ML19224B463
| ML19224B463 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/14/1979 |
| From: | Metropolitan Edison Co |
| To: | |
| References | |
| 1622.2, TM-0544, TM-544, NUDOCS 7906150129 | |
| Download: ML19224B463 (31) | |
Text
,
TMI DOCUMENTS DOCUMENT NO:
TM-F9 1 I
COPY MADE ON 5"?- T ~ 7f OF DOCUMENT PROVIDED BY METROPOLITAN EDISON COMPANY.
- AC',#
Supervisor, Document Control, NRC l
l i
I i
~
t
"TEMPOllARY CIIANGE"
).
\\
Three Mile Island Nul ar Station SIDE 1 Fe p!M1-5 Temporary Change ts tice (TCN)
TCN NO. 2 d6c9 NOTE: Instructions and guidelsnes en AP 1001 (From TCN Log inoem) must be followed when completing Unit No.
M-this form, f
Date ~
I W
1.
Procedure
/ /' M 1 RE LCn'. id e ih o 6 4 5 k)A fTG-r No.
Titie 2.
Clunge (inciude page numbers. peregrapn number. and e,act wording of change.)
N 4IIIM(IEC 3.
Reason for Change:
Hyomu PuM cwNevP syvc+1
~
4.
Recommended by
>Mf M/Y/??
f.
O/[
M/d/7h V'
- /
Date Supervisor's S+gnatus;d 8
Date /
6.
Ouration of TCN - No ionger tnan ninety days from etf active date of TcN or as in (a) or (b) below whichever occurs first.
(a)
TCN will be cancelled b a pr edure revision issued as a result of a Procedura Change Request to be submitted by
' A. /
(Submit PCR as soon as possible)
Supervmor Su.yfting TCN (b) TCN is not valid af ter v
(f all in circumstances wh6Ch will result en TCN be.ng cancelled) 7.
(a) is the procedure on the Nuclear Cafety Related Procedure Ust? (Sec. AP 1ool - A diz 8)
If "Yes", complete Nuclear Safety Evaluation. (Side 2 of this Form)
Yes No (b) is the procedure on the Environmental Impact Procedure List?
(Sec. AP 1001 - A ndix B)
If "Yes", complete Environmental Evaluation. (S;de 2 of this Form)
Yes No
[
(c)
Does the change ef fect the intent of the original procedure?
Yes No NOTE: If all answers are "no" the change may be approved by the Shif t Supervisor. If question (c) is answered "yes", the change
}
must be reviewed by the FORC and approval by the Station /Umt Superintendent prior 'o implementation. If the ansvar to question (c) is "ru" the change may be approved by two tiembers of the plant ma.agement staff at least one of whom holds a senior reactor operators license on the unst affected in accordance with paragraph 3.6.4.2 cf AP t ool.
8.
Review and 4croval s
Black (c) "yes" Block (c) "no" Approved _
Approved b
Sh.tt Supervisor / Foreman Date O tscense Date e
Reviewed.
/
,, /,. ///tw Y[
9" [ f@tnr' Plant Mrg. Statt Dete/
Members Of PORC Reviewed Chairman of PORC De to Contacted Approved POHC Memoets Date Unit Super...tendent Date i
Unit Superinten".:ent Date l
l NOTE: The block (c) "Yes" review and approval chain may be followed at a nytime.
9.
Accroval M
IN Manager, Generation Quality Assurance a 4-r Date NOTE:
M.G Q. approval required only on cbtain AdministratiMocedures listed in enclosure 7 of AP 1001 10.
TCN is Cancened 7
T MI-56 Rw. & 7 7
" EVALUATION" I
'41 Three Mile Island Nuclear Station SIDE 2 Figud.1001-4 Nuclear Safety / Environmental Impact Evaluation
~
1.
Pracedure NM, d'
'D66N RAO 64ii b) A86 2
'7 9-od 8
' No.
Titi*
T.mpor.ry Change Notic. No.
2.
Nut. lear Safety Evaluation Does the attached procedure change:
- (a) increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety?.............
.. ves noY
- (b) create the possibility for an accident or malfunction of a different type than an, avaluated
............. ves O no Y previously in the safety analysis report?...
- (c) reduta the marg.a at ufety as defined in tne basis for any technical speci'ica'..on?,.... yesO noW Details of Evaluation is.pi..n.hy.n.
...oov. qu... n..,. "no" Attach.dJetsor.al pages af r.qu+ red.)
%1Cb C dCl4 N N
A ML A
ft bIiklli Evaluation By d//2 4 Date M6M/
~
/
, i-
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3.
Environmental Impact Evaluation
& U NM Does the attached procer'ure change:
(a, paisibly involve a significant environmental impact'............
yesO t.d (if 3(a) i:"yes", answer questions (b) and (c) and fill in "D etails of Evaluatipn" belovv.
If "no", state why by filling in the " Details of Evaluation" below).............. yesO noO
- (b) have a significant adverse effect on the environment?...................... yes noT
- (c) involve a significant environmental matter or question not previously reviewed and f
eva l ua t e d b y t h e N. R.C............................,..,,,,...,, yesO no_T D
Details of Evaluation c anacn.ao t.n., p..
i, r.qu,,.oi be f#
Y' Y
Evaluation By C [
._/b Date
/
26'
/
/
/}
/
4.
Unit Superintendent requests POR C review j Check if YES.
5.
Approval Evaluation Accompanying PCR Evaluation A compan ing TC*
Approval M
4.
3- /iGf S
Ucensee Date Unit Superintencent Date f
y
'p/ e Member at Plant Statt '
Date Approval Unit Superintendent Date NOTE: The Evaluation " Accompanying a PCR" evaluation and approval chain may be f ollowd at anytime.
- t. U O UJJ
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as f:, N C + e:r l AaC7'kh{
- dl'IC1 1
MS RILEt;iE i 4
L.0T'.; ;T
. '5 F.EleA*_
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r %m.}
I I
l PARTICULA TES I
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p C.i 2.35x104 uCi !
I lLE G ASSES + H.3
' l. 9 x 10 16 eg 2 CC,*.1PLETE THIS SECTION IF HOLD UP TIME >45 DAYS OR IF REACTOR SLCG.
