING LIMITS REPORT (COLR) i I OCTOBER 1989 j l 1 , CONTROLLED COPY 1 I l PREPARED BY DATE: Supervisor, Core Analysis l i River Bend Nuclear Station j l l l l A APPROVED BY: DATE: ' Manager, Engineering River Bend Nuclear Station l 1 APPROVED -BY : DATE: l Facilities Review Committee l River Bend Nuclear Station ; l l APPROVED BY: DATE: Nuclear Review Board ) River Bend Nuclear Station i l l l l l 1
4 . . Page 2 of 22 RBS CYCLE 3 COLR SAMPLE Rev. o LIST OF EFFECTIVE PAGES Page (s) Revision 1-22 0 lr l l l
p ea y+. Page 3 of 22 Ras CYCtE 3 Cota SAMPLE Rev. O INTRODUCTION AND
SUMMARY
o This report provides the values of the Average Power Range Monitor (APRM) scram and rod block setpoints, the 3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) limits, the core flow dependent MINIMUM CRITICAL POWER RATIO (MCPR) limits, MCPR , the thermal power dependent MCPR limits MCPR and the LINEkR HEAT GENERATION RATE (LHGR) limits for River Bend Station, Cycle 3 as required by Technical Specification 6.9.3.1. 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. f i
w L'. , Page 4 of 22 L SAMPLE RBS CYCLE 3 COLR Rev. 0 l TECilNICAL SPECIFICATION 2.2.1 LIMITING SAFETY SYSTEM SETTINGS REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS The APRM flow biased simulated thermal power-high scram trip setpoints for use in Technical Specification 2.2.1, Table 2.2.1-1 are as follows: ALLOWABLE I FUNCTIONAL UNIT TRIP SETPOINT VALUES
- 2. Average Power Range Monitort
- b. Flow Biased Simulated Thermal Powcr-High '
- 1) Two Recirculation 0.66W+48% 0.66W+51%
Loop Operation
- 2) Single Recircula- 0.66W+42.7% 0.66W+45.7%
tion Loop Operation The relationships for two recirculation loop operation are taken from Reference 4. The relationships for single recirculation loop operation are taken from Reference 5, which is based on Reference 6. l l q l
s= c e oe ,
-c Page 5 of 22 RBS CYCLE 3 COLR Rev. O SAMPLE t
TECHNICAL SPECIFICATION 3.2.1 i POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINFAR HEAT GENERATION RATE The limiting APLHGR value for'the most limiting lattice > (excluding natural uranium) of each fuel type as.a function of AVERAGE PLANAR EXPOSURE is given in Figures 1, 2, 3, 4, 5, 6, 7, and 8. These values were determined with the SAFE /REFLOOD LOCA methodology described in GESTAR-II (Reference 3). Core location by fuel type is provided in Figure 11, which is taken from Reference 3. These figures are used if alternate. calculations are required. The limits of these figures shall be reduced to a value of 0.84 times the two recirculation loop operation limit when in single loop operation (Reference 6). P e I I l l l l 1
f( c i Page 6 of 22 RBS CYCLE 3 COLR SAMPLE Rev. 0 , TECHNICAL SPECIFICATION 3.2.2 POWER DISTRIBUTION LIMITS ' t APRM SETPOINTS ' L The APRM flow biased simulated thermal power-high scram trip setpoint (S) and flow biased neutron flux-upscale R fr use in Technical control rod block trip setpoint-(SSpecification 3.2.2 are as follows:B) , j a) Two Recirculation Loop Operation y ' Trip Setpoint, Allowable Value S (0.66W + 48%)T S (0.66W + Sl%)T , S RB (0.66W + 42%)T S RB (0.66W + 4 5%) T b) Sing)e Recirculation Loop Operation Trip Setpoint Allowable Value S (0.66W + 42.7%)T S (0.66W + 45.7%)T S RB (0. 66W + 36.7%) T S RB ( . 6W + 39.70 T where: S and S RB are in percent of RATED THERMAL POWER, W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated core flow of 84.5 million lbs/hr. T = The ratio of FRACTION OF RATED THERMAL POWER (FRTP) divided by the CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLPD). T is applied only if less than or equal to 1.0. The relationships for two recirculation loop operation are taken from Reference 4. The relationships for single recirculation loop- operation are taken from Reference 5, which is based on Reference 6.
