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Latest revision as of 22:24, 15 March 2020
| ML19331D666 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/21/1980 |
| From: | Dill J, Kitts R, Zobel W TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19331D664 | List: |
| References | |
| IP-18, NUDOCS 8009030438 | |
| Download: ML19331D666 (48) | |
Text
-
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, ., ,' / ,
Scquoyah Nuclear Plant ncysm II DISTRIBUTION
'e-ic 81 Plant Master File 1C 82 Superintendent 1C 83 Assistant Superintendent (Oper.)
IC 84 Assistant Superintendent (Maint.)
TVA REP - IMPLEMENTING 1C 85 Administrative Supervisor PROCEDURES DOCUMENT 1C 86 Maintenance Supervisor (M) 1C 87 Maintenance Supervisor (E) 1C 88 Maintenance Supervisor (I) 1C 89 Results Supervisor IP-18 1C 90 Operations Supervisor 1C 91 Quality Assurance Supervisor 1C 92 Health Physics Supervisor PLANT REIIAsE RATE 1C 93 Public Safety Services Supv.
CALCULATICNS LC 94 Chief Storekeeper 1C 95 Outage Director 1C 96 Emergency Cabinet Control Room 1C 97 Emergency Cabinet Communications Room IC 98 Emergency Cabinet Gatehouse 1C 99 Emergency Cabinet Meteorological Bldg.
1C 100 Emergency Cabinet Meteorological Bld.
IC 101 Staff Incustrial Engineer (Plt Sys)
IC 102 Shift Engineer's Office lc 103 Unit Control Room Prepared By: (1.)a / / ek 2,,S,/ 1C 104 QA&A Rep. - SNP 1C 105 Health Physics Laboratory Revised By: h.d. N M S [. /); /[
^
1C 106 Medical Office Submitted By: t/
n fj h// _
,M. K j f/f/)
1C IC 107 Resident NRC Inspector - SNP 108 Technical Support Center S'uperiFisor 1C 109 Assistant HP Suparvisor 1C 110 Plant Duty Supervisor PORC Review: 9 2/ PD IC OC H&S - John Ingerson - MS Date Approved By: (/ ) ,,
' ' Superintendent.' / ' .
Date Approved: p - ; / - po Rev. No. Date Revised Pages Rev. No. Date Revised Pages .
M 7JJ,l22)
The last page of this instruction is Number 4S
,8009030 #3g
,re .ee- - , m e -- - - - - -
q--g ,-e ,e,,,--e. ----,w,w ,, - - , , - + ----,,--.,--,,-..-r-w-
-, , - , - ,r,-- -
SQNP Page 1 of 6
,. REP-IPD SQN, IP-18 -
Rev. O PLANT RELEASE RATE CALCULATIONS 1.0 Purpose This procedure describes the methodology used to calculate and predict the plant releard rate of noble gases, iodine & particulates during accident conditions.
PART A PLANT PARAMETERS REQUIRED FOR REII.ASE RATE CALCULATION 2.0 Determine which isotope spectrum to use based on the latest primarv coolant measurement.
2.1 On Worksheet 1-A record the latest measured primary coolant activity (per SI-50 for noniodine isotopes and SI-55 for radiciodine, or post-accident measurement) and calculate the activity ratios. Record ratios on worksheet 1-A, step 1.0.
2.2 On Worksheet l'-A, Step 1.1 circle the entries corresponding to the ratios calculated 's 2.1.
2.3 On Worksheet 1-A, step 1.2 check the isotope spectrum on the line with the most circled entries. This isotope spectrum will be used in steps 2.0 through 7.2 of this procedure.
IMPORTANT: A POWER CHANGE OF MORE THAN 15 PERCENT WITHIN 2-8 HOURS BEFORE TE PRIMARY COOLANT SAMPI.E WAS TAKEN INVALIDA17.S THE RATIOS INVOLVING IODINE (I). IN SUCH A CASE, RELY ON THE C/R R.CIO.