% Fj='(0.15/u Ci/sec) (2.12 x 163 3
tt / min /ce/sec) l
=
y Ci/ccTOTAL from 24 3
ft / min
'~..
l 4
e F =(6.0x10 M /Sec) (2.12 x 10 +3 3
LCWEST = FM 3
f t / min /M'/Sec) =
l G
TOTAL FROM 25 3
ft / min O COMetETE Tsis sECTiOn rF sOto.ue TiMF <45 DAYS F =(1.5x10-3 Ci/ Sect (2.12 x.163 ft 3.- :.i/cc/ sec)
/
l 1
=
z 1
_ p Ci/cc TOTAL CO L 24 -
3 ft / min L
i LOWEST = FM F = (1.2x103 3
M /sec) (2.12 x 10'3 3
3 ft / mis,/M /<'ac)=
l g
3 TOTAL COL 25 FILL IN THIS SiOE FOR *.*.'ASTE CECAY TANKS l FILL IN THIS SIOE FCR REACTOR GLOG.
3Ib le r M ( 1.)
22 u ru< 27777 Ft3#1in D0 liOI RELEASE TAtW. d T R T S e RVC R O CourtcTc T 4 s ssCT:Cu in i.i < ru < io"g RETURN 70 3 SHIFT /SUPERVISCR
" ft3 COMPLETE THIS PART IF 27777<FM<55555 ft /mi.
3 g FR,im-1 n,La,,J1 SETP0Im.. FM=
r
=
'=
RELEASE RATE = F'1 = E500ii} ft / min 3
. -V50 SETPOIih =0.9x F:1 =
- fta/ min.
O ru >io rJews COMPLETE THIS MRT I:_RM5555 ft / min 3
ilDG-FR-1484-1 ALARM SETPOINT=
h'" '..
RELEASE RATE = FM=-B)0!iHi ft /mia J
woc.v60 se TPoi"T - e et %.a
$ EXCErr Fcft HYDRoqEV Puf:.GE' a
33 VDG-R-1480 (Gas Channel)VCG-R-1480 and HP-R-219 asTiuAreo ReAoa.cs o* HP-R-225 and HP-R-225 or HPR-2 ccTiu Arso Resomos or l
{ Cuc uid' CAL F ACT Xa i03
+ EKG =!
leom l
- ~ "
VDG-R-1480 G 34c,3Cn,unet j
34 HP-L-219 (Gas Channel) m 1
1 q
y K
}
p CUcc xe-131
[a cue. x-ia4 cat rect uis:} {Fvi
' LOW cut STAC41 C.iL F ACTOR Xa-i33
+
SKC
- * [E y1 - I s
sg i
e o'
IcemHP-R-225G -
. HP-R-219 ' FLOW CFM.
=>
icpm HP-R-226G
- L 8" N-EP-R-219G 35 HP-R-219 (Iodine Channel) 35 icome CxAsseL
,y I uce,.,,q r,,L,,;7,,,,,KH,,,,,,] [y] y ;
m nE he. n fC g
y.v m ax hf.ec.no;
- JM
+
L ".
-HP-R-2251 HP-R-219 Flow CFM com og.
J yF8 gh.,
H7-R-21]I ICPC HP-R-226I com 36 HP-R-219 (Particula,te Channel) 30 PARTICW.ATc CHANNEL
,v
).
[
{ cac-c-ia dh>L FACT] f 4. f agg)( yj 3
ILT. rACT)]
i
/./ CUce CFi37 F LOW can STACK CAL rACC R Cs 13 7
.[e4C
- "' HP-R-225P
- {a*
w HP-R-219 FLOW CFM
~
IcPa HP-R-226P ymkRE.
-l
' com HP-R-219P w
CAL. r ACTO RS AR E AV AILAB LE IN CON T58.0 L ROOM 206 036 18.0
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M ag d
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1622.2 Revision 1 05/08/78
~
5.29 Enter the result of 100 x estimated quantity in this release i.om h divided by the quarterly release allotment.
5.30 Complete the upper section if this is a waste gas tank that has been isolated for greater than 45 days, or if this is a Reactor Building release.
Two flows are calculated. Transfer the lowest value to the box to the right (lowest F ).
This is the maximum m
flow rate (F ) that can be allowed in ordar not to exceed the m
instantaneous release limits. Complete the lower section in an identical manner only if this is a waste decay tank that has been isolateo for < 45 days.
NOTE:
If flow rate n block h is too r strictive for release go to block 0.
Complete Block 0
as per step 5.30 above with the concurrence of the nift Supervisor that Unit I will not release gaseous waste during this period.
i 5.31 Fill in the left side of the form for 'aste decay tank releases.
l If F is < (1.1) CFM, then this tank is too radioactive to be m
released under normal conditions; return from at this point to the Shift Supervisor.
If F is greater than 1.1 CFM but less than 10 m
CFM, then the WDG-FR-1484-1 set point is the value of F. The m
actual release rate, WDG-V-188 A/B set point will be adjusted to is obtained from @,
If F is > (10) CFM, check 90% of F. F m
m m
tha box. The maximum value the alare s an be set is (10) CFM, therefore, this value will be used. WDG-V-188 A/B will be adjusted to (9) CFM.
l 5.32 Fill in the right side c f the form for reactor building releases.
I 30A is < 27777 CFM the reactor,do not If F as calculated in 30 or m
i nseg and return form o 56 < Le rvow. cxceF fir Hydrogen Puge.
e F
l k:lm;y 2.-
is h _radi= ti,c ccicn ed-L..d r nocc;' conm. tier: ;-
_m The H ddjea furpt rde is 15ccfm.
retu-3.c' tc the 9 ft Eg:rvis:-
If F is > 27777 CFf but less m
than 55555 CFM, then AH-FR-5063 or AH-FR-5064 reading is the value from h. The reactor building purge rate is 25000 CFM.
Fm 206 037 9.0 i
(
Revision 4 02/05/79
[
If the, 'a1
<ated in h is > 55555 CFM check the last box.
The maximum release rate is 50,000 CFM.
S.33 "
gases, it is estimated that the dominant long lived activity will be Xe-133; therefore, this nuclide is used for estimated reading.
For WDG-R-1480 multip1-. the specific activity of Xe-133 in pCi/cc from by the calibration factor of WDG-R-1480 in cpm /pcice. Add to this the background of WDG-R-1480. The calibration factor and background for this monitor and for all other monitors is obtainable from the Control Room remote readout or from the local meter on the monitor.
5.34.1 For HP-R-219 gas channel, the Xe-133 specific activity in pCi/cc is obtained from h F is obtained from h The m
building purge flow is obtained from the HP-R-219 flow meter on the HP-R-219 monitor.
