ML20084R861
| ML20084R861 | |
| Person / Time | |
|---|---|
| Site: | Byron, 05000000 |
| Issue date: | 04/27/1984 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20084R841 | List: |
| References | |
| BZP-380-A8, NUDOCS 8405230291 | |
| Download: ML20084R861 (25) | |
Text
-_ .-.
)
BzP 380-A8 Revision 1 1 -
SUGGESTED SAMPLING LOCATIONS SCENARIO SAMPLPlG LOCATIONS (S) SAMPLE PROCEDURES (S) COMMENTS .,
Small break LOCA Rx Power >1% RCS Hot Leg BZP 380-12/ ,
Loop 1 1(2)PS9351 A or Diluted R/C and - '
Loop 3 1(2)PS93518 BZP 380-15/
R/C Stripped Gas ,,
Alternate Point n RCS Pressurizer Same as Hot Leg '
1(2)PS93508 Sampling Procedures and Containment BZP 380-18 If Containment atmosphere process monitor .
Atmosphere BCP 800-7 1(2)RE-PR0ll indication is increased or is increasing.
' ~
Rx Power <l% RCS Hot Leg Same as Hot Leg If PCS pressurized and RC pumps running.
Loop 1 1(2)PS9351A Sampling procedures Loop 3 1(2)PS9351B RHR 1(2)PS9353A Same as Hot Leg If RCS on RHR
, 1:2)PS93538 o Sampling Procedures l
Alternate point l
j RCS Pressurizer Same as Hot Leg 1(2)PS9350B Sampling Procedures l
l i
i APPROVED APR 271984 8405230291 040504 -la-(3956P) PDR ADOCK 05000 B. O. S. R.
BZP 380-A8 R vision 1 ,
SCENARIO SAMPLING LOCATIONS (S) SAMPLE PROCEDURES (S) COMMENTS
'Large break LOCA s
} Rx Power >1% Containment sump NONE i 1(2)PS156 i and i Containment BZP 380-18 I Atmosphere BCP 800-7 l and RCS Hot Leg BZP 380-12/ If Containment Sump is providing cooling to Loop 1 1(2)PS9351A or Diluted R/C and core, do not include hot leg sample activity l Loop 2 1(2)PS9351B BXP 380-15 in damage assessment calculations.
R/C Stripped Gas Rx Power <1% Containment BZP 380-18 Atmosphere BCP 800-7 !
and .
Containment Sump NONE Provided Containment Sump supplying core 1(2)PS156 cooling j or
- RHR System
1(2)PS9353B or RCS Hot Leg Loop 1 1(2)PS9351A or BZP 380-12, Diluted R/C Loop 2 1(2)PS9351B BZP 380-15 R/C Stripped )
Gas IB
'1 l l l , ,
APPROVED APR 2 71984 -
. . . R.
(3956P)
BZP 380-A8 R: vision 1 ,
SCENARIO SAMPLING LOCATIONS (S) , SAMPLE PROCEDURES (S) COMMENTS Steam Line -RCS Hot Leg BZP 380-12/D11uted Break 1(2)PS9351A R/C and 1(2)PS9351B BZP 380-15 R/C or Stripped Gas Alternate Point RCS Pressurizer Same as above 1(2)PS9350B and
. Containment BZP 380-18 If Containment atmosphere process monitor Atmosphere BCP 800-7 1(2)RE-PR011 has increased or is increasing.
Steam Generator RCS Hot Leg BZP 380-12 Tube Rupture 1(2)PS9351A Diluted R/C and i 1(2)PS9351B BZP 380-15 R/C Stripped Gas Steam generator NONE .
blowdown Main Steam NONE J
Containment BZP 380-18 If Containment atmosphere process monitor 1 Atmosphere BZP 800-7 1(2)RE-PR0ll has increased or is increasing.
I t
i
+
l 1
APPROVED APR 2 71984 l (3956P)
BZP 380-A8 Revision 1 ,
i i SCENARIO SAMPLING LOCATIONS (S) SAMPLE PROCEDURES (S) COlmENTS ..
i I Indication of Centainment Sump None , When coupled with excessive RCS leakage.
Significant Containment 1(2)PS156 Stmp Inventory and Containment BZP 380-18 If Containment atmosphere process monitor Atmosphere BCP 800-7 1(2)RE-PR011 indications have increased or are increasing.
4 Containment Bldg Containment BZP 380-18 When coupled with reactor cooling anomalies or 1
Ridiation Monitor Atmosphere BCP 800-7 excessive RCS leakage Alarm and .
