ML20033A353
| ML20033A353 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 10/15/1981 |
| From: | Thornburg R PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML16340C099 | List: |
| References | |
| EPR-2-01, EPR-2-1, NUDOCS 8111250238 | |
| Download: ML20033A353 (62) | |
Text
c.
c NUMBER EP R-2
@GW3 Pacific Gas and Electric Company t
REVISICP, 3 DATE 8/11/81 r'
OEPARTMENT OF NUCLEAR PLANT OPERATIONS p
e I i
OlABLO CANYON POWER PLANT UNIT NO(S) 1&2 PAGE 1 OF 57 h
l; 4
EMERGENCY PROCEDURE TITLE.
RELEASE OF AIRBORNE RADIOACIIVE MATERIALS
( W' i S
/
APPROVED:
PLANT MANAGERI/
DATE SCOPE This procedure describes the steps to be taken to evaluate and recover from the consequences of an airborne release that results in an Unusual Event, Alert, Site Area, or General Emergency.
It does not describe the operation of the plant equipment necessary to terminate or minimize the release.
This latter subject is covered in the appropriate OP series Emergency Procedure for the particular release mechanism.
SYMPTOMS 1.
The following symptoms indicate that an airborne release may be occurring in the Controlled Area:
a.
There is actual or suspected leakage of water, steam, or noncondensible p*y gases from any vessel or piping system containing primary coolant, N
liquid radwaste, or gaseous radwaste.
b.
Damage occurs to a submerged, irradiated fuel assembly with the resultant release of signifiennt quantities of noncondeusible gases.
c.
Alarms occur on CJMs.
d.
A fire occurs ir. r411oactive materials.
e.
G-M type survey instruments in the area begin to show an increasing background count rate.
NOTE: The external dose rate produced by airborne levels near MPC is very low and may not be noticed on a Rad Owl.
However, it produces a noticeable increase on a G-M survey instrument, f.
A major radioactiva material spill occurs.
2.
There are numerous indications available in the control room to identify and diagnose a possible airborne release.
These vary depending upon the mechanism of the release, and are covered in detail in the OP series Emergency Procedures and EP G-1, " Accident Classification and Emergency Plan Activation." However, the most likely f
symptom (s) will involve alarms on at least one of the area and/or process radiation monitors.
811125d238 811116 PDR ADOCK 05000275 F
PDR r
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 REVISION-3 DATE 8/11/81 PAGE 2 OF 57 O
RELEASE OF AIRBORNE RADIOACTIVE MATERIALS l
TITLE.
IMMEDIATE ACTIONS 1.
Personnel in the Area Unless qualified and equipped with appropriate monitoring and/or a.
evacuate the area and proceed to access control.
respiratory equipment, b.
Notify the control room.
2.
The Shift Foreman (interim Site Emergency Coordinator) shall:
a.
Clear the affected area.
This can be done most efficiently by sounding the emergency signal.
The emergency signal shall be sounded for the following circumstances:
- 1) J.irborne contamination is widespread.
Refer to EP R-4, "High External Radiation (In-Planc)."
- 2) Major damage occurs to plant equipment.
Refe:- to appropriate OP procedure or EP G-1, " Accident Classificatior and Emergency Plan Activation."
- 3) Site evacuation is necessary.
Refer to EP G-5, " Evacuation of Nonessential Site Personnel."
- 4) Mobilization of personnel is necessary.
Refer to EP G-2,
" Establishment of the Onsite Emergency Organization" and EP G-4, " Personnel Assembly and Accountability,"
(
- 5) The Shift Foreman deems it necessary.
b.
Establish an appropriate interim onsite emergency organization in accordance with EP G-1, " Accident Classification and Emergency Plan Activation."
- 1) Assign the Emergency Liaison Coordinator and the Liaison Assistant to begin notification of offsite agencies and plant staff.
2)
Assign operators to isolate the release using appropriate OP series emergency procedures.
- 3) Have the Emergency Evaluations and Recovery Coordinator (normally the Shif t Engineer) begin preliminary evaluation and classification of the actual or potential severity of the release.
Instructions for performing this evaluation are contained in the Subsequent Actions scetion of this procedure.
~
OtABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3
DATE 8/11/81 PAGE 3
OF 57
)
f TITLE:
RELEASE OF AIRBORNE RADIOACTIVE MATERIALS Treat any injured personnel in accordance with EP R-1, " Personnel z.
Injury (Radiological Related and/or Overexposure."
SUBSEOUENT ACTIONS 1.
Subsequent Actions Common to All Events Establish an appropriate long-term onsite emergency organization in a.
accordance with EP G-2, " Establishment of Onsite Emergency Organization." As a mi n 4==, notify the following personnel:
- 1) Plant Manager (Long-Tem Emergency Coordinator)
- 2) Plant Superintendent
- 3) Supervisor of Chemistry and Radiation Protection b.
Alert offsite groups in accordance with EP G-3, " Notification of Offsite Organizations."
- 1) Prompt notification of County and other offsite authorities should occur within about 15 minutes j for the Unusual Event class and sooner (consistent with the need for other emergency actions) for other classes. Use Form 18-9221, Emergency Notification Record.
NOTE: As a minimum, notify the NRC Operations Center within one hour via the " hot line."
This notification is required pursuant to 10CFR50.72 as an event requiring initiation of the licensee's emergency plan or any section of that plan.
- 2) Periodic updates on the status of the emergency shall be provided to the County and other offsite authorities, at least every 15 minutes. Use Form 18-10262, Emergency Status Form, giving as much infomation as is known at the time.
2.
Classify the Emergency a.
General
. 1)
Ic a large extent, subsequent actions are based upon the potential severity of the occurrence, as identified by the emergency classifi-cation. Therefore, the Emergency Evaluations and Recovery Coordinator (EERC) shall inform the Site Emergency Coordinator at the earlies O
possible time whether the emergency is classified as an Unusual V
Event, Alert, Site Area or General Emergency using EP G-1, " Accident Classification and Emergency Plan Activation."
OtABLO CANYON POWER PLANT UNIT NO(S) 1 & 2 NUMBER EP R-2 REVISION. 3 DATE 8/11/81 PAGE 4 OF 57
/
TITLE; RELEASE OF AIRBORNE RADI0 ACTIVE MATERLU.S l
I NOTE:
If core damage is a possibility, the Shif t Engineer should be directing his attention towards its assessment and the task of classifying the accident should be assigned to someone else, such as a Senior Control Operator.
- 2) The EERC shall keep the Site Emergency Coordinator apprised of any escalation or reduction of the emergency classification.
b.