5.34.2 For Reactor Building purge gas channel, the Xe-133 specific activity in pCi/cc is obtained from hF is btained fr.om m
h The flow out of the stack is obtained from AH-FR-5063 for HP-R-225 and AH-FP,-5064 for HP-R-226) or AH -FF-5080 ftv R229.
f% for Rydec3en Pvge is 150 cfm.
5.35.1 For HP-R-219 iodine channel, I-131 is estimated to be the dominant activity, therefore, the specific a:tivity of I-131 is obtained frcm on the charcoal fiiter, the filter factor is obtained from h, rad V is the estimated volume to 3
be released in Ft from 5.35.2 For Reactor Building purge Iodine Channel, I-131 specific activity is obtained from h the filter factor is obtained from h, V is the volume estimated to be released in Ft 3 from The flow out the stack is from AF-FR-5063 for HP-R-225 and AH-FR-5064 for HP-R-226,or. AL Fit-Soso pr H PR 229 206 038 10.0 u k
% L % nu:.d.m A - 2h s',m mp mr.cNg'a n-CNi
1622.2 Revision 2 08/08/78 pg 5.36.1 For HP-R-219 particulate channel, Cs-137 specific activity l
from 19 is ised, V is the estimated volume to be released in 3
Ft from 5.36.2 For Reactor Building purge particulate channel, Cs-137 is estimated to be the dominant a.:.tivity. Therefore, the specific activity of Cs-137 in pCilcc is obtained from the filter factor for particulate is obtained from 20.
The flow out the I
reactor building stack is obtained from AH-FR-5063 for HP-R-i l
225 and AH-FR-5064 fo" HP-R-226,,M-FR-So80 for RFRu9. 3 V is the volume in ft" of the Reactor Building from 5.37 The quarterly allotment used to date in this quarter for both I plus particulates and Noble gases is obtained from the RECORD OF GASEOUS RELEASES LOG (see 1675). The estimated quarterly allotments
_ of I-131 and Noble gases for this release are obtained from If either of the sums are greater than 100%. then this release cannot be made without notifying the NRC.
Radiation Protection responsibilities include filling in the information contained in the boxes in parts and 59 from.
or 42 from 5.38 The Radiation Protection Supervisor / Chemist will evaluate the data, check the calculations and reco rend the release be approved or disapproved. Then the Supervisor of Radiation Protection and Chemistry / Unit Superintendent or designated representative will make a similiar review and reco=endations. The final authority for approval of a gaseous release rests with the Shif t Supervisor.
Then, and only then will the tank be released.
206 039 g
-yg a
P 8
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"TIO1Polt All Cll ANGE" D*
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~
"'J1 Thre? Mile Island Nurlear Station SIDE 1
~
)'N ~ C Figen 1001 - 5 Temporary Change hotice (TCN) b TCN NO.
NO r'E:
instructions and guidennes in AP iooi (From TCN Log inoex)
(.(
Unit No.
T musi be f oiioned on n compiering e
\\
Date 1.
Procedure W)G l$dcM km '
b dhJ Y n m.1 b]W/w tm.
G' T s tle
/
2.
Chance cinciude page numbers. paragrapn numbers, and exact wording of enange j QdZ 3.
Reason for Chance:
s l,< N f.v 0
Recommended by k,Md z/a2 /7f 5.
" <'hy / 4 > m
.2/fJ/7'/
4.
' Date Supervisor's S ature Date 6.
Duration of TCN < No longer than ninety days f rom ef f ective date of TCN or as in (a) or (b) below whichever occurs first.
(a)
TCN will be aancelled b" racedure revision issued a:a result of a Procedure Change Request to be submitted by LR t. _e 6 (Submit PCR as soon as possible)
/
[}
Supervisor Submitting TCN (b) TCN is not E afYer j
(till in circumstances Which wdi result in IGN beir4 c3nceded) 7.
(a) is the procedure on the Nuclear Safety Related Prccedure List?
(Sec. AP 1001 - Appendix B)
If "Yes", complete Nuclear Safety Evaluation. (Side 2 of this Form)
Yes No i l
y (b) is the procedure on the EnvironmentalImpact Procedure List?
(Sec. AP 1001 - Aopendix 8)
If "Yes", complete Environmental Evaluation. (Slee 2 of inis rormi Yes y No i
I (c)
Does the change etfett the intent of the original procedure?
Yes No p NOTE.
If att answers are "no" the change may be approved by the Shif t Supervisor. If Question (c) is answered "yes", the charNe must be reviewed by the PORC and approval by the Station / Unit Superintendent prior to implementation. If the answer to Question (C) is "no" the change may be approved by two members of the plant management staf f at least one of whom holds a senior reactor operators hcense on the unit affected in accordance with paragraph 3.6.4.2 of AP 1001.
8.
Review and Acoroval Block (c) "yes",(f Q Block (c) "no" Approved ( MbCM4 Av%'Mw
!N Approved A
m phett Supervisor / Foreman Date SH O Liceny,
Ca te Reviewed, !? ('t, [r,,. _
J/c/79 I
I ll g
f
.p Me Der ant Mrj Date
- 6n 4
Members
/
2 OfPORC MMb4 0
.?M/W f
Reviewed t aijar,
yyh v oHC oa te lCha.< man et
/
Contacted Approsed f
HOHC Memt;ers Ore
'# nit Superintendent j Date Approved
> # r
"'4 pt Superintehdent Ca:e NOTE-The biocir (c) "Yes" ryew and approval cham may be fo' lowed at a nytinie.
1 Aporuval 7
Manager. Generat on Quality Assurance
/
Date NOTE M G Q A acoroval rmusted only on certain Adm.n Strative Procedures listed in Enclosure 1 of AP 1001 706 040 10.
TCN is Cancened Shif t Suoe? Visor /Shaf t Foreman Ca te l
Tw 56 n.v 8 77 e
"EV Al.U A l'lO N" sIT AP 1001 Three Mile Island Nuclear Stat:an SIDE 2 Figure f 001-4 N uclear Saf ety/ Environmental impact E valuation f
~> -y [$ #
- 1. Procedure M// /4#4J 4;ord k,t., _ WJ77C 2
so.
/
tm.
T.mpo,.,v chang. Notic. No.
2.
Nuclear Safety Evaluation Does the attached procedure change:
- (a) increase the probability of occurrence or the consequences of an accident or malfunction of l
equipment important to safety ?.