Containment Sump NONE When coupled with reactor cooling anomalies or excessive RCS leakage.
- l. Safety Injection RCS Hot Leg BZP 380-12/ .
! Actuated Loop 1 1(2)PS9351A or Diluted R/C and Loop 2 1(2)PS9351B BZP 380-15/
R/C Stripped Gas .
. Alternate point
! RCS Pressurizer Same as Hot Leg 1(2)PS9350B Sampling Procedures
. Indication of RCS Hot Leg BZP 380-12/
High Radiaton Loop 1 1(2)PS9351A or Diluted R/C and Level inRCS Loop 3 1(2)PS9351B BZP 380-15/
j R/C Stripped Gas
} Alternate Point Same as Hot Leg RCS Pressurizer Sampling procedures i i 1(2)PS9350B i !
4 l
APPROVED APR 2 71984 i
1 (3956P) B.O.S.R.
F .
l
- 3Z? 380-A8 Revision 1 700 -
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Specif ic Gravity SPECIFIC GRAVITY OF WATER V5 TEMPERATURE APPROVED APR 2 71984 Page 2 B. O. S. R.
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CCNTAINM BT HYOROGEN CONCS TRATION SASED CN -
IIECMIUM WATER REACTION APPROVED APR 271984 B. O. S. R.
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RELEASED OF KR-87 APPROVED APR 2 71984
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INVENTORY itELATIONSHIP OF % CLAD DAMAGE WITH RELEASED OF I-131 WITR SPIKING APPROVED APR 2 71084 P'S* 'd a. o. s. a.
3ZP 380-AG Rsvision 1 c.;
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REl.ATIONSHIP OF : CLAD DAMAGE WITH ' INVENTORY RELEASED OF I-132 APPROVED APR 2 71984 B. O. S. R. 1 Page 4e
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RELATIONSHIP OF % CLAD DAMAGE WITH % INVENTO RELEASED OF I-135 APPROVED APR 2 71984 B. O. S. R.
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RELATIONSHIP OF % FUEL OVERT'L".PERATUR INVENTQRY RELEASG OF XE, XR. I. C5 t j
APPROVED ,
APR 271984
\
Page Sa B.O.S.R.
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RELATIONSHIP OF 1 FUE. ObiWGATtJRE WITH 1 INVENTORY RELEASED OF SA, SR APPROVED APR 271984
- 8. O. S. R.
Page 5b MSM hN' 4*p_a gagg ,
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RELATIONSHIP OF : FUEL MELT WITH % INVENTORY l RELE AS ED O F XE o r KR o r I or CS or TE APPROVED APR 271984 B. O. S. R.
Page 6a )
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RELATIONSHI? 0F % FUEL MELT WITH % INVENTORY
- RELEASED OF PR APPROVED
< APR 271984 Page 6e B.O.S.R.
j
j BZP 380-A8 i Revision 1 j .
j CHARACTERISTICS OF CATEGORIES OF FUEL DAMAGE PERCENT CONTAlletENT AND TYPE HIGH RANGE CORE EXIT HYDROGEN CORE OF FISSION FISSION ARE THERMOCCUPLE CORE MONITOR DAMAGE PRODUCTS PRODUCT HONITOR, READINGS UNCOVERED 1(2) AI PS 343 or 344 CATEGORY RELEASED RATIO R/hr* (DBG F) (YES/NO) (VOL % Hy)
No Clad Damage Kr-87<1X10-3 Kr-87=0.022 <750 No Uncovery Negligible Xe-133<1X10-3 I-133=0.71 1-131<1X10-3 I-133<1X10-3 0-50% Kr-87 10-3-0.1 Kr-87=0.022 0-97 750-1300 Core <6%
Clad Damage Xe-133 10-3-0.1 1-133=0.71 Uncovery I-131 10-3-0.3 I-133 10-3_o,1 4 50-100% Kr-87 0.1-0.2 Kr-87=0.022 97-194 1300-1650 Core 6%-11%
Clad Damage Xe-133 0.1-0.2 I-133=0.71 Uncovery i
I-131 0.3-0.5 I-133 0.1-0.2 0-50% Fuel Xe. Kr, Cs. I Kr-87=0.22 194-25,000 >1.650 Core 6%-11%
Pellet 1-20 I-133=2.1 Uncovery i Overtemperature Sr. Ba 0-0.4 50-100% Fuel Xe.Kr.Cs,I Kr-87=0.22 2.5E4-5.0E4 >l.650 Core 6%-11%
- Pellet 20-40 I-133-2.1 Uncovery Overtemperature Sr. Ba 0.4-0.8 4
0-50% Fuel Xe, Kr. Cs. I Kr-87=0.22 5.0E4-8.5E4 >1,650 Core 6%-11%
Melt 40-70 I-133=2.1 Uncovery Sr. Ba 0.2-0.8 i
Pr. Rb, 0.1-0.8 l l
! 50-100% Fuel Xe, Kr Cs. I. Te Kr-87=0.22 >S.5E4 >l.650 Core 6%-11%
, Melt >70 1-133=2.1 Uncovery Sr. Ba >24 Pr. Rb >0.8 ,
APPROVED
- 10 hours after shutdown. 94 i _7_
1
. (3956P) B. O. S. R.