How to Make Initial Classification of the Emergency There are four general methods for initially classifying an emergency:
1) accident scenario, 2) estimate release rate,
- 3) Use accident summary sheets, or
- 4) perform offsite monitoring.
("'s Each is discussed below.
- 1) Classify Emergency Based Upon Emergency Scenario l
The preferred method for initially classifying the emergency is to diagnose the most likely cause (LOCA, steam line break, gas decay tank rupture, etc.) and base the classification on this information.
a) Co to the appropriate OP series procedure and use the guidance contained therein to classify the accident.
b)
If the emergency does not fit any OP series procedure, or if the guidance in the OP series procedure is unclear, go to EP G-1.
EP G-1 gives examples of typical emergency scenarios which fall into each accident classification. Classify the emergency at a level consistent with the scenario which most closely approximates the actual situation, c)
If multiple emergency situations are occurring simultaneously, such that the probability of a release of radioactive materials is increased over what it would be for a single occurrence, classify the emergency one level higher that it would otherwise have been based on the most severe single occurrence.
l l
l l
DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3
TITLE:
RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
- 2) Classify Emergency Based On Release Rate 4
a) General j
The second best way to classify the emergency is to estimate the magnitude of the release rate. However, using release rate information to classify the emergency is subject to the following limitation:
(1) If e classification based upon the emergency scenario is
.e severe than would be warranted by release data, conservative (emergency scenario) classification.
use m for this is that EP G-1 specifies a classifi-The cation.
many events based upon the potential for a reles*
51s conservative classification must be used
.tal release does not materialize.
ever..
c.
(2)
If the relea e data indicates a classification more severe than the classification based upon the scenario, use the conservative classification based on release
~.
'O data, if the release data is considered to be reliable.
(3) Both whole body and thyroid exposure must be considered when making a classification based upon release data.
Classify the emergency based upon the most conservative of these two values.
b)
Dose and Release Rate Criteria for Classifying Emergency !
The criteria for classifying an emergency based on dose and release data are summarized in Appendix 1.
c)
Instructions Regardless of the particular instruments used, the basic technique is as follows:
(1) Determine the classification criteria using Appendix 1.
Use real meteorological data if possible, or default values is necessary.
(2)
Estimate the noble gas and iodine release rates ih curies /second. There are numerous possible techniques for doing this. Appendix 2 gives detailed instructions for the following co m n methods:
(a) Use of plant vent noble gas monitors RE-14 or RE-29.
i l
DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REWSION 3
DATE 8/11/81 p
PAGE 6 OF 57 TITLE:
RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS (b) Use of plant vent fodine monitor RE-24.
(c) Use of containment air sample results if leak is via containment purge or other path out of containment.
(d) Use of RCS coolant sample results during S/G tube rupture.
(3)
Compare the estimated release rate data with the criteria values.
3)
Classify Emergency Using Accident Summary Sheets Appendix 6 contains summary sheets for each accident analyzed in the FSAR. They can be used to estimate the severity of an accident.
l
- 4) Classify Emergency Based On Field Monitoring Data l r I
a) General As discussed in Appendix 1, the accident classification definitions are based upon dose rates at the site boundary.
In theory, therefore, field data taken at the site boundary should provide a direct method of classifying the accident.
In practice, this is only the third best technique because there is the possibility that you will miss the plume, and also because it takes considerable time to deploy monitoring teams.
b)
Instructions Appendix 6 summarizes the basic formulas related to environmental monitoring that are useful in classifying i
accidents and in projecting doses.
NOTE:
At this point, the emergency is classified.
Go to Steps 3, 4, 5, or 6 for Unusual Event, Alert, Site Area Emergency, or General Emergency respectively.
3.
Subsequent Actions for an Unusual Event Evaluate the internal exposure received by affected personnel using a.
the instructions given in Emergency Procedure R-1, " Personnel Injury l
(Radiological Related) and/or Overexposure."
G
OtABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3 DATE 8/11/81 es PAGE 7 OF 57 TITLE RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
(
I Make the best possible quantification of the extent of any offsite b.
release using the results of air samples, effluent monitors, envorinmental monitoring, or other techniques.
Conduct appropriate c,leanup and reentry operations.
c.
NOTE:
General guidelines for cleanup and reentry are contained in.
Close-out the event with a verbal summary to offsite agencies and d.
complete the following written reports:
- 1) Plant Problem Report (see Nuclear Plant Administrative Procedure C-12).
- 2) Written summary to NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
Subsequent Actions for an Alert Activate the Technical Support Center, the Emergency Operations Facility, a.
and the Operational Support Center in accordance with EP's, EF-1, O
EF-3 and EF-2, respectively.
If the release has the potential for necessitating onsite protective b.
measures (i.e., if it is more than about 10 times the threshold levels for an Alert), make a check of downwind onsite assembly areas to determine if any protective measures are needed for onsite personnel.
If the results of the initial assessment indicate that site personnel c.
are receiving significant exposures, and that evacuation can measurably reduce it, the Site Emergency Coordinator shall order their evacuation either offsite (preferred) or to an upwind site location (if the duration of the release is expected to be very short).
d.
Provide periodic meteorological assessments to offsite authorities and, if any releases are occurring, dose projections for actual releases.
- 1) Activation of EARS is the preferred method for transmitting dose projections offsite.
2)
If EARS is not available in either the automatic (EARAUT) or manual (EARMAN) mode, perform appropriate hand calculations using Appendices 2 - 7 of this procedure.
Perform Comprehensive Follow-up Surveys Onsite e.
h' 1)
Personnel Asse, ably Areas Although a preliminary assessment should have been made at personnel assembly areas, if the release was substantially in
. - = =..
---a
.q_e._
- M_ _ -
DIABLO CANYON PCWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION. 3 DATE 8/11/81 PAGE 8 OF 57 TITLE RELEASE OF AIRBORNE RADIOACTIVE MATERIALS k
h excess of limits, it is wise to check or recheck these I
locations as time and conditions pemit, with the following objectives:
l a) To verify that long-term evacuation is not required if personnel were not previously svacuated based upon the initial assessment.
b) To obtain iodine and particulate samples if these were not obtained earlier (assuming that significant quantities of iodine and particulate matter were released, and that the cloud has not long since passed),
c) To run smear surveys to see whether decontamination is required.
If significant activity is found, the smear pans should be counted on the MCA to assist in decemining the isotopes to which persons might have been exposed.
(If significant personnel exposure is suspected, the persons should also be whole body counted in accordance with Emergency Procedure R-1).