3.0 Determine severity of fuel failure Note: The information labeled " Expected: r.nd " Design" is based on 1 percent failed fuel; the " Modified TID-14844" information is based on 1 per-cent of the total radioactivity inventory of an equilibrium reactor core. ,
3.1 On Worksheet 1-A, circle the calculated specific activities for each of J the isotopes (I-131, Cs-137, Rb-88) given in Worksheet 1-A, step 1.3 ;
for the isotope spectrum chosen in 2.3. .
3.2 Calculate and record on worksheet 1-A, step 1.4, the ratio of -he cas-ured specific activity (from step 2.1) to the circled calculated values of Worksheet 1-A, step 1.3.
3.3 Select n normalization factor corresponding most closely to two of the three rat ios. Record this on worksheet 1-A, step 1.5.
I NOTE: For "Erpected" and " Design" isotope spectra, the normalization 1 factor corresponds to the failed fuel fraction; for the " Modified i TID-14344" spectrum, the normalization factor corresponds to the percentage of equilibrium core inventory.
,, ,.-,-w , - - . , - - . . , - - . , . . - - . . , , , .-.-,-n. ,- - , , , _ . --,- ,---_,,,-.,_.,,----,,n . - . - - . - -
~
SQNP ,
Page 2 of 6 REP-IPD SQN, IP-18 Rev. 0 4.0 Determine primarv coolant leak rate into containment.
Use worksheets 1-B and 1-C. Record readings of radiation monitors 1-RM-90-100, 1-RM-90-112, 1-RM-90-106 on worksheet 1-B, step 1.0. If 1-RM-90-112 and/or 1-RM-90-106 readings are off-scale, record 1-RM-90-2. Record the time the readings are taken on worksheet 1-B, steps 1.0 and 1.1.
4.1 From the last detector efficiency verification (TI-18, Worksheet 18-C.1B),
convert epm readings to pCi/cc. Record on worksheet 1-B, step 1.0.
4.2 Calculate the elapsed time from reactor shutdown to the recording of monitor readings. Record on worksheet 1-B, step 1.1.
4.3 If both radiation monitors 1-RM-90-112 and 1-RM-90-106 readings are off scale, skip to 4.12; otherwise, continue with 4.4 4.4 From the last detector efficiency verification (TI-18, Worksheet 18-C.1B) calculate the ratio of Xe-133 specific activity to total specific activity for 1-RM-90-112, 1-RM-90-106. Record on worksheet 1-B, step 1.2.
4.5 Calculate the Xe-133 specific activity in upper containment by multiply-ing the specific activity derived from the radiation monitor 1-RM-90-112
-reading (i.n step 4.1) by its Xe-133/ total ratio (in step 4.4). Record on worksheet 1-B, step 1.3.
4.6 Calculate the Xe-133 specific activity in lower containment by multiply-ing the specific activity derived from the radiation monitor 1-RM-90-106 reading (in step 4.1) by its Xe-133/ total ratio (in step 4.4). Record on j worksheet 1-B, step 1.3.
4.7 Determine the primary coolant leak rate into lower containment as follows:
Note: Use data based on radiation monitor 1-RM-90-106 readings if on scale. Use data based on radiation monitor 1-RM-90-112 readings if 1-RM-90-106 is off scale.
4.8 For isotopic spectrum:
Expected - Use Figure la with 1-RM-90-106 data; use Figure 2a with 1-RM-90-112 data.
Design - Use Figure Ib with 1-RM-90-106 data; use Figure 2b with 1-RM-90-112 data.
Modified TID-14844 - Use Figure Ic with 1-RM-90-106 data; use Figure 2c with 1-RM-90-112 data.
SQNP Page 3 of 6 REP-IPD SQN, IP-18 Rev. 0 4.0 Determine primary coolant leak rate into containment (Cont.)
4.9 Norr lize the measured Xe-133 specific activity by dividing by the norma-liza <on factor determined in step 3.3. Record on worksheet 1-C, step 1.5.
4.10 Using the elapsed time from step 4.2, estimate. a primary coolant leak rate by visually interpolating between the applicable curves in Figures 1 or 2.