~
- BZP 380-A8 Revision 1 SELECTED NUCLIDES FOR CORE DAMAGE ASSESSMENT Core Damage State Nuclide Half-Life
- Predominant Gammas (Kev) Yield (%)*
Clad Failure Kr-85m** 4.4 h 150(74), 305(13)
Kr-87 76 m 403(84), 2570(35)
Kr-88** 2.8 h 191(35), 850(23), 2400(35)
Xe-131m 11.8 d 164(2)
Xe-133 5.27 d 81(37)
Xe-133m** 2.26 d 233(14)
Xe-135** 9.14 h 250(91)
I-131 8.05 d 364(82)
I-132 2.26 h 773(89), 955(22), 1400(14)
I-133 20.3 h 530(90) .
I-135 6.68 h 1140(37), 1280(34), 1460(12), 1720(19)
Rb-88 17.8 m 898(13), 1863(21)
Fuel overheat Cs-134 2 yr 605(98), 796(99)
Cs-137 30 yr 662(85)
Te-129 68.7 m 455(15)
Te-132 77.7 h 230(90)
Fuel Melt St-89 52.7 d St-90** 28 yr -
Ba-140 12.8 d 537(34)
La-140 40.22 h 487(40), 815(19), 1596(96)
La-142 92.5 m 650(48), 1910(9), 2410(15), 2550(11) ,
Pr-144 17.27 m 695(1.5)
- Values obtained from Table of Isotopes, Lederer, Hollander, and Perlman, Sixth Edition.
- These nuclides are marginal with respect to selection criteria for candidate nuclides: they have been included on the possibility that they may be detected and thus utilized in a manner analogous to the candidate nuclides.
8- APPROVED
' "' APR 2 71984 B. O. S. R.
_eu=-e==-*M=es= e**=
,,,.w-%
- - - - +.-,-------.,r - - " ' ' ' ' -
. BZP 380-A8 Rev12 ion 1 ISOTOPIC ACTIVITY RATIOS OF FUEL PELLET AND GAP Nuclig Fuel Pellet Activity Ratio Gap Activity Ratio Kr-85m 0.11 0.022 Kr-87 0.22 0.022 Kr-88 0.29 0.045 Xe-131m 0.004 0.004 Xe-133 1.0 1.0 Xe-133m 0.14 0.096 Xe-135 0.19 0.051 I-131 1.0 1.0 I-132 1.5 0.17 I-133 2.1 0.71 I-135 1.9 0.39 Where:
Total Activity of Noble Gas Isotope Released Noble Gas Ratio = Total Activity of Xe 133 Released Total Activity of Iodine Isotope Released Iodine Ratio = Total Activity of I 131 Released APPRoyED 9- APR 271984 (3956P)
- 8. O. S. R.
-- - - - ~ - . .
- -*--%- , -- ,_ - , . - - - - - + , - --------,y,,n7,.--y, - - ,v,r y y- w,. ,gg .sy ,y.-yy--ps,-- ----gwy--,,,y, ,.--.v-,-,---ee---.y.g. , - - , , . - - - - - - - .-,.y------+-- y w, aw.