- 2) Remainder of Site Downwind areas which may have been contaminated should be checked for contamination to provide data for determining the necessity and extent of cleanup operations.
Smear samples should be retained for subsequent isotopic analysis if required.
f.
Perfom Offsite Monitoring as Warranted If the estimate of curie release and/or onsite monitoring indicates that offaite effects are negligible (as they would be for most Alert conditions), offsite monitoring may not be necessary. However, if there is a realistic possibility that offsite locations may have become contaminated, local government agencies should be alerted and on offsite monitoring program should be instituted for the following purposes:
1)
Deternine the need for long-term decontamination or impoundment of foodstuffs, even if offsite personnel evacuation is not required.
NOTE: These decisions are the responsibility of local government agencies. However, current governmental recommendations are summarized in EP RB-10.
2)
Allay any public concern.
- 3) Obtain background data for reports to regulatory agencies.
l
___T_______~_____________________________________
OtABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3
DATE 8/11/81 PAGE 9
OF 57 TITLE:
REI. EASE OF AIRBORNE RADIOACTIVE MATERIALS
('G Conduct appropriate post-accident cleanup and reentry operations.
g.
h.
Close-out the event with a verbal summary to offsite agencies and complete the following written reports:
1)
Plant Problem Report (see Nucienr Plant Administrative Procedure C-14).
- 2) Written summary to NRC within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
5.
Subsequent Actions for a Site Area Emergency Activate the Technical Support Center, the offsite Emergency Operations a.
Facility and the onsite Operational Support Center in accordance with EP 's, EF-1, EF-3, and EF-3, respectively.
b.
Consider evacuation of nonessential site personnel.
If it is likely that a release is occurring, or will occur which exceeds the threshold for a Site Area Emergency (i.e.,17mR WB or 85 h
mrem thyroid at site boundary), evacuation of site personnel either W
offsite (preferred) or to an upwind site location (if the duration of i
b the release is expected to be very short).
Provide periodic meteorological assessments to offsite authorities c.
and, if any releases are occurring, dose projections for actual releases.
- 1) Ac.tivation of EARS is the preferred method for transmitting dose projections offsite.
2)
If FARS is not available in either the automatic (EARAllT) or manual (EARMAN) mode, perform appropriate hand calculations using Appendices 2 - 7 of this procedure.
d.
Perform Offsite Monitoring
~
1 A Site Area Emergency release is of sufficient magnitude such that some offsite protective measures, such as evacuation of persons in portions of the LPZ, or long-term impoundment of foodstuffs, may be required near the site boundary.
Therefore, an offsite monitoring program should be established for the following purposes:
1)
Initially the program should be directed toward identifying those areas where personnel evacuation may be necessary to prevent persons fror, exceeding the recommended evacuation criteria do.es of 500 mrem wbole body and/or 5 rem thyroid.
lb G
OlABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION - 3 DATE 8/11/81 PAGE 10 OF 57 TITLE:
RELEASE OF AIRBORNE RADIOACTIVE MATERIALS l
I
- 2) Once any immediate evacuation is accomplished, the program should be set up to determine the need for long-term decontmination or impoundment of foodstuffs, which may be desirable even in areas where prompt personnel evacuation was not required.
NOTE: These decisions are the responsibility of local government agencies. However, current government recomendations are summarized in EP RB-10.
- 3) The program should provide background data for any necessary reports to regulatory agencies.
- 4) The program should provide the data to answer questions of public Concern.
Take Protective Measures for Members of the Public (if required) e.
Tabla 1 summarizes recommended protective actions for exposure to a passing plume. The area where action is taken must include the entire area in which the dose c-iteria have been exceeded.
A somewhat larger m
area than this should be considered.
I
(
l If evacuation is required, determine which area is to be evacuated. On a map, draw an arrow point 1ng in the downwind direction. Mark a 22.5" l
l sector on,both sides of thfs downwind sector.
Evacuate everyone within l
this 67.5 sector out to
.o limit of the LPZ.
NOTE: The decision to evacuate and which area is to be evacuated are the responsibility of local government agencies.
f.
Conduct appropriate post-accident cleanup and reentry operations.
Close-out the event with a verbal summary to offsite agencies and g.
complete the following written reports:
- 1) Plant Problem Report (see Nuclear Plant Administrat5.ve Procedure C-12).
- 2) Written summary to NRC within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
6.
Subsequent Actions for a General Emergency Activate the Technical Support Center, the Emetgency Operations a.
Facility and the onsite Operational Support Center in acr.ardance with EP's, EF-1, EF-3, and EF-2, respectively.
O
1&2 NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3
DATE 8/11/81 PAGE 11 OF 57
.~,
RELEASE OF AIRBORNE RADIOACTIVE MAIERIALS TITLE b.
Evacuate Site Personnel
- 1) As soon as the accident has been classified as a General Emergency, evacuate all nonessential site personnel in accordance with instructions given in EP G-5.
2)
Evacuate site personnel engaged in recovery actions if it appears that they will exceed the emergency dose criteria given in EP RB-2.
Evacuate Members of the Public from the Downwind LPZ c.
As soon as the accident has been classified as a General Emergency, notify the Sheriff and recommend immediate evacuation of the LPZ in the downwind direction with the rgmainder of the ingestion pathway LPZ being placed on standby alert If it is anticipated that conditions will escalate to a General Emergency, it is not necessary to delay evacuation of the LPZ until confirmed offsite monitoring results are obtained.
If evacuation is required, determine the area which should be evacuated G
first. On a map, draw an a: row pointing in the downwind direction.
Mark a 22.5 sector on either side of this downwind sector.
Evacuate everyone within this 67.5 sector out to the limit of' the LPZ.
d.
Provide periodic meteorological assessments to offsite authorities and, if any releases are occurring, dose projections for actual releases.
- 1) Activation of EARS is the preferred method for transmitting dose projections offsite.
2)
If EARS is not available in either the automatic (EARAUT) or manual (EARMAN) mode, perform appropriate hand calculations using Appendices 2 - 7 of this procedure.
e.