Record on worksheet 1-C, step 1.6, the value of the specific activity from the curves cbove and below the normalized measured value and the cor-responding primary coolant leak rate.
4.11 Record on Worksheet 1-C, step 1.7 the estimated primary coolant leak rate.
4.12 If the readings for both 1-RM-90-106 and 1-RM-90-112 are off scale, do the following:
4.12.1 Select Figure 3a, 3b, or 3c depending on the isotope spectrum chosen (" Expected," " Design," or " Modified TID-14844," respec-tively).
4.12.2 Normalize the measured exposure rate at monitor 1-RM-90-2 location
, tor dividing by the normalization factor determined in step 3.3.
Record on Worksheet 1-C, step 1.8.1.
4.12.3 Using the elapsed time from step 1.1, estimate a primary coolant leak rate by visually interpolating between the applicable curves of Figure 3. Record on worksheet 1-C, step 1.8.2, the value of the calculated monitor reading from the curves above and below the normalized measured value and the corresponding primary coolant leak rate.
4.12.4 Record on Worksheet 1-C, ste, ~.8.3, the estimated primary coolant leak rate.
5.0 Determine containment leak rate.
Use worksheet 1-D. Obtain flow from SI-2 for the shield building exhaust .
and record in step 1.0. Also, record containment pressure and the time of reading in step 1.1.
5.1 Calculate the radioactivity release rate by multiplying the specific activity from 1-RM-90-100 (worksheet 1-B, step 1.0) by the vent flow from step 5.0 and by 472 (unit conversion factor):
Release Rate = 472 x Activity x Vent Flow Reco,rd on Worksheet 1-D, step 1.3.
l .
- SQNP Page 4 of 6 REP-IPD SQN, IP-18 Rev. O i
5.0 Determine containment leak rate.(Cont.)
l 5.2 Select from Figure 4 the sheet corresponding to the isotope spectrum (worksheet 1-A, step 2.3) and primary coolant leak rate (worksheet 1-C, step 1.7 or 1.8.3) determined earlier.
5.3 Divide this measured rate by the normalization factor from Worksheet 1-A, step 1.5. Record on Worksheet 1-D, step 1.4.
i 5.4 Using the elapsed time from Worksheet 1-B step 1.1, estimate a gaseous leak rate by visually interpolating between the curves of Figure 4. l Record on Worksheet 1-D step 1.5, the value of the calculated vent release '
rate from the curves above and below the normalized measured value and the corresponding gaseous leak rates.
5.5 Record on Worksheet 1-D, step 1.6 the estimated gaseous leak rate.
5.6 From Figure 5, for the containment pressure determined in step 5.0 and the calculated leak rate, obtain an equivalent hole size.
PART B PREDICATED' VENT RELEASE RAT 2--NO CHANGE IN PLANT CONDITIONS 6.0 Calculate noble gas vent release rate Use worksheet 2-A.
6.1 Use the - me sheet of Figure 4 selected in Step 5.2.
6.2 Use the containment leak rate determined in Step 5.4.
6.3 Select the time for suich the vent release rate is desired.
6.4 Obtain the noble gas vent release rate by interpolation between the r
curves on Figure 4:
} 6.4.1 Determine interpolation fraction = LRD - LR(L)
LR(U) - LR(L) where: LRD = containment leak rate from Step 5.4 LR = containment leak rate for which curve is calculated.
(U),(L) = value of LR immediately (above) (below) LRD 6.4.2 Determine the difference between vent release rates correspond-ing to LR(U) and LR(L) at the desired time, multiply by the
. interpolation fraction, and add to the vent release rate corres-ponding to LR(L).
SQNP Page 5 of 6 REP-IPD SQN, IP-18 Rev. 0 6.0 Calculate noble gas vent release rate (Cont.)
6.4.3 Multiply by the normalization factor from Worksheet 1-A, Step 1.5. Record on Worksheet 2-A, steps 1.0, 1.1 and 1.2.
7.0 Calculate the iodine vent release rate.
Use Worksheet 2-B.