I',' o m e . , 4 e t Page 7 of 22 RBS CYCLE 3 COLR S A ht P L E Rev. O T,ECHNICAL SPECIFICATION 3.2.3 t, POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO The MCPR limits for use in Technical Specification 3.2.3 for MCPR and MCPR are shown in Figures 9 and 10. These values wkre determiEed with the GEMINI methodology and GEXL-PLUS critical power ratio correlation described in GESTAR-II (Reference 1) and are consistent with a Safety Limit MCPR of 1.07. l i l i I
w o , . ,
-t Page 8 of 22 SAMPLE RBS C CLE 3 COLR
!? TECHNICAL SPECIFICATION 3.2.4 POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE The LHGR limits for use in Technical Specification 3.2.4 are 14.4 kw/ft for GE8x8EB fuel and 1.3.4 kw/ft for all other 4 fuel. The GE8x8EB fuel consists of fuel types BS322B and BS322C. Core location by fuel type is provided in Figure 11. The higher limit for GE8X8EB fuel is proprietary to GE and does not appear in Reference 1. The NRC SER on the GE8B design (Reference 2) recognizes the chango to the LHGR limit, ' and the proprietary value is found in References 18 and 19 of Reference 2. k .
r"~", . , 'en g . f, "<?( . pgp};+&I% %; ig g ,g
*- #r' <
(l. . Page 9 of 22 l[ S AL M P L E "88CjCLE3COLR I ' g. ):;; TECHNICAL SPECIFICATION TABLES 3.3.1-2 and 4.3.1.1-1 TheLsimulated thermal power time constant for use in Technical Specification Table 3.3.1-2, Footnote ** ist v.
, 6 + 0.6 seconds, o The maximum simulated thermal power time constant for
~
g use in Technical Specification surveillance Table 4.3.1.1-1 is: i 6.6 seconds
, See Reference 7 for the basis of the time constant.
t
t r , . c .- .\*;
'1
- s o ;c p Page 10-of-22
- S A M P L E. RBS CYCLE 3 COLR t- Rev. 0 TECHNICAL SPECIFICATION 3.3.6 INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATI'N O The APRM flow biased neutron flux-upscale control rod block trip setpoints for use in Technical Specification .
3.3.6, Table 3.3.6-2 are as follows: TRIP FUNCTION l
- 2. APRM
- a. Flow Biased Neutron Flux Upscale *'
TRIP SETPOINT ALLOWABLE' VAL E
- 1. Two Recirculation' O.66W+42%* 0.66W+45%*
Loop' Operation
- 2. One Recirculation 0.66W+36.7%* 0.66W+39.7%*
Loop Operation
- The Average Power Range Mo'nitor rod block function is varied as a function of recirculation loop flow (W). The trip setting of- this' function must be maintained ~in accordance with Specification 3.2.2.
The relationships for two recirculation loop operation ; are taken from Reference 4. The relationships for single recirculation loop operation are taken from Reference 5, which is based on Reference 6. 9
ll
;.
.w#
,=
o !. Page 11 of 22 t SAMPLE RsS CYCLE 3 COLR Rev. O REFERENCES
- 1) NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version).
- 2) ' Letter, C.O. Thomas to J.S. Charnley, " Acceptance for. 6 Referencing of Licensing Topical Report,"
NEDE-24011-P-A-6, Amendment 10, General Electric Standard Application for Reload Fuel, May 28, 1985. 3)' Document 23A5934, Revision 0, " Supplemental Reload Licensing Submittal for River Bend Station Reload 2, Cycle 3," October'1988.
- 4) GE Design Spec Data Sheet for. Neutron Monitoring System,
-Revision 1, Document Number 22A3739AR, April 1984. ,
t
'5) Engineering Calculation G13.18.6.l*03-0, "APRM Flow Biased ' Scram and Rod Block Setpoints for Single Recirc Loop Operation."-
1 6)- " Single-Loop Operation Analysis for River Bend Station, Unit 1," NEDO-31441, May 1987.
- 7) Later
L: . Page 12 of 22 S A M P L.E ass cycte 3 cota j 13' Rev. 0 gM Ng l t m g 11 ) \ 1
^
k 10 s. k
*.I L % -
%L .
k , s I. N . 7 ,,,mmm ,,mmmmmmm mmmmmmmm mmmmmmmm mmmmmmmmu ; 9 10 . 30 38 de 50 1 AVERAGE PLANAR EXPOSURE (GWd/t) -)
- ~
J l I riOuRE 1 . MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHOR) vtasus AytitAst Puuwt Exposults sPasitsos4 l em en a e e
y - - i2 o 1-4 . , g .a, t ENCLOSURE.III CORE OPERATING LIMITS REPORT SUBMITTAL 89-03 BASES REVISION
SUMMARY
Subject (Section) Revision Limiting Safety System Remove reference to the 6 second simulated Settings (B2.0) thermal time constant and .setpoint formula, i
' Average Planar Linear Heat Provide APLHGR' references to COLR Generator Rate (3/4.2.1) ,
Minimum Critical Power Provide MCPR reference to COLR Ratio (B 3/4.2.3) I i 4 t
A ;(
;1 t 'T 3 POWER DISTRIBUTION-LXMITS 8ASE5 g --
472 MUM CRITICAL 00WER RATIO The'requiredoperatinglimitMCPAs at steady state operating conditions o is
.-+ es !; :ified '- 5;;;ifi;;t.;a 3.2.4 are derived from the established fuel i
. 6perational cladding integrity Safety Limit MCPR cf t.07 and an analysis of abnoratal transients.