Perform Offsite Monitoring
- 1) General A General Emergency release is of sufficient magnitude such that some offsite protective measures beyong the LPZ, such as evacuation or long-term impoundment of foodstuff, may oe required. Therefore, an offsite monitoring program should e established for the following purposes:
1This can be done by sounding the Early Warning System.
v e-
DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3
DATE 8/11/81 PAGE 12 OF 57 TITLE:
RELEASE OF AIRBORNE RADIOACTIVE MATERIALS a)
Initially, the program should be directed toward identifying those areas located beyond the LPZ where personnel evacuation may be necessary to provent persons from exceeding the recommended evacuation criteria doses of 500 mrem whole body and/or 5 rem thyroid.
b) Once any immediate evacuation is accomplished, the program shall be set up to determine the need for long-term decontamina-tion or impoundment of foodstuffs, which might be desirable even in areas where prompt personnel evacuation was not required.
NOTE: These decisions are the responsibility of local government agencies. However, current government recomendations are summarized in EP RB-10.
c) The program should provide background data for any necessary reports to regulatory agencies.
d) The program should provide the data to answer questions of l
l public concern.
m
(
f.
Take Protective Measures for Members of the Public Table 1 sumarizes recommended protective actions for exposure to a passing plume. The area where action is taken must include I
the entire area in which,the dose criteria are exceeded. A somewhat larger area than this should be considered.
NOTE: Evacuate at least a 67.5 sector (22.5 on both sides of the downwind sector).
Conduct appropriate post-accident cleanup and reentry operations.
g.
h.
Close-out the event with verbal summary to offsite agencies and complete the following written reports:
- 1) Plant Problem Report (see Nuclear Platn Arfministrative Procedure C-12).
- 2) Written summary to NRC within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
APPENDICES 1.
Summary of Criteria for Classifying Emergency Based '6on Dose and Release Data
(
2.
Instructions for Estimating Noble Gas Release Rate Using Plant Vent Monito RE-14 or RE-29
NUMBER EP R-2 DIABLO CANYON POWER PLAN.T UNIT NO(S) 1&2 REVISION 3
DATE 8/11/81 PAGE 13 OF 57 RELEASE OF AIRBORNE RADIOACTIVE MATERIALS TITLE-Instructions for Estimating Iodine Release Rate Using Plant Vent Monitor RE-24 3.
4 Use of Containment Air Sample Data to Estimate Release Rate 5.
Use of RCS Coolant Sample Results During S/G Tube Rupture Accident 6.
Accident Summary Sheets 7.
Summary of Field Monitoring Formulae that are Useful in Classifying Accidents ATTACHMENTS 1.
Form 18-10262, " Emergency Status Form" 2.
Form 18-9221, " Emergency Notification Record" 1
I l
iniBRBEEiEEiEE
. - -..c.
.v y $,
~ :.~,E'.('b
.~
, ~
b 3,
M,. <.S;'s..-J.,. z
~
W q ;<:4,.9,
',! 9 : %.
.. ':.92-5f:!::-:-f:frf::, :5:5.e:!:.?. 6% ',,.
.s ~
],
wt ji 6.
6....,....._smK M x* h y, y y,.. ? :...
c.
. y,.
' . / f f;. j.<....'<. y'. c.: : : :.. ; ~y
.c..
... ?
.?
~
<r
.s eI.M.$'e**es -,* dS-.*** E -L..
e R ~m.s W.y.CiM i[s?, W f;( 'ened ' air M N W :+ 4 ci Q r T.h w k b W -
(., ni,.y? WA.
- '.~ ' :: :-L-a
~
ps p a-or, c..,r,e. c
't r
r /s..r'_,.eY.. -
l t l f
.~
~ '-
.]
,,.. s r <
. f f.:...'
.;..,.g %
~ ' -
' 3 [ _ ; _. - ['
,/
2h,,
,.;.:." ~
~
'I
,,e,r e,,
m,
, p
-(.
.(i f - (-..,, f -
(
e,
- ia( - ' M ( [ - 4 :s gee (. u M ',qr-
,g' g g,,,, is t-.t
, :,(:' -
/y%we.p'y} m,*.x. ~ - i-,. : : > ?
nv '. :n
~v v :
v vpf.y
- a.
r_, ;r: ? ; y,';.. ;.2,. : a;.
., ~. >. :
.,L-
)X r
,,'7,
- ; A';'l-? { 'l.
',. N ! ', - -[,ff.f -', ". :}. _'. f'.: _
,'. } -l :".,-
-i;:.:-.-
r,~,.h.
'd.;:rt ;Je7 : f. :s.
?.
.,.?.
' t.a.
e Il
- l' f c..
1{.
ef* >,' ': r.,(:. ^'.,r ' <r<'
,: ; ' /,. '_l..
^,
- c. r.
M g,(
'1
_?
t
[a b
- m.ar aqst2: q,so mmtwarcrA '
3'M' m
$m$iTfMNG g:.;c.sn:3 3 ~
, :. c,e 4 r' 4 0s-h ~4,E.-t.sc-AAL e +4.r..
gikd 0
'lM/
f q. ;. u.
vt-.. e.1 s.
.,'t %,i,'. ',
.c
~ -'
. g '. t t,'
k h r. < '
l
,I
-._{;. N(
- I k
u.
...I-
.{q he
- t n...
1+.......
.y.----
- .:....g..
..I ' O.,-c.'.f,h.~. ',
.,.1. s 7, ;', N'. ;. -cp,: ; - -y f::. -
- M E M $ % N ; N D,,1;; g "-I;.J
- [..$ M @
t
'~ '
m
- v. n....~. - -..
..,.,.c.n,,=...~.
O i'
.B!!!BBBREBf,EBBBBI
le REDUCE o
Thyr i s
s thr TO A W110LE o( d less tha u05 5D}
CASEOUS BODY
,/
)
Re
(
)
ed %d LUME AllD P
(/
n5 comm
%,)
TilYROID n
tio td N
pla Action (*)
DOSE Offsite ned s
n y
Whole Body a tho ipr te tiv o
w advis u
c h
Thyr id 5
ory to e
r ties av iat a tions (*}
c 0.5 Honi further ine k shel ay is s e m
to 5 o
g to e
nvir str ter sue Co lev ls.
r e an h
to 25 ad Pr mme ts u tio n
n onm c
n.
evio ental s
Se k shelt r diatio prote tivusly r s
e a
c ecomm reco Co d
e e ded nside n
n n ider da tio er Whole body s
c r
as co ns e
nstr ints ev a
m minim or te ay be ac Honito m ke itu tion /u le a
a u.
rmin ted.
5 m
1hyr id 25 lev ls. envir r
a n
ad a
n o
abo ss e
impr ve onm ad affe ted Co tr l e tal n
r diatioa tic l.