. yes nod
- (b) create the poss;bility for 'n accident or malfunction of a different type than any evaluated previously in the saf ety analysis report?.
yes n03
- (c) reduce the margin of safety as defined ir. the basis for any technical specification?.
yes noE '[
l Details of Evaluation n.o...n on,.n....
to.do. ou iio-.... ~no-4ti.cn.oostion.io.
.e,.auer.o.
7 b G l:r y e +'A b&hf l~** ' ' / a' *%H
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Q'f.;Lt-k.Lu }
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(,ol C"
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y y
h
,A
- r-ic C /t.:
/
m lcfal;,nne['->'
.4 Evaluation By m [c M#
Date 2,/b /n i
/' 'i //
V" l
3.
Envirunmental imcact Evaluation
[
jfVa/{a,f Rie CJ.rnws 3 4'M Does the attached procedure change:
J/y# Ma f
(a) possibly involve a significant environmental impact?
yes no Y (if 3'a) is "yes", answer questions (b) and (c) and fill in "D etails of Evaluation" below.
If "no", state why by filling in the " Details of Evaluation" below) yes no (b) have a sionificant adverse effect on the environment?.
yes no
- (c) involve a significant environmental matter or question not previously reviewed and evaluated by the N.R.C.,
yes no Details of Evaluation i Attach aditionai page, of r.quireo)
Y O
N
!M f
h l;.- % c,$..,c h,* N,/u,h- -
DhlN f$. AM V
^
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Evaluation E Jb'.,_
e,f.f//p
- te
//
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r 4
Unit Superintendent requests PORC review l Check i' YES.U 5.
Approval f
Evaluatwn i,ccompanying PCR Evaluation Accompanyingf}CN
[
h b *, />'.
Appruval f'I
/
e
, /,',-
j < ',[ 6 SHQ Ucens se p 03fe
(
/ Unit Superintencent Da te Reviewed Yemter of P:a rt Statt Da:e i
Approval
/
l tunit Supermtendent l Date NOTE The EvaNat.on " Accompan ying a PCR'* evaiwa tion anrj approval cha.n ma y be f ollowad at ariy tirr e.
/
j 5
1622.2 Revision 1 l
06/08/78
- 5. ?9 Enter the result of 100 x estimated quantity in this release from h divided by the quarterly release allotment.
5.30 Cor:plete the upper section if this is a waste gas tank thah has I
been isolated for greater than 45 days, or if this is a Reactor Building release.
Two flows are calculated.
Transfer the lowest value to the box to the right (lowest F ).
This is the maximum m
flow rate (F ) that can be allowed in order not to exceed the instantaneous release limits.
Complete the lower section in an identical manner only if this is a waste decay tank that has been isolated for < 45 days.
f If flow rate 'n block h is too estrictive for release NOTE:
go to block
'. Complete Block as per step 5.30 above with t e concurrence of the f t Supervisor that Unit I will not release gaseous waste during this period.
5.31 Fill in the lef t side of the form for waste decay tank releases.
i i
If F is < (1,1) CFM, then this tank is too radioactive to be m
released under normal conditions; return from at this point to the Shi f t Supervisor.
If F is greater than 1.1 CFM but less than 10 m
CFM, then the WDG-FR-1484-1 set point is the value of F.
The m
l actual release rate, WDG-V-188 A/B set point will be adjusted to 90% of F.
F is obtained from @.
If F is > (10) CFM, check m
the box.
The maximum value the alarm can be set is (10) CFM,,
therefore, this value will be used. WDG-V-188 A/B will be adjusted to (9) CFM.
5.32 Fill in the right side of the form for reactor building releases.
I If F as calculated in h or is < 27777 CFM the reactor
_ m ouilding air is too radioactive to be released under normal conditions; a
return form to the Shif t Supervisor.
If F.
is > 27777 CFM but less than 55555,CFM)en AH-FR-5063 or AH-FR-5064 reading is the value
/ h.
Th'e reactor building purge rate is 25000 CFM.
F com m
~
206 042 e
m - -,
e
602-Revis m 4 02/05/79
\\
If the F calculated in is > 55555 CFM check the last box.
E q
The maximum release rate is 50,000 CFM.
~
5.33. For gases, it is estimated that the dominant long lived activity will be Xe-133; therefore, this nuclide is used for estimated reading. For WDG-R-1480 multiply the specific activity of Xe-133 in pCi/cc from by the calibration factor of WDG-R-1480 in cpm /ucicc. Add to this the background of WDG-R-1480.
The calibration factor and background for this monitor and for all other monitors is obtainable from the Control Room remote readout or from the 4
local meter on the monitor.
5.34.1 For HP-R-2i9 gas channel, the Xe-133 specific activity in pCi/cc is obtained from F is obtained from The building purge flow is obtained from the HP-R-219 flow meter on the HP-R-219 monitor.
5.34.2 For Reactor Building purge gas channel, the Xe-133 specific
/
'pCi/cc is obtained from F is obtained from Th flow out of the stack is obtained from AH-FR-5063 for
-R-225 and AH-FR-5064 for HP-R-226.
5.35.1 For HP-R-219 iodine channel, I-131 is estimated to be the dominant activity, therefore, the specific activity of I-131 i s obtainec from on the charcoal filter, the filter factor is obtained from
, and V is the estimated volume to be released in Ft from 5.35.2 For Reactor Building purge lodine Channel, I-131 specific
~
activity is obtained from the filter factor is obtained from
, V is the volume estimated to be released in Ft3 from The flow out the stack is from AH-FR-5053 for HP-R-225 and AH-FR-5064 for HP-R-226.
a 206 043 10.0
I,es.m.[.
e'
-.i f ' -
}
b "E l ^ 2b' '
! N[h r.2
+ PAnricutATES I
uc.il 2. 35x104 uCi (
^
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'OBLE G ASSES
l 1.9 x 'O o d 1
l ce b COMPLETE Tsis SECTIC 2 IF HOLD UP TIME >45 DAYS OR IF REACTOR 3LCG.
~
00 Fj- (0.15/u Cusec) :2.12 < 163 ft3/r.n tc eseci
=
i
~
u Ci!c: TOTAL from 24 f:3/ min J
I g =(6. 0x10 M /S-:c) (2.12 x 10 +3 F
3 3
2 fr / min /M /Sec) =
[
TOTAL FROM 25 3
ft /r-in O COuetETE Tsis sect:Or2 :s sOtO.ue TIME <4s OAvs
~
F) = (1. 5x10-3.p/Sec) (2.12 x 1633 ft / min /cc/sec) l
=
i p Ci/cc TOTAL COL 24 3
f t / min
'~
~
LOWEST = FM F "II 2x103 3
M ISM) (2.12 x 10'3 f:3/ min /M b se:) =
l l
G 4
TOTAL COL 25 flLL IN THIS SICE FOR WASTE CEC AY ANKS l FlLL ;N THis StO; FCR AE ACTOR CLOG.