For any abnormal operating transient analysis, with the initial condition of the reactor being at the steady state operating limit, it is required that the resulting MCPR does not decrease below the Safety Limit MCPR at any time in Specification during the transient assuming instrument trip settings given. 2.2. L To assure that the fuel cladding integrity Safety Limit is not exceeded during any anticipated abnormal operational transient, the most limiting tran-sients have been analyzed to determine which result in the largest reduction in CRITICAL POWER RATIO CPR . The t flow, increase in'pressur(e an)d power,ype of transients positive reactivity evaluated insertion, were loss o and coolant provided ' temperature decrease. The limiting transient yields the largest delta MCPR. in the CULR When added to the Safety Limit MCPR ef 1.07, the required einimum operating - limit MCPR e
- Speci*fectie 3.2.2 is obtained-::: i: pr;;; t:d in fip.:r; 3.2.!-1.
Analysisoftransientsoccurringduringsing13recirculationloopoperation indicates that the maximum operating limit MCPR will be bounded by the limits in Sp- !f t::ti-- 3.2.-3 t regions of plant operation,The power-flow map of Figure B 3/4 2.3-1 shows typical o COLR The evaluation of a given tranft ns with the system initial param-eters identified in Reference 2 that are input to a GE core dynamic behavior transient computer program. in Reference 2. The principal The codes used to evaluate transients are described MCPR caused by transient, result of this evaluation is the reduction in provided in the COLR The purpose of the MCPRf and MCPR define operating limits at other than , rated core flow and power conditions. At . lass than 1005 of rated flow and power the required MCPR is the larger value of the MCPR f and MCPR, at the existing core flow and power state. The MCPRy s are established to protect the core from inadvertent core flow increases such that the 99.95 MCPR limit requirement can be assured. The MCPR the correspone,s were calculated such that, for the maximum core the limiting bundle's relative power was adjusted until the MCPR was slightly abcve the Safety Limit. Using this relative bundle power, the MCPRs were calcu-lated at different points along the 10$%-of-rated steam flow control line corresponding to different core flows. The calculated MCPR at a given point of core flow is defined as MCPRf . RECElVED NOV 301988 RIVER BEND - UNIT 1 8 3/4 2-4 soc Amendment No.12, 31
L Wy - l
.( . -
y Loi LIMITING SAFETY SYSTEM SETTINGS e ,
;
BASES- l
?
REACTOR PROTECTI0ft SYSTEM INSTRUMENTATION SETPOINTS (Continued)
, 1 Average Power Ranae Monitor (Continued)
~
, .The'APRM trip system is calibrated using' heat balance data taken during steady state conditions. Fission chambers provide the basic input to the system and therefore the monitors respond directly and quickly to changes due ;
to transient operation for the case of the Neutron Flux-High setpoint; i.e., 1 for a power increase, the THERMAL POWER of the fuel will he less than that , indicated by -the neutron flux due to the time constants of the heat transfer ' associated with the fuel. For the Flow Biased Simulated Thermal-Power-High
.i' -
setpoint, a time constant Of S ::: 0.0 :e:er.h is introduced into' the flow ' biased APRM in order to simulate the fuel thermal transient characteristics. A more conservative maximum value is used for the flow biased setpoint as , d r:- h T dl; 2.2.1-1. - "N w nrovided in the CORE OPERATING LIMITS REPORI' ^ (COLR) . ) The APRM setpoints ' fiE'irgiluft'eWp?H'vTdeMiif^foItTi" Safety L Limits and yet allow operating margin that reduces the possibility of unneces-sary shutdown. The flow referenced trip setpoint must be adjusted by the specified formula,i- b;if t::ti - 3.2.0 in order to maintain these margins j when CHFLPD is & to FRTP. e 1% plastic strain does not occur in the degraded situation. The scram settTngs and rod block settings are adjusted in accordance with the formula in this specification, when the combination of THERMAL POWER and CMFLPD indicates a peak power distribution, to ensure that L an LHGR transient would not be increased in degraded conditions. RIVER BEND - UNIT 1 B 3/4 2-2 Amendment No. 22, II, 33 l l i' ' s ._ .._. _ . _ _ . _ , _ _ _}}