If n
c n
c o
abov a
a constr ints ar acces ea.
e prev s
Co du t a
s to n
n et n
c spe ial full s Mo ito e tei. to x
n m
c a dato n
be lev ls nvir ry ev giv c le r
co a
e ental r diaticu tio.
childr en fonsider e
eva i
a) for ad onm a
cu tio a
r ation n
a The m
a tio n theandato adju t n
en eva n
cu tio sho ld se o
ad s
n a
a u
in ide t c
ry e ar pr c
s ea fo on egn n
e Icv ls. a u tion ba n
ns acces v
at of c
are s to n
r Sheltering i e
a
\\
m w
ust recomm om The take ended affe ted en.
Control if sd e
c v lue existing c for are a
evac s
pr o ditio nning omptly au tio alte a
an of a.
At 05 s
pla n
n r
can the tim rem n tiv j
a cco not whole body i s into purpo mplished. be prin iple n
e c
e of se.
g the inciden s
co Pr te tiv of s ba nsiier tio maintaining r dt, off upo o
sed a
c l
a iatioicials guidan n (e.g.,ea tio n
c n
l e ther,de isio c
w a c
expo may imple e fr n
ns i
o sures me t m the
- tate low-impa t plu at me ar iv lthe tim n
as lo r
of pr te tiv Califor ia (
tim )e the a
w of as c
reaso e.
o n
n bly a hiev b a
c see c
e r fer ac e
a le (tio n
enc ALARA),s in ke e 3).
eping with v
the I
lt i
1&2 NUMBER EP R-2 OlABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3
DATE 8/11/81 PAGE 15 OF 57 TITLE; RELEASE OF AIRBORNE RADIOACTIVE MATERIALS APPENDIX 1
SUMMARY
OF CRITERTA FOR CLASSIFYING EMERGENCY BASED UPON DOSE AND RELEASE DATA NOTE 1: For each classification, the actual definition is given from EP G-1.
If the necessary information is available, this is the best criteria In addition, however, a set of Ded.ved Criteria are also to use.
provided. These are calculated criteria, which are slightly less accurate because of the necessity to make calculational assumptions, but which may be more useful depending on what information is readily available.
NOTE 2:
In general, derived criteria are expressed in terms of the site boundary atmosphere dilution factor, (X/Q)800 This can be obtained from the meteorological computer. However, If this information is not readily available, default values of the crite3 a are given using the FSAR 1
design basis (X/Q)800 = 5.3X10 " sec/m.
NOTE 3: The deff.itions of terms used in the quations are:
' NG = noble gas release rate (Ci/sec) k
= iodine release rate (Ci/sec)
I NNG = total curies of noble gas released (C1) 9
= total curies of iodine released (C1) 1 b = iodine concentration (pC1/CC or Ci/m )
(X/4)800 = centerline atmospheric dilution factor @ 800 m (sec/m )
l A.
UNUSUAL EVENT 1.
Definition Radiological effluent technical specification limits exceeded.
The technical specification limits correspond to site boundary (800 m or 0.5 miles dose races of:
a.
Whole body 2.
0.057 mR/hr.
b.
Thyroid A 0.170 mrem /hr.
l t
~ ~ - ~ - - ~
~~~~
~
-~
~.
~ ~
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 & 2 REVISION-3 DATE 8/11/81 PAGE 16 OF 57 l
TITLE:
REIIASE OF AIRBORNE RADIOACTIVE MATERIALS l
I APPENDIX 1 (Continuedl 2.
Derived Criteria a.
Noble Gas Release Rate
-7 4
g 6.3x10 3g (X/Q)800 Default Value: k see NG b.
Iodine Release Rate a
. do I
(Assumed to be I-131)
(X/k)800 Default Value: 6
.2 1.7x10- Ci/sec 7
m Centerline Iodine Concentration @ 800 m c.
-11 I E 9.2x10 (Assumed to be I-131)
B.
ALERT 1.
Definition Radiological effluents grtater than 10 times technical specification limits exceeded.
This corresponds to the following dose rates at the site boundary (800 m or 0.5 miles):
I a.
Whole body e.
0.57 mR/hr.
b.
Thyroid
?-
1.70 mrem /hr.
1
- 2. Derived Criteria a.
Noble Gas Release Rate
-6 4
6.3x10 NG a (X/4)800 Default Value: 4 2
0.012 Ci/sec O
(
3g
DIABLO CANYON POWER PLANT UNIT NO;S) 1&2 NUMBER EP R-2 REVISION 3 DATE 8/11/81
^
PAGE 17 OF 57 TITLE:
RELEASE OF AIRBORNE RAP 70 ACTIVE MATERIALS APPENDIX 1 (Continued)_
b.
Iodine Release Rate
. 2d0 I g (Assumed to be I-131)
(X/6)800
-6 Default Valuc:
dg 1.7x10 C1/sec 7
Centerline Iodine Concentration at 800 m c.
-10 X 3 9.2x10 (Assumed to be I-131) 7 C.
SITE AREA EMERCENCY 1.
Definition Radiological effluents correspond to greater than 50 mR/hr for 1/2 hour or greater than 500 mR/hr for 2 minutes to the whole body (or five times m
E ese levels to the thyroid) at the site boundary (800 m).
This can also be interpreted to mean an accident which produces a total j
dose at the site boundary of ? 17 mR (whole body) or 2 85 mrem (thyroid).
2.
Derived Criteria Peak Noble Gas Release Rate (3 2 minutes duration) a.
-3 QNG g 5.6x10 (X/4)800 Default Value: k
- 2. 10.5 C1/sec NG b.
Average Noble Gas Release Rate (2"30 minutes duration)
-4 63c 2 5.6x10
(
800 Default Value: k sec NG c.
Total Noble Gas Release Q
2 0.68 3g (X/6) 800 Default Value: Qgg.h 1280 Curies
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) 1 & 2 REVISION 3 DATE 8/11/81 PAGE 18 OF 57 RELEASE OF AIRBORNE RADIOACTIVE MATERIALS l
TITLE:
APPENDIX 1 (Continued) d.
Peak Iodine Release Rate (>,.2 minutes duration) k
- 1. 5x10 (Assumed to be I-131) r (X/6)800
-3 Default Value: 6 E 2.5x10 C1/sec 7
Average Iodine Release Race (7 30 minutes duration) e.
k 1*
(Assumed to be I-131) r (X/Q)800 Default Value: 6 >, 2.5x10 ' C1/sec
~
7 f.
Total Iodine Release 1.65x10 '
Qg o
7
(
(X/h)800 Default Value: Q g 0.3 Curies 7
D.
GENERAL EMERGENCY 1.