7.1 Use the sheet of Figure 6 corresponding to the one of Figure 4 selected in Step 6.1.
7.2 Follow procedure 6.0. Substitute Figure 6 for Figure 4.
NOTE: It is not necessary to recalculate the interpolation fraction (Step 6.4.1)'since it will be unchanged. Record on Worksheet 2-3, step 1.0.
8.0 PREDICTED VENT REI. EASE RATE--CHANGING PI. ANT CONDITIONS 8.1 For a different postulated primary coolant activity:
8.1.1 Consider which isotope spectrum (" Expected," " Design,"
" Modified TID-14844") was chosen in Step 2.0.
8.1.2 Consider the magnitude of the normalization factor determined in Step 3.0.
8.1.3 Decide on a new primary coolant activity by increasing the normali-zation factor (fuel failure) or changing the isotope spectrum based on' plausible developments in the condition of the plant.
In order of increasing severity, isotope spectra rank as follows:
(1) Expected (2) Design ~
(3) Modified TID-14844 If the isotope spectrum is " Expected," do act increase the nortali-zation factor to more than 2; instead, change the spectrum to
" Design."
If the isotope spectrum is " Design," do not increase the normali-
. zation factor to more than 15; instead, change the spactrum to
" Modified TID-14844."
-~ .
- SQNP Page 5 of 6 REP-IPD SQN, IP-18 Rev. 0 8.2 For a different postulated containment leak rate 8.2.1 For an anticipated change in containment pressure with no addi-tional containment (egradation, use Figure 5 with the equivalent hole size determined in Step 5.5.
8.2.2 For anticipated containment degradation, use Figure 5 with an appropriately chosen hole size.
8.2.3 Determine the new containment leak rate from Figure 5.
8.3 For an anticipated degradation of the primary coolant loop.
Change the primary coolant leak rate to containment.
8.4 For the postulated changed plant parameters, recalculate future vent releases using the methods given in part 2.0.
NOTE: Part B is based on unchanged plant parameters. If the postulated conditions are more severe than those determined to exist in part A, the part B methods with the changed parameters will result in release rates which are tso high;
. conversely, in the unlikely event that the postulated condi-tions are less severe, the estimated release rates will be too low.
W m , .. - - - - - _ _ . . _ - - _ _ , . _ _ - . . . , _ - . . _ . -- _- - _ _ . _
~
SQNP Page 1 of 6 REP-IPD SQN, IP-18 Attachment 1 Rev. 0 GASEOUS RELEASES WORKSHEET 1-A 1.0 Determination of Isotopic spectrum I = I-131 specific activity pCi/g C" = Cs-137 specific activity pCi/g R*,
Rb-88 specific activity pCi/g Im/Cm = Im/R m = Cm/Rm
1 Selection of Isotope Sepctrum Appropriate Isoptope I/C I/R C/R Spectrum 8.5 < I/C 5 18.5 1.0 < I/R 5 10 C/R $ 0.18 Expected I/C 5 8.5 I/R 5 1 ^ 0.18 < C/R 5 1.0 Design I/C > 18.5 I/R > 20 C/R > 1.0 Modified TID-14844 1.2 Chosen distribution is (check one).
" Expected"
" Design"
" Modified TID-14844" 1.3 Specific Activity in Primary Coolant (Prior to Incident) for Three Isoptopic Spectra Specific Activity Level (pCi/g) ~
Isotope Expected Design Modified TID-14844_
6 I = I-131 2.3 2.5 9.33 x 10 C = Cs-137 0.16 1.0 4.15 x 10 5 R = Rb-88 5 1.9 3.7 2.38 x 10
, - , .-. - ,- . . . - . , , , , - - - . , . - . . , . , . , . , - . . , . . . _ , ,.-_-_-._,c - ,.-
_ ~ ,
., SQNP Page 2 of 6 REP-IPD SQN, IP-18 Attactment 1 Rev. O GASEQUS REI. EASES k'ORKSHEET 1-A (Continued) 1.4 Subscript m denotes measured specific activity.