31 0 i,Fu<i.i n l g s W j j,yl g,m, A42 O ir au < 27777 Ft 5plin DC liO! RELEASE TA:n
~
/
,,2 CO M PL E T E T HI S S E CTi O N JF'1.1 < F M 4 t o ----
RETUP. i.TG 3 SHIFT /.S'dERVISC J u,a.-F Lm.,1 S JP'01 m... M =
f+, 3 COMPi.ET~ THIS PART IF 27777<FMe55555 f t /r.
3
=r r r RELEASE RATE = FM = ElRijl it /c.in 3
/
WTenSc. i r0 p i =0.9x ri! =
d ft / min k
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/
C"PLETE THIS lGT I C"sE5555 ft /nin
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/0 RELEASE RATE = FM=-bE221 fv/r.in tv e c. es p y se rpo,s r.,
n ESriv ATE o nE 9nc s cF ya-c.-la80 anc nP-s-213-EST8M ATED AEACsNG3 OF HP.R_223 ggd gp,},p}"c 73M+G-RrG50 (Gas tQnnel) f I
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% OF QUAR 1 En LY ALLOTt?E';T USED TO D AT E I l.131 ;
!NO3LE GASSES!
% OF QUARl E4t Y ALLQ1'ENT TihS DUMP
[__ _
i l 131;[_ __,
-NOSLE GASSES' i L AST RELEASE u !?:CLUCCD.
TOTAL I131;l INOSLE GASSES-I RE L E ASE R ECC'." TEN D E D BY RACI ATION PROT. SUPE R/ FORE."AN O Rete ^5E nCCc:. "ENcEo aY suesa. rad. eRoT. s CsEM/untT suet:
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CONTROL ROOM IlLE COPY sfin5 I
_ 03/26/79 THREE MILE ISLAND NUCLEAR STATION
..77"
{
STATION HEALTH PHYSICS PROCEDURE 1622.2kE
- _ ---- %ggg RELEASING RADI0 ACTIVE GASECUS WASTE FRCM UNIT-2 Table of Effective Pages P30e Date Revision Pace Date Revision Pace Date R evision 1.0 10/05/77 0
26.0 51.0 2.0 06/08/78 1
27.0 52.0 3.0 06/08/78 1
28.0 53.0 4.0 10/05/77 0
29.0 54.0
.,,., g,
~ ~,~
5.0 10/05/77 0
30.0 n, e ~ <an c 755.0 i!:
1 ;.
i
'
- q ' ;b."..
d 'Aj 1 6.0 10/05/77 0
31.0
,J 56.0
.j h
c57.0 ' e L J 7.0 10/05/77 0
32.0 i
1.)
' ^5 8 '.D~ ~/
a
' i " M' -
8.0 06/08/78 1
33.0 9.0 03/26/79 5
34.0 59.0 10.0 03/26/79 5
35.0 60.0 11.0 08/08/78 2
36.0 61.0 12.0 10/06/78 3
37.0 62.0 13.0 02/05/79 4
38.0 63.0 14.0 06/03/73 1
39.0 64.0 15.0 10/05/77 0
40.0 65.0 16.0 03/26/79 5
41.0 66.0 17.0 10/05/77 0
42.0 67.0 18.0 03/26/79 5
43.0 68.0 19.0 02/05/79 4
44.0 69.0 20.0 02/05/79 4
45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recommends Approval Unit 2 Staff Recommends Approval Approval A
Date Approval N-Date Cognizant Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recommends Approval
///
Date 0 ate 3 3 ?
Chairman of PORC v> Chairman of PORC Unit 1 Superintendent Approval Unit 21uperinteri$ent Approval AffY N.st -
Date]' G b' 9 Date Manager Generatton Quality Assurance Aporoval A;
Date TMI SS A Rev s/77 206 046 5
w 1622.2 Revision 0
~
10/05/77 THREE MILE ISLAND NUCLEAR STATION STATION HEALTH PHYSICS PROCEDURE 1622.2 RELEASING RADI0 ACTIVE GASE0US WASTE FROM UNIT-2 1.0 PURPOSE This procedure describes the regulations applicable to radioactive gaseous discharges to unrestricted areas and the monitoring programs designed _ ensure compliance with these regulations.
2.0 DISCUSSION 2.1 Radioactive gases result primarily from the escape of gaseous fission products from the fuel, and by neutron activation of constituents in the water and air in the immediate vicinity of the core. Those radioactive gases that hre produced in or released to the reactor coolant should ultimately be collected in the low pressure vent header system and compressed in the waste gas decay tanks for decay and re-use or release to the atmosphere. Normal hold-up time in the waste gas decay tanks will be at least 45 days. Shorter hold-up times can be employed orovided the appropriate environmental tech. specs. are satisfied.
2.2 The other source of gaseous waste comes from purging the atmosphere of the reactor building. Radioactive gases in the reactor building come from neutron activation of the atmosphere or from gaseous leaks from the reactor coolant system.
2.3 Radioative gases are released through the unit vent from the Reactor Building exhaust system, main condenser vacuum pump exhaust, fuel handling exhaust, auxiliary Building exhaust and Waste Gas Decay System. The gases are continuously monitored and recorced. This is a continuous release and is samoled periodically as per requirements in the Tech. Specs.
206 047 1.0 i
1622.2 Revision 1 06/08/78 4
E.4 Analysis of gaseous ef fluent is necessary to ensure adherence to the "as low as reasonably achievable" philosophy and to assure compliance with Environmental Technical Specifications. Environmental Technical Specifications limit the release rates for noble gases, H, r dioactive iodine and particulates.
3 2.4.1 The Technical Specifications contain two types of limits (in-stantaneous release rates, and quarterly average release rates) for two classes of radioactive materials (Iodine-131 and particulates with half-lives Treater than 8 days, and gross gaseous activity. Under unusual conditions, the quarterly average limit used in this report may be increased, but this requires notification of the NRC.