Definition Radiological effluents correspond to 1 R/hr whole body or 5 rem /hr thyroid at the site boundary.
2.
Derived Criteria a.
Noble Gas Release Rate 0.011 Q3g 3 (X/h)800 Default Value: D 3 21 C1/sec NG b.
Iodine Release Race
-0 2.7x10 (Assumed'to be I-131)
Q7 g (X/4)800 Default Value: k 3 0.005 C1/sec g
w h ee.4 e.,,.,
I DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3 DATE 8/11/81 PAGE 19 OF 57 TITLE:
RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS APPENDLT 2 INSTRUCTIONS FOR ESTIMATING NOBLE CAS RELEASE RATE USING PLANT VENT MONITORS RE-14 OR RE-29_
APPLICABILITY First choice if noble gas release is going out of plant vent.
INSTRUCTIONS 1.
Determine Plant Vent Flow Rate (in efm) on Affected Unit Check FR-12 on Unit 2 RMS board in control room.
If operable, read a.
flow rate directly off of chart.
F vent b.
If FR-12 is inoperable, determine the flow rate using the number of ventilation fans in operation and the following fan capacities:
n cfm FHB exhaust fans @ 35750 cfm/ fan O'
Aux. bldg. exhaust fans @ 73500 cfm/ fan
=
cfm
=
cfm Cont. purge exhaust fans @55000 cfm/ fan
=
cfm 2 purge fan @300 cfm/ fan
=
Cont H
=
cfm Sum F, g
=
y 2.
Read RE-14 (in control room) if it is on scale.
Otherwise read RE-29 in the package boiler room.
Convert the readings to plant vent concentration usir$ Figure 1 (for RE-14) or Figure 2 (for RE-29).
Summarize the data in spa ex prov,ided.
NOTE: on Figure 1, assume effective age 4 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> for all accidents except a fuel handling accident where the fuel has been out of the core for at least a month.
RE-14 RE-24 Time epm pC1/cc Time mR/hr.
uCi/cc O
1
~
DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3 DATE 8/11/81 PAGE 20 OF 57 TITLE:
RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS I
I APPENDIX 2 (Continued) 3.
Calculate Noble Gas Releese Race Regardless of the instrument used, the formula for calculating the noble gas release rate is:
(cfm) x 4.72 x 10
QNG(Ci/sec) = (pC1/cc Vent x F INSTR.
TIME (pCi/cc) x (F
) x (4.72 x 10~4) = Q3g (Ci/sec) g 4.72 x 10 '
~
=
RE-x x
4.72 x 10 '
~
=
RE-x x
~0 RE-x x 4.72 x 10
=
4.72 x 10
=
RE-x x
4.72 x 10
=
RE-x x
~0 RE-x x 4.72 x 10
=
~4 l
I k
RE-x x 4.72 x 10
=
~0 RE-x x 4.72 x 10
=
4.72 x 10 '
~
=
RE-x x
Date By l
O
DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3
DATE 8/11/81 PAGE 21 OF 57 1
l TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS APPENDIX 2 (Continued)
FIGURE 1 RESPONSE OF PLANT VENT RADIOGAS MONITOR (RE-14) i t
10' _
i
../e e
e i e
.....it
,,...sii i
e ii...6 l l 1 l 3 'll' l i I i 11 til l l I i l 110' I i l I l I llI i i I Ylll l i I l i lli I lll!
I I 1111ll lllIlli l I lillli I!AllIl i I lillll l
g l i l 11 llll l ! I i 6 t il i I l lillit i i l l/ fill l i 1 t illil Vi t illil
^
li!
i ii q
10 EFF. AGE ;
, x
..e e i,i. ",
i
/iiii.o e
iei....
f
.i.... y,1000 hr -
v i i i s iltll n,. I I N J i/1ti i t i t ite i
y'i i 116611 r i t s i sii i
3 i
f.......
C I i i li tiil i l i V;w I I i t t li;l / i li tial i i t ill:t I!!!!!
2
/
_ LC ' ' l I l i 1 91111 t i l I litil i l I l l illi i i l liitti
! l i t t ilil I t l ilitt 1
10 '
10 10
10-s 10-"
10'3 10"*
10-3
~7 Plant Vent Concentration (uCf/ce)
O
~~lT.
OtABLO CANYON POWER PLANT UNIT NO(S) 1&2 N"MBER CP R-2 REVISION 3 DATE 8/11/81 PAGE 22 OF 57 TITLE:
RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS l
I APPENDIX 2 (Continued)
FIGURE 2 RESPONSE OF INTERIM PLANT VENT RADIOGAS MONITOR (RE-791 Time After Reactor Shutdcwn i w'"/
'i' i
i t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> jl 47 j
i 103 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> n..
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
_jr-I hour I
t r
i VMA' I
I I
I I!II I ! I III!!III IIM I ! ! IIIbE/ I!
^02 ul
-x m
u
_..,, =..
i N Ni b.1 M////<
ni I
a i
t t
t 84 o
"g-i, t
I i i!
I i
.i i
f t
I 6-l
\\i iT$ \\t'//M 3
ll ll l.
I 11 l
l I l
l iiMJV I ll l
~
1
= 10
- Q d,
I
(
C
.J,..
,m,
' i i
r it i ws i
! i in 6
s E
l l l I
ll 4V II l l l Ill.
I
$ 1
=
E
-a I
4X 8
i wf, u
.i i i
.n h
0 1
IW I.4Vl i
I i1 1 Il Cg 10_1 -
j
-4 W J
C s
a 1
i w/
ii!
i iir 9
i
,i!
S j ig ir g10-2 3.<-f/ I III I
I!I i
II
'I II!
I II!
Ii i
I M i
o
.i i &W on i,i a
wn w
w n
l ll lll1 l ll ll I
I I
_I ll 8/ III I
l 10-3 II. i ~ I.
I
/// T '_ I i
i i w en n it i !
9
.i i.
,i i
,i i i
mo i.
4 I
U I I
10 # '
I U"
O
~
../
.I 6
f.
1 il I t
'n ! i
. ii i n ti i
in in ii i
i
,o':
l I!
II 4 I
Ill Ill 10-5!i!lll!I I IIIII Il I' ll 10-1 1
101 102 103 104 10 106 107 5
EXPOSURE RATE (mR/hr) m
..e
==+s~
=
' see e =nare om*=
- = *.
m
NUMBER EP R-2 OtABLO CANYON POWER Pt. ANT UNIT NO(S) 1 & 2 REVISION 3
DATE 8/11/81 PAGE 23 OF 57 TITLE RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS APPENDIX 3 INSTRUCTIONS IVR ESTIMATING IODINE RELEASE RATE USING PMNT VENT MONITOR RE-24 APPLICABILITY RE-24 first choice for estimating iodine release rate for minor accidents, where RE-24'will go off scale for any release classed as' r lease path is the plant vent.
