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 Sampling Procedures 1:2)PS93538 o
l l
Alternate point 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 or j
RHR System Provided RHR taking suction from Containment 1(2)PS9353A or Sump.
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
SCENARIO SAMPLING LOCATIONS (S)
SAMPLE PROCEDURES (S)
COlmENTS i'
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.
Containment Bldg Containment BZP 380-18 When coupled with reactor cooling anomalies or 4
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 1(2)PS9350B i
i i
4 l
APPROVED APR 2 71984 i
(3956P)
B.O.S.R.
1
F l
3Z? 380-A8 Revision 1 700 600 500 F
.7 400 w3 21 8
300 4
200 100 L
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0.25 0.50 0.n 1.0~
Specif ic Gravity SPECIFIC GRAVITY OF WATER V5 TEMPERATURE APPROVED APR 2 71984 Page 2 B. O. S. R.
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Revision 1 26.0 24.0 -
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10 20 30, 40 50 60 70 80 90 100 ZIRCCNIUM WATER REACTION (%)
CCNTAINM BT HYOROGEN CONCS TRATION SASED CN IIECMIUM WATER REACTION APPROVED APR 271984 B. O. S. R.
Page 3
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W8P >JtFf-41J Ravision 1 1.
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itELATIONSHIP OF % CLAD DAMAGE WITH INVENTORY RELEASED OF I-131 WITR SPIKING APPROVED APR 2 71084 P'S* 'd
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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 'dITH % INVENTO RELEASED OF I-133 APPROVED APR 2 71984 B. O. S. R.
Page 4 f
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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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i RELATIONSHIP OF % FUEL OVERT'L".PERATU INVENTQRY RELEASG OF XE, XR. I. C5 t
j APPROVED APR 271984
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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 RELE AS ED O F XE o r KR o r I or CS or TE l
APPROVED APR 271984 B. O. S. R.
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- s. o. s. a.
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RELATIONSHI? 0F % FUEL MELT WITH % INVENTORY RELEASED OF PR APPROVED APR 271984 B.O.S.R.
Page 6e 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 APPROVED Pr. Rb >0.8 94
- 10 hours after shutdown.
i
_7_
(3956P)
B. O. S. R.
1
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.
APPROVED 8-APR 2 71984 B. O. S. R.
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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.
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L BZP 380-A8 Revision 1 CALCULATION OF INGROWTH AND DECAY CORRECTION FACTORS e.157t 0
Kr-86 e.547t 0
Kr-87 5
e.247t 0
Kr-88 1
-2.62e (3.54E-3)t + 3.62e (2.45E-3)t Xe-131M 1
-0.185e (3.41E-2)t -0.10e (1.28E-2)t+1.285e (5.48E-3)t Xe-133 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
> e.00359t 0
I-131 1
0.103e (8.91E-3)t +0.897e (0.307)t I-132
> e.0341t 0
I-133
- - e.104t 0
I-135 Cs-134 2-1 1
Te-129
> 1.09e (0.161)t +0.16e (8.47E-4)t -0.25e (0.605)t r-- e.00892t 0
Te-132 y e.00225t 0
Ba-140 1
1.09e (2.25E-3)t -0.09e (1.72E-2)t La-140 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 APR 2 71984 B. O. S. R.
- i
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.m
-..r
,,g.,.,. -,
,y
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c.
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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
' E l' F* Pt C) if Et t)
J (3956P)
APR 271984
- 8. O. S. R.
l
-__=---m s
~-
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)
,. -.... ~. -
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-,._--,,__.,__,.-2,_
r-m
.,,, - - - + -
r - - - ---- * --
BZP 380-A8 Rsvision 1 PERCENT OF NOBLE GASES IN CONTAINMDTI
"g i i
6, 10 5
5 -
00 10.
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u R
Q.*
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a 10 4
-o
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's TI00%-9 f
5 30%,.,,
0%-
3 g
x 10 e
i o
u H
Rey'8see E
C
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s 2
10..
I
"~
100%,.
~
w SQL 0%,
E W
1 o%
o 10 Z
g
~
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=
10 V
y
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a NobIe cAs Re1
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ease.
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10
=-
z o
=
u
-- ~,,
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-2 i
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i*g 100 1000 h,r i
e i i
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,_%
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