2.4.2 The values used for instantaneous releases are as follows:
5 3 Qi < l.2 x 10 3 /sec Gross Gaseous:
MPCi Where Qi = uCi/sec release rate I
MPCi = 10CFR20, Appendix 3, Table 11, Col. 1 I
Iodine-131 and Particulates with half lives greater than 8 days: < 0.3 uci/sec.
The release flow rates are adjusted to insure that these limits are not exceeded. The above limits are applicable if the gas decay tanks are held for greater than 45 days and for Reactor Building Purge.
If the waste gas decay tank is to be held for less than 45 days the following limits apply:
2.0 20(3 048 i
1622.2 Revision 1 06/08/78
= 1 4 x 103 g3/sec Qi 2
Gross Gaseous:
MPCi Iodine-131 and Particulates with half lives greater than 8 days: 1 003 uci/ wc.
0 2.4.3 The working quarterly average limits are as follows:
3 3 Of
=1 4.8 x 10 g /sec Gross Gaseous k MPC' Iodine-131 and Particulates with half lives greater than 8 days: 1 0.006 uci/sec.
If these limits are exceeded, then the commission must be notified within 30 days.
2.4.4 Under unusual conditions, the following maximum quarterly average limits shall not be exceeded.
4 3 1
Qi, = 1 9 x 10 M /sec Gross Gaseous: I MPC1 Iodine-131 and Particulates with half livas greater than 8 days: 1 0.024 aci/sec.
2.5 The release of radioactive gaseous effluents is contiaucusly monitored by VAR-748 (Condenser Vacuum Pump Discharge), WDG-R-1480 (Waste Gas Decay Tanks), HP-R-219 (Waste Gas Relief Header Unit Vent) and HP-R-225/HP-R-226 (Reactor Building Purge Exhaust). Monitors HP-R-219, HP-R-225 and HP-R-226 detect radioactive noble gases, iodine and particulates. VAR 748 and WDG-R-1480 detect only gaseous
~
radionuclides.
3.0 206 049
1622.2 Revision 0 i
10/05/77 2.5.1 In the event one of the above monitors becomes inoperable, grab samples will be taken as required in the Technical Specifications.
2.5.2 Analysis performed will be as designated in the Environmental Technical Specifications.
3.0 REFERENCES
3.1 FSAR, Unit 2.
3.2 Environmental Technical Specifications.
3.3 1606, Air Sampling for Radioactive Iodine.
3.4 1608, Air Sampling for Tritium.
3.5 1951, Determination of Tritium, and 1958, Gamma Spectrcmeters.
3.6 2104-1.11, Nuclear Plant Sampling.
3.7 L0 CFR 50.
3.8 10 CFR 20 3.9 1631.2, Sampiing of Waste Gas Cecay Tanks and Reactor Building 3.10 1675, Radioactive Waste, Release Records.
4.0 E0VIpMENT 4.1 Charcoal Cartridges.
4.2 2" particulate filters or equivalent 4.3 Geli Cetection System
, 4.4 Sampling container 4.5 Liquid Scintillation Cetection System 5.0 OPERATING INSTRUCTIONS Prior to releasing gaseous effluents to the environment from the Waste Gas Cecay Tanks or the Reactor Building, a Gaseous Release Permit must be obtained.
4.0 206 050 5
1622.2 Revision 0 10/05/77 NOTE:
In these operating instractions, the item number of section 5 will refer to the identically numbered sections of the Permit.
5.1 Ths Shift Superviosr initiates the request for release, and is responsible to provide items (l)through(3) 5.2 The appropriate box is checked to indicate whether the Reactor Building or a specific decay tank is to be sampled, analyzed and released.
5.3_ In order that no additional gas is added to the waste gas decay tanks before the release is complete, the tank is isolated and conspicuously labeled with a CO NOT OPERATE tag. The date and time of tagging is recorded. The pressure in psig is recorded.
This is obtained from the Waste Gas Control panel for the W3ste Gas Decay Tanks; and from the Control Room for the Reactor Building Pressure.
The Estimated Volume to be released is calculated as indicated and converted to cc. The form is then turned over to the Radiation Protection Department for completion of items ({)through(f )
5.4 The next sequential Unit release number is assigned and recorded in the RECORD OF GASEQUS RELEASES LCG (see 1675).
5.5 The appropriate box is checked.
5.6 The Radiation / Chemistry Technician /Jr. will then sample the designated tank or reactor building in accordance with 1631.2, Health Physics Procedure for Sampling of Waste Gas Decay Tanks and Reactor Building.
The sample collector will record the date anc time of sampling; and tag with the appropriate radiation label.
5.0 206 05i 5
~~
1622.c Revision 0 10/05/77 5.7 The Radiation / Chemistry Technician /Jr. responsible for performing analysis, and the Radiation Protection Supervisor / Foreman responsible for approving tne data in sectionhtbrough @ both sign in the appropriate location after completion of the analysis.
5.8 The date and time of each analysis is recorded.
5.9 The estimated volume to be released in cc is obtained fromh 5.10 The Station Chemistry Procedure Number followed in performing the i
- equired analyses is recorded. The Tech. Spec. limits are divided into limits for two classes of radioactive materials:
Iodine-131 and Particulates with half-lives of greater than 8 days, and noble gas and H activity exclusive of Iodine-131 and Particulates with 3
half-lives greater than 8 days. Therefore, the two classes of material are calculated separately. The sampling consists of drawir.g a known volume of air through a sampling train consisting-of a Particulate Filter, and Iodine Filter (charcoal), and then taking a gas samole of the effluent of the sample train. The three samoles are analyzed separately, therfore, there are three sections of columns on the form.
The nuclides listed are those expected to be found, or those required to be tabulated in the 1675. All peaks must be quantified.
If additicani nuclides are found, add them to the form.
NOTE:
If the Gamma Analysis is not performed in accordance with 1958.3, Perform Steps 10 through 17.
5.11 The volume sample counted is recorded.
5.12 The samole counting time is recorded.
5.13 The gross number of counts, including background, are recorded.
6.0 206. 052 i
N 1622.2 Revision 0 10/05/77 5.14 The background counting time is recorded.
5.15 The total background counts are recorded.
5.16 The net sample count-rate is calculated.
GROSS COUNTS h ]
dACKGROUND COUNTS h)
[ SAMPLE COUNT TIME h )
hACKGROUND COUNT TIME b ]
5.17 The ".' coutttiag error (2 6) incalcul.ated.
[ GROSS COUNTS h ] + BACXCROUND COUNTS (f5))
2 x 100 x/']SAPPLE COUNT TIME @ ] 2
[ BACKGROUND COUNT TIME h 2
/
x NET SAMPLE COUNT RATE @
5.18 The gamma abundance for the energy listed is tabulated for the nuclides expected to be of importance. All significant peaks must be identified.