Subscript c denotes claculated specific activity from Table 2.
I /I mC
= C3 /C C
= R2 /R C
=
1.5 Select a normalization factor corresponding most closely to two of the three ratios:
Normalization Factor F=
b w
- b
3
, SQNP Page 3 of 6 REP-IPD SQN, IP-18 Attachment 1 Rev. O GASEGUS RELEASES WORKSHEET 1-B 1.0 Radiation Monitor Readings @
Time and-Date 1-RM-90-100: cpm = pCi/cc 1-RM-90-112: cpm = pCi/cc 1-RM-90-106: cpm = pCi/cc 1-RM-90-1 mr/hr 1.1 Reactor shutdown date and time Monitor reading date and time Elapsed time t, = hr min = hrs 1.2 Detector Efficiency Verification Date and Time:
1-RM-90-112: Xe-133 pCi/cc (Upptr Containment)
Total. pCi/cc Ratio (Xe-133/ Total) =
1-RM-90-106: Xe-133 pCi/cc (Lower Containment) Total pCi/cc Ratio (Xe-133/ Total) =
1.3 Measured containment Xe-133 specific activity:
Xe-133 in Upper Containment:
pCi/cc x = pCi/cc = MXe (1-RM-90-112) (Ratio)
Xe-133 in Lower Containment:
pCi/cc x = pCi/cc = MXe (1-RM-90-106) G<a tio)
y . .
I SQNP Page 4 of 6 REP-IPD SQN, IP-18 Attachment 1 Rev. O GASEOUS RELEASES WORKSHEET 1-C 1.4 Calculate primary coolant leak rate using monitor 1-RM-90-106 or 1-RM-90-112 from Figure 1.a (lower containment, monitor 1-RM-90-106) or Figure 2.a (upper containment, monitor 1-RM-90-112) for " Expected,"
Figure 1.b or 2.b for " Design," or Figure 1.c or Figure 2.c for
" Modified TID-14844."
1.5 From step 1.3 worksheet 1-B.
MXe = pCi/cc or MXe = pCi/cc 1-RM-90-106 1-RM-90-112 where MXe is the measured Xe-13? specific activity at t,.
Normalization factor (from 1.5, worksheet 1-A) F=
MxeN = pCi/cc or = pCi/cc 1-RM-90-106 1-RM-90-112 1.6 Calculated. specific activity frem Figure (Record figure used).
CXe(U) = pCi/cc CXe(L) = pCi/cc PCL(U) = gpm PCL(L) = gpm where: CXe(U) = Calculated Xe-133 activity greater than MXeN CXe(L) = Calculated Xe-133 activity smaller than MXeN PCL(U) = Primary coolc t leak rate corresponding to CXe(U)
PCL(L) = Primary coolant a sk rate corresponding to CXe(L) 1.7 Estimated primary coolant leak rate: gpm 1.8 Calculate primary coolant leak rate using monitor 1-RM-90-2:
1.8.1 From step 1.0, worksheet 1-B, 1-RM-90-2 MER = mR/H where MER is the measured exposure rate at t, Normalization factor (from 1.5, worksheet 1-A) F=
MERN = MER/F: mR/h
-
- SQNP {
Page 5 of 6 REP-IPD SQN, IP-18 Attachment 1 Rev. O GASEOUS RELEASES WORKSHEET 1-C (Continued) 1.8.2 Calculated monitor reading from applicable curve Figure 3 (Record figure used). .
CDR(U) = mR/h CDR(L) u mR/h PCL(U) = gpm PCL(L) = gpm where: CDR(U) = Calculated monitor reading greater than MERN CDR(L) = Calculated monitor reading smaller than MERN PCL(U) = Primary coolant leak rate corresponding to CDR(U)
PCL'L) = Primary coolant leak rate corresponding to CDR(L) 1.8.3 . Estimated primary coolant leak rate: gpm E
o 9
i e
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. . 3%9 rage .o c,e
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Ss**.%* , T..v. T. 2 Atta ctr.ent 1 Rev. O .