Site Area Emergency or above, and dose rates may make instrument inaccessible.
Under such circumstances, it is best to estimate the release rate by some other method, although a technique is given for estimating high release rates using this instrument.
INSTRUCTIONS 1.
Determine Ratio of Plant Vent Flow Rate to Sampler Flow Rate a.
Sampler Flow Rate Read at instrument. Otherwise assume the normal setting of 1 cfm.
'O F
=
sw I
efm l b.
Plant Vent Flow Rate
- 1) Check FR-12 on Unit E % to.:cd in control room.
If operable, read flow rate df:u 6p or chart.
F C
I venc l
l 2)
If FR-21 is inoperable, determine the flow rate using the number l
of ventilation fans in operation and the following fan capacities:
cfm FRB exhaust fans @35750 cfm/ fan
=
cfm Aux. b1dg. exhaust fans @73500 cfm/faa
=
_ cfm Cont. purge exhaust fans @55000 cfm/ fan
=
cfm Cont. H2 purge fan @ 300 cfm/ fan
=
Sum F,,g j
e g, j
=
y c.
Calculate Flow Rate Ratio
=
FRR = F F
=
vent samp (O) vv
OtABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION.
3 OATE 8/11/81 PAGE 24 OF 57
.~
TITLE:
RELEASE OF AIRBORNE RADIsACTIVE MATERIALS l
l APPENDIX 3 (Continued) 2.
Obtain Reading On Instrument and Calculate Release Race
~1 Turn the toggle switch on the front of the instrument to the uC1/sec(x10
)
a.
position.
b.
Turn the SCALE FACTOR switch to the "1000" position.
This switch is 1ccated inside the door on the lower front part of the instrument.
Record the scale factor in the blank in paragraph 2.d. below.
To allow for instrument respor ce time wait at least one (1) minute c.
and then read the chart. Enter this readint; in the blank in paragraph 2.d. below. The chart reading is a number between 1 and 1000.
If the_
instrument does not read on scale, I-131 is not a significant contri-bution to the accident.
f d.
Calculate the release rate ing the formula Q7 (C1/sec)=(Chart Reading)x (Scale Factor)x (FRR)x 10 l
l (Chart ) (Scale )
TIME (Reading)x(Factor) x (FRR) x (1047)
Q7 (Ci/sec)
=
c
-17 10
(
~
-17 10
~1 10
~
10
-17 10
-17 10
~17 10
-1 10 3.
Calculating Re. lease Race 7.f Cartridge Is Analyzed In the Lab If Sometimes it is desirable to take the cartridge to the counting room.
so, have the technician report the total pCi of I or I-131 contained on the cartridge.
a) Activity on Cartridge (Acart) =
pCi (circle I or I-131) b) Estimate the time over which the release has persisted (in seconds).
( EC)
Ot
=
RELEASE O
1&2 NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 DATE 8/11/81 m
PAGE 25 OF 57 TITLE:
RELEASE OF AIRBORNE RADIOACTIVE MATERIALS (A!
v APPENDIX 3 (Continued) c) Calculate the average release rate using the equation:
-6 6 (C1/sec) = hcart (EC1)] x (FRR) x 10 I
h RELEASE (Sec)
-6
=(
)x(
) x 10 -
C1/sec
(
)
l 4.
Calculating Release Rate If RE-24 is Inaccessible N0g: This method is very approximate and is an interim technique only.
Take a Ra.iowl or other y dose rate measuring instrument and approach a.
RE-24 as close as possible, being careful not to exceed personnel exposure limits.
b.
Get as close to RE-24 as you can and take a Radowl reading (in R/hr.)
C and also estimate the distance (in meters) you are from RE-24.
I
\\
U Dose Rate (DR)
R/hr.
=
Distance to RE-24 (d)
=
m Estimate the time over which the release has persisted (in seconds).
c.
g Q g = sec.
d.
Calculate the release rate from the equation.
k (C1/sec) = 60 x (DR) x (d) x (FRR)_
(0 RELEASE)
= (60) x (
)x(
)2 x(
)
(
)
l Ci/see __l S.
Calculating Release 3 ace If RE-24 is Accessible, But Dose Rates Are Too High To Permit Cartridge To ifa Collected Proceed as in p'aragraph 4 above, with the follouing exceptions:
a.
- 1) Open Cartridge holder door and take dose reading on exposed r-cartridge. Again, estimate distance in meters.
h()
DR =
R/hr d=
m
,,#wm
- g
- * +
=+i=-
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 I
REVISION 3 DATE 8/11/81 l(-
PAGE 26 OF 57 TITLE ILrLEASE OF AIRBORNE RADI0 ACTIVE MATERIALS I
l APPENDIX 3 (Continued) b.
Calculate the release rate from the equation:
~
Q (C1/sec) = 1.3 x (DR) x (d) x (FRR)_
7 (A E E)
- 1.3 x (
)x(
)2xg
)
(
)
l Ci/sec_
NOTE: The reason the equations are different is because there is less shielding when the cartridge is expoaed.
MN
-(
l I
N
___._____.____T_r______
9 DIABLO CANYON POWER PLAN 1 UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3 DATE 8/11/81 PAGE 27 OF 57
'j
(/
TITLE: RELEASE OF AIRBORNE RADIOACTIVE MATERIALS APPENDIX 4 USE OF CONTAINMENT AIR SAMPLE DATA TO ESTIMATE RELE*dE RATE APPLICABILITY Many postulated accidents first result in a release to containment.
From there the activity may go to the environment via the containment purge (if it is not isolated), or via some unspecified leak path.
If a containment air sample is obtained and the leakage flow rate is known, or can be estimated, the release
/
rate is easily determined.
INSTRUCTIONS _
l.
Obtain air sample and analyze for noble gas and/or iodine. The results will be given as concentration, C(in pC1/cc), in the containment atmosphere.
TIME AT C
C WHICH SAMPLE NOBLE CAS IODINE WAS TAKEN (pC1/cc)
(pC1/cc)
NJ l
2.
Estimate flow rate from containment, F
)*
cont NOTE:
If there is no obvious leak path, assume containment leaks at design value of 0.1%/ day, whi:h translates to F
= 1.S cfm.
F cont cfm l
3.