If other nuclides are found, or if gamma's other than those taculated are used for the isotopic quantification, the appropriate gamma abundance shall be obtained from TABLE,0F THE ISOTOPES.
5.19 Record the Specific Activity (SA).
Refer to the appropriate S.C.P for further information.
The efficiency of the counter is obtained from charts in the counting room.
NET SAMPLE COUNT RATE (52)
S. A.= (AMPLE VOLUME USED] { GAMMA ABUNDANCE]}.22 x 10kF 6
5.20 The sample is taken before the HEPA filters and charcoal filters which are in the release path of the gaseous release. There fore,
to calculate the concentration released to environment, the concentration 7.0 206 053 i
1622.2
~
Revision 1 06/08/78 in the sample is multiplied by the FILTER FACTOR. This term is the
~
fraction passing the filter, and is calculated by (1 minus the Filter Retention Efficiency). The methods of measurement are not exacting, and the efficiency will vary with the time, chemical composition, and particulate size. A conservei ve factor of D.1 (90% filter retention) is used for particulates and iodine, and 1.0 for gases.
5.21 The MPC's for gases identified are tabulated.
If other nuclides are identified, enter the appropriate value from 10 CFR 20, Appendix B, Table 11, Column 1.
5.22 Enter the result of Specific Activity from @ multiplied by Filter Fraction from h divided by MPC frcm @, for Noble gases and H in(2J.
3 5.23 Enter the product of Specific Activity frcm h and Filter Fraction from h, for Iodines and Particulates found inh).
5.24 Enter the sum of all nuclides in the particulate and charcoal filters inh 5.25 Enter the sum of all nuclides in the gas sample in@.
5.26 Transfer the value from (h to the top line and the value from h to the bottom line.
5.27 Transfer the estimated volume to be released from @.
5.23 Enter the estimated quantity to be released (product of each line of h andh ) in the corresponding line.
The next unnumbered column, (the quarterly release allotment) is the product of the applicable quarterly average limit (see 2.4.3) and the number of seconds in a quarter of a year. This is the Quarterly Release Allotment.
The units for gaseous releases have been converted from M to cc.
8.0 206 054 5
1622.2 Revision 5
~
03/26/79 5.29 Enter the result of 100 x estimated quantity in this release from (28 divided by the quarterly release allotment.
5.30 Comple'.e the upper section if this is a waste gas tank that has been isolated for greater than 45 days, or if this is a Reactor Building release. Two flows are calculated.
Transfer the lowest value to the box to the right (lowest F ).
This is the maximum m
flow rate (F ) that can be allowed in order not to exceed the m
instantaneous release limits. Complete the lower section in an identical manner only if this is a waste decay tank that has been isolated for < 45 days.
If flow rate in block 60) is too restrictive for release NOTE:
0 90 to block 30 Compl Me Block (f0A as per step 5.30 acovewiththYc.oncurrence of the $7fift Supervisor that Unit I will not release gaseous waste during this period.
5.31 Fill in the left side of the form for waste decay tank releases.
If F is < (1.1) CFM, then this tank is too radioactive to be m
released under normal conditions; return frcm at this point to tne Shift Supervisor.
If F is greater than 1.1 CFM but less than 10 g
CFM, then the WDG-FR-1484-1 set point is the value of F.
The actual release rate, WDG-V-188 A/S set point will be adjusted to is obtained from @.
If F is > (10) CFM, check 90". o f F.
F g
m the box. The maxitum value the alarm can be set is (10) CFM, therefore, this value will be used. WDG-V-188 A/B will be adjusted to (9) CFM.
5.32 Fill in th right side of the form for reactor building releases.
If F a,s alcul ted in @ or @is<27777CFMthereactor
/ggghin qtro(is too radioactive to be release p retult.orm to the Shift Supervisor.
If F is > 27777 CFM but less m
than 55555 CFM, then AH-FR-5063 or AH-FR-5064 reading is the value F,
from @.
The reactor building purge rate is 25C00 CFM.
}
206 055 9.0
1622.2 Revision 5 03/26/79 If the F calculated in @ is > 55555 CFM check the last box.
3 The maximum release rate is 50,000 CFM.
5.33 For gases, it is estimated that the dominant long lived activity will be Xe-133; therefore, this nuclide is used for estimated reading.
For WDG-R-1480 multiply the specific activity of Xe-133 in uCi/cc from @ by the calibration factor of WDG-R-1480 in cpm /pcice. Add to this the background of WCG-R-1480. The calibration factor and background for this monitor and for all other monitors is obtainable from the Control Room remote readout or frcm the local meter on the monitor.
5.34.1 For HP-R-219 gas channel, the Xe-133 soecific activity in uCi/cc is obtained frem @F is obtained from @ The m
building purge flow is obtained from the HP-R-219 flow meter on the HP-R-219 monitor.
5.34.2 Fcr Reactor Building p.,rge gas channel, the Xe-133 specific activity in pCi/cc is obtained from
@F is cbtained from n
@ The ficw out pd the stack i.s ob;af(u i d frcm AH-FR-5063 for
/Ja
-7 Y o
2-77-57 28AnggFR-5064yorHP-R-226.
5.35.1 For HP-R-219 iodine channel, I-131 is estimated to be the dominant activity, therefore, the specific activity of I-131 is obtained from @ on the charcoal filter, the filter factor is obtained from @, and V is the estimaced volume to 3
be released in Ft from @
5.35.2 For Reactor Building purge Iodine Channel, I-131 specific activity is obtained from h the filter factor is obt.ined from @, V is the volume estimated to be released in Ft 3 from @ The flow out the stack is from AH-FR-5063 for HP-R-225 and AH-FR-50F' for P/-R-225.
LN s j p w 'b 206 056 oo i
~
1622.2 Revision 2 08/08/78 1
9 5.36.1 For HP-R-219 particulate channel, Cs-137 specific activity froni is used, V is the estimated volume to be released in 3
Ft from 3.
5.36.2 For Reactor Building ourge particulate channel, Cs-137 is estimated to be the dominant activity. Therefore, the specific activity of Cs-137 in uCi/cc is obtained from 19, the filter factor for particulate is obtained from 20. The flow out the reactor building stack is obtained from AH-FR-5063 for
-R-fGA/W' -T? 'h. 3 225 and AH-FR-5064 for HP-R-226
/ is the y lume in ft ci the Reactor Building from 3.