-.c .<.:.
w:u -r .::r = s er: .t.:I.<=_: .
1.
1.0 Chtain flew fres SI-2 for Shielding Scildi:g I.xhaust:
Time a :1 Cate 1.1 Cc :ai =en. Pressure FdI-30 *.2: psi
- 47.,w.
.. .a 2
.. , s :.
c.u- v -: psi
..at. 2 .*:.
.V #. .s 1.2 Frc= vorksheet 1-3, step 1.0 1-52-30-10C: ;.Ci/cc 1.3 . Measured " -14 3 ild g vent Release Eate:
. .u, = .,., . x x = pC:./s 1 .:d-90-100 Value frca 1.0
- 1. '. Nor=alizatic: facter (fres 1.5, verksheet 1-A) .? =
.\.
. :-. = .rs-}:: :,;C:.. / s 1.5 Calculated vent release rate fr:s Figure I. (Rec:rd figure used).
G3(U) ;.:Ci/s G2(!.) pCi/s
.r .=. ( ~v ) s-.-su . :(.r )
A, sse..
shere: G2(") = Cale: lated vest release rate greater tha VKF5 CAR (!.) = Calculated vest release rate s= aller th2: VRF5 LR(C) = Gasec :s leak rate correspceding to G3(U)
LR(L) = Gasecus leak ra:e correspc ding to G2(!)
1.6 Ccatai =ent gaseens leak rate:
UO = sefh l.
1.7 Cestai:eent equivale : hele size (diaseter)
CF.E5 = 1:ches t
. A em . -
l
.-. - ~ _ . _ , - _
- r. . . . ._. _,..,_..-.,,y .,e., . _ . py_ . -. , _.
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' SQNP Page 1 of 2 REP-IPD SQN, IP-18 Attachment 2 Rev. O GASE0CS RELEASES WORKSHEET 2-A Containment Noble Gas Release Rate Containment Leak Rate from Worksheet 1-D, step 1.6 LRD = cfh 1.0 From Figure 4 (Record figure used)
LR(U) = scfh LR(L) = scfh where: LR = Containment leak rate used in procedure Step 5.4 1.1 Time elapsed since reactor shutdown :: hours 1.2 Interpolation Fraction:
LRD - LR(L)
IF = LR(U) - LR(L)
_~ ( )-( )_
( )-( )-
From applicable Figure 4, at t, determine CRR(U) corresponding to LR(C):
CRR(U) = pCi/s From applicable Figure 4, at t, determine CRR(L) corresponding to LR(L):
CRR(L) = -
pCi/s -
Normalization factor (from step 1.5, worksheet 1-A) F = '
Future noble gas release rate =
{ IF x [ CRR(U) - CRR(L) ] + CRR(L) } xF
= x[ x
{ -
]+ }
= pCi/s NOTE: Same nomenclature as on worksheet 1-D.
-~
~. -
SQNP Page 1 of 2 REP-IPD SQN, IP-18 Attachment 2 Rev. O GASEOUS RELEASES WORKSHEET 2-A Containment Noble Gas Release Rate Containment Leak Rate from Worksheet 1-D, step 1.6 LRD = cfh 1.0 From Figure 4 (Record figure used)
LR(U) = scfh LR(L) = scfh where: LR = Contairment leak rate used in procedure Step 5.4 1.1 Time elapsed since ' reactor shutdown t: hours 1.2 Interpolation Fraction:
IF _ LRD - LR(L)
LR(U) - LR(L)
_( )-( )_
~( )-( )~
From applicable Figure 4, at t, determine CRR(U) corresponding to LR(U):
CRR(U) = pCi/s From applicable Figure 4, at t, determine CRR(L) corresponding to LR(L):
CRR(L) = pCi/s Normalization factor (from step 1.5, worksheet 1-A) F = -
Future noble gas release rate =
{ IF x { CRR(U) - CRR(L) ] + CRR(L) } xF
={ x[ -
]+ } x .
= pCi/s NOTE: Same nomenclature as on worksheet 1-D.
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