. L BZP 380-A8 Revision 1 CALCULATION OF INGROWTH AND DECAY CORRECTION FACTORS Kr-86 : e0.157t Kr-87 5 e0.547t Kr-88 > e0.247t 1
Xe-131M : - -
-2.62e (3.54E-3)t + 3.62e (2.45E-3)t 1
Xe-133 > - - -
-0.185e (3.41E-2)t -0.10e (1.28E-2)t+1.285e (5.48E-3)t 1
Xe-133M > -0.le (3.41E-2)t ,y,1, -(1.28E-2)t 1
- -1 - -
-9.26e (1.04E-1)t -0.033e (2.66)t +10.293e (7.58E-2)t I-131 0
> e .00359t 1
I-132 > 0.103e (8.91E-3)t +0.897e (0.307)t I-133 > e 0.0341t I-135 ::- e0.104t Cs-134 2- 1 1
Te-129 - -
> 1.09e (0.161)t +0.16e (8.47E-4)t -0.25e (0.605)t Te-132 r-- e0.00892t Ba-140 y e .00225t 0
I 1
La-140 > - -
1.09e (2.25E-3)t -0.09e (1.72E-2)t 1
La-142 -
-0.14e (3.78)t ,g,34,-(0.449)t 1
Pr-144 > - -
0.91e (1.04e-4)t +0.09e (2.4)t .
Where:
t = the number of hours between reactor shutdown and time of sample count (ftcm column 2 of BZP 380-T4 pages 1 and 2). i 10-(3956P) APPROVED l i
APR 2 71984 B. O. S. R.
- i
. - . - -- ._w, -e- .m -..r -
_.%__ , -. ,,g.,., . - , ,y _.-w.- c. .m. _ r. - -- --
, BZP 380-A8 Revicion 1 NORMAL OPERATING ACTIVITY
- Specific Activity in Reactor Coolant Nuclide (uci/am)
KR 85m 1.1 (-1)
KR 87 6.0 (-2)
KR 88 2.0 (-1)
Xe 131m . 1.1 (-1)
Xe 133 1.8 (+1)
Xe 133m 2.2 (-1)
Xe 135 3.5 (-1)
I 131 2.7 (-1)
I 132 1.0 (-1)
I 133 3.8 (-1)
I 135 1.9 (-1)
Values obtain9d from ANS 18.1 (3956P) J' E l' F* Pt C) if Et t)
APR 271984
- 8. O. S. R.
l s .-- - .-
_ _ -__=---m _
~- .
BZP 380-A8 Revision 1 IODINE 131 ACTIVITY RELEASED DUE TO SPIKING PHENOMENA Range of Average SA Total I-131 Available for Release, Curies 0.5 < SA < 1.0 3400 0.1 < SA < 0.5 380 0.05 < SA < 0.1 200 0.01 < SA < 0.05 200 0.005 < SA < 0.01 100 0.001 < SA < 0.005 100 SA < 0.001 2 Maximum I-131 Available for Release.
Range of Average SA for. Curies (90% probability of not exceeding 90/90 Upper Confidence Level indicated curies 0.5 < SA < 1.0 6500 0.1 < SA < 0.5 950 0.05 < SA < 0.1 650 0.01 < SA < 0.05 650 0.005 < SA < 0.01 300 0.001 < SA < 0.005 300 SA < 0.001 10 Where SA = the normal operaing I 131 specific activity (pci/ga) in the reactor coolant.
KPPROVED APR 271984 B. O. S. R, (395'P)
, . - . . . . ~ . - - -...-..
-w,. - . _ , ,
r - - - ---- * --
-,._--,,__.,__,.-2,_ _ __ _ . - ----r- -
_m . , , - , _ , , - - - . , , , -
. - - + -
- BZP 380-A8 Rsvision 1 PERCENT OF NOBLE GASES IN CONTAINMDTI 10 6, , , , , ,,,,,_ , i i ' '
"g 5 .
00 5- E 10 .
i
~
E u
R a 4 Q.* .
N -
- -l-10 ..
- : %. '- 4 o - -e .
5
's TI00%-9 ,
fx 10 3
5 30%,.,, 0%-
g e
o i -
H u
C -
Rey'8see ~
'% E s* 2 10 .. -
I ' %. "~ ~
w
. 100%,. -
SQL 0% ,
W - -- E 1
o 10 - o% - :
Z ! .
g :
" ~
= O V
'i-10 :. -
y : ~
i 'r atin ~
- ~
NobIe cAsease. Re1 .
-s i$ 10 =- -
z : -
o = -
. . . . u -
-- ~ ,, .
~ ~. -2 i
,,,,,,I , ...6..
h,r i i e i i*g 100 1000 i
TIME ..TER SHUTDOWN, ROURS
- Specific to Byron Nud e,ar Generating Station only APPROVED APR 271984 M" 8. O. S. R.
Page 13
- - - - , , c,_% ,. . . _ _ _s- . _ . . . _ . - -