5.37 The quarterly allodeni used to date in this quarter for both I plus particulates and Noble gases is obtained from the RECORD OF GASEOUS RELEASES LOG (see 1675). The estimated quarterly allotments of I-131 and Noble gases for this release are obtained from 2 9'.
If either of the sums are greater than 100%. then this release cannot be made without notifying the NRC.
Radiation Protiction responsibilities include filling in the information contained in the boxes in parts 39 and 42.
32' 39 from 31 or 42, from 33, 34, 35, 36 5.38 The Radiation Protection Supervisor / Chemist will evaluate the data, check the calculations and recommend the release be approved or disapproved. The'1 the Superviscr of Radiation Protection and Chemistry / Unit Superintendent or designated representative will make a similiar review and recommendations.
- final authority for approval of. a gaseous release rests with the Shift Supervisor.
Then, and only then will the tank be released, 11.0 206 057 h
--=a-O e m
-e-=~
-+
e-
=m--
1622.2 Revision 3 10/06/78 NOTE:
Just prior to release of a waste gas decay tank WDG-R-1480 must be proven operable by a test using the installed check source or equivalent.
5.39 Operations is responsible for completion of the remaining portions of sections through The alarms and valves are set as indicated.
NOTE:
Prior to release of gas dacay tank or Reactor Building, Operations will notify the Radiation Protection Department prior to release, to insure the changing of HPR-219 particulate and charcoal cartridge.
40 Time, date and pressure are filled in when the release starts and ends.
5.41 Mark the records as indicated at the beginning and at the end of the release.
5.42 Record the appropriate instrument readings before, during and after the release.
5.42.1 Insure that a gas and tritium sample have been obtained at approximately the 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> point of each reactor building purge.
5.43 The Shift Supervisor will verify that all data frca through are compeite and accurate. After signing the form, it is returned to the Radiation Protecticn Department for completion.
NOTE:
Operations will notify the Radiation Protection Department after termination of release, to insure the changing of HPR-219 particulate and charcoal cartridge.
12.0 206 058 Ab
=
-..-----+w-
--+w-
=- -
.m m
m_
1622.2 Revision 4 02/05/79 5.44 The ac;ual release volume is calculated based upon readings taken during the release AP is obtained from For reactor _ building purges, Fm is from and t is from (total time of release).
5.45 The actual quantity released is calculated by multiplying the specific activity from hby the actual release volume from h NOTE 1:
For reactor building purges, the additional quantities of isotopes released due to primary system leakage must be accounted for. Threrfore, complete steps 5.46 through 5.53 for reactor building purges only.
NOTE 2:
For particulate and Iodine actual quantities released, the HP-R-219 filters are removed and counted for activity.
See 1675.
5.46 Total in-leakage time is calculated. Record the time the purge stopped from and the time the Reactor Building was sampled from The in-leakage time is the total time in minutes between these two times.
5.47 Total in-leakage volume is calculated by multiplying the purge rate 4
from by the total in-leakage time from by 2.832 x 10.
5.43 List all gasses identified from gas and tritium samples taken from HPR 219 at approximately the 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> point of the purge.
Prior to sampling, verify with the Control Rool which purge exhaust lines are in use.
5.49 Record the specific activities of those isotopes identified in the gas and tritium samples taken during the purge.
5.50 Record the MPC values of those isotopes identified in the samples taken during the purge.
5.51 Divide the specific activities in by the MPC values in 13.0 206 059
1622.2
~__-
Revision 1 G5lDal7a 5.52 Summarize all h entries.
~
5.53 The additicr,al quantity due to in-leakage (in curies) is calculated by multiplying the specific activities in @ by the total in-leakage volume from @ by 10-6 5.54 For those isotopes listed in h, the quantities releases as listed in h are recorded.
5.55 The actual quantities released (including in-leakage) are calculated by adding columns @ and h for each isotope.
5.56 Enter total from h.
5.57 Enter volume released from h 5.58 Quantity this release is calculated by multiplying h by h.
5.59 Enter the result of 100 times the quantity thi.s release, from h,
16 divided by the quarterly release allotment,1.9 x 10 cc.
5.60 Station Superintendent / Unit Superintendent's approval is required prior to extending purges beyond 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with the reactor coolant system pressurized. Additional samples must be obtained at. this time.
14.0 206 060
1622.2 b
h7 SHIFT SUPERVISOR REO.UESTS RELEASE PERMIT TANK IS SAMPLED AtJD At1ALYZED RELEASE CALCULAT10:15 ARE MADE TO ASSURE THAT I?! S T At4 T A N E Q U S O R QUARTERLY Lir41 TS ARE S'ET ESTIMATED READit:GS ARE CALCULATED FOR E F F LU EtlT MONITORS APPROVAL TO RELEASE IS GRAt!TED 1
RELEASE IS MADE.
RELEASE DATA ARE RECORDED l
CALCULATI0tlS ARE MADE OF ACTUAL 0.UAttiTY RELEASED l
15.0 206 06i
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_ll.131; INOSLE GAS $35
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INOSLE GAGSEE NOSLE GASSES i LAST RELEASE a INCLUCED.
TOTAL I-131; RELEASE RECO?.*"ENCED BY RACI ATION PROT. SUPER / FORE'W1 O RELEASE ncCC?.".:cNoED cy SUPER. RAD. PROT. & CHEM / UNIT SUP' O RELEASE APPGCVED SY SHIFT SUPERVISC R
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. TOTAL COL 25 j
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18,0
- e
1622.2 Revision 4
~
02/05/79 Total Noble Gas and Tritium Concentrations During Reactor Building Purges The following sections will be filled out for reactor building purges only.
Total in-leakage Time:
Time Purge Stopped Time
_ Date Time of Original Rx Sample Time Date Total Time Min.
Total in-leakage Volume:
Volume =
CFM x min x 2.832 x 10
=
cc n
D N) 6 6
6 6
SpeMfic Additional Actual Qty.
Activi ty Curies
- Released, (uCi)
S.A due to Qty. Released including Isotoce
( cc)
MPC MPC In-Leakace from in-leakace l
1 l
f h E=
n 5
b Quant @1ty this D
To ta Frcr.
Volume Ortrly. Release i Allotment 52) xel eased (U)
Release Allotmen t This Release l
l I-cc cc 1.9 x 10 cc
- 06 065 20.0