Calculate Release Rate The expression is as follows:
Q (Ci/sec) = C (pCi/cc) x F (cfm) x (4.72 x 10~ )
J e
+
l DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3 DATE 8/11/81 PAGE 28 OF 57 TITLE:
RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS APPENDIX 4 (Continued) x (4.72 x 10 ')=
9 IODINE (C1/sec)
(FCONT)
TIME ( IODINE) x
~0 4.72 x 10
-0 4.77 x 10
-0 4.72 x 10
-4 4.72 x 10 4.72 x 10 '
~
TIME ( NOB GAS)_ x
( CONT)_ x (4.72 x 10- )_
9 NOB GAS (C1/sec)_
4.72 x 10 '
~
4.72 x 10 '
4.72 x 10 '
-4 4.72 x 10 p
(,
4.72 x 10' O
OtABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3
OATE 8/11/81
.s PAGE 29 OF 57 b;
TITUh RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS V
APPENDIX 5 USE OF RCS C00LAVI SAMPLE RESULTS DURING_
S/G TUBE RUPTURE ACCIDENT APPLICABILITY The most difficult accident to estimate the release rate for is a S/G tube rupture becAuse of uncertainties in primary to secondary leak rate and in steam leak rate co atmosphere. However, if the activity level in the RCS is known, it is possible to make some assumptions about leak rates and maka some very rough approximations of the release rate.
INSTRUCTIONS 1.
Determine Primary System Activity Measurement will be activity concentration, C, in pC1/cc.
RCS Concentrations (pCi/ce)
Estimate Flow Rate To Atmosphere The best estinte of the release rate that can be made is that the flow rate of reactor coolant to the atmosphere is equal to the primary to secondary tube rupture flow during the period when steam is being dumped.
Estimate the primary to secondary leakage using a mass balance, or guess at it based upon the assumption that the complete severance of one tube produces a primary to secondary leakage of 600 gpm.
Estimate The Release Rate The appropriate equation is:
-5 Q (C1/sec) = C(pCi/cc) x F (gpm) x PF x 6.3 x 10 p
Where:
PF = iodine partition facter, to account for retention of
-m d
)
iodine in water. Use PF = 1 for noble gases, PF = 0.1 for iodine 11 S/G is empty, and PF = 0.01 for iodine is S.C is partly full of water.
- ~- -
~
1&2 NUMBER EP R-2 DIA*LO CANYON POWER Pt. ANT UNIT NO(S)
REVISION 3 DATE 8/11/81 f
PAGE 30 OF 57 TITLE:
RELEASE OF AIRBORNE RADIOACTIVE MATERIALS
{
g APPENDIX 5 (Continued)
-5 TIME IODINE x PRI, SEC x PF x 6.3 x 10
= 0 IODINE (C1/sec)
TIME (BOB GAS) x ( PRI,SEC) x g) (6.3 x 10-5) = 6 NOB CAS (Ci/sec) x_1.0 x
x x 1.0 x
x 1.0 x
__ x 1.0 x
x 1.0
(
e
}
L e
\\
NUMBER EP R-2
{
DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 DATE 8/11/81 PAGE 31 OF 57 j
TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS APPENDIX 6 ACCIDENT SU.St\\RY SHEETS This attachment contains summary sheets for the various postY11ated accidents l
which have been analy:ed in the FSAR. These sheets contain both the " design l
basis" and " expected" case variables which were assumed in.:he FSAR analyses.
The sheets can be used to compare actual measurements w1:_h assumed numbers from the FSAR, in order to help evaluate how things are going in relation to predictions, or they can be used as a source of data to supply unavailable numbers.!n F 'culations which are performed at the time of the accident.
Two-sets of data are included. The " design basis" case is expected to be highly conservative, where every variable is at a worst-case condition. The
" expected" case is the best estimated prediction of what might actually occur.
When FSAR values are used to make calculations or predictions at the time of the accident, the " design basis" values can be used to provide a quick upper limit result, but as soon as data becomes available which tends to confirm one case or the other, the one which best agrees with the data should be used.
The accident classifications identified in this attachment are based on the activity releases. Other emergency procedures may have different classifications which are based on the initiating event.
The summary sheets provided are:
A.
10A MAJOR LOCA I
B.
10B MAJOR STEAM LINE BREAK C.
10C MAJOR FEEDWATER LINE BREAK D.
10D BLACKOUT (OR PLANT C00LDOWN WITH ATMOSPHERIC DUMP)
E.
10E SMALL LOCA F.
10F TUBE RUPTtJE G.
10G LOCKED ROROT H.
10H FUEL HANDLIM ACCIDENT IN FUEL HANDLING BUILDING I.
10I FUEL HANDLING ACCIDENT IN CONTAINMENT J.
10J ROD EJECTION ACCIDENT K.
10K GAS DECAY TANK RU?TURE L.
10L LIQUID HOLDUP TANK RUPTURE M.
10M VCT RUDTURE O
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S),
REVISION 3 DATE 8/11/81 PAGE OF 32 57 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
{
l
SUMMARY
SHEEI 1A MAJOR LOCA FSAR FSAR PARAMETER DBA EXPECTED ACTUAL l
1.
Total Release to Containment i
Free Volume, C1 a.
Ie-133 2.03x108 1.36x106 b.
Other Noble Gases 5.73x108 4.27x105 7
1.82x105 c.
I-131 2.21x10 d.
Other Iodine 1.90x10e 2.73x105 e.
Effective Age of 0
20 Mixture (hr)
I I
2.
Containment Spray Effeetiveness a.
Removal half-life (hrs) 0.022 0.0075 b.
Number of operable 1
2 spray pumps 3.
Containment Leak Rate 0.1 for 1st day 0.05 for ist day
(%/ day) 0.05 after 1st 0.025 after 1st day day 4.
Total Release to Environs, First 2 Hours, C1 a.
Ia-133 16,840 56 b.
Other Noble cases 25,930 21 c.
I-131 191 0.05 d.
Other Iodine 1,325 0.08 l
e.
Effective Age of Mixture 1
40
(
}
f.
Release Mechanism Containment Containment Leakage Leakage
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 DATE 8/11/81 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS SUNMARY SHEET 1A (continued)
FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 5.
(x/Q)CLksec/m) 3 l
~
a.
800m (site boundary) 5.29x10
5.29x105 b.
10000m (6 mi. LPZ) 2.20x105 2.20x106 6.
Whole Body Dose Results a.
Total 800m dose for 5,600 0.365 lst two hours (mR) b.
Total 10000m dose for 567 0.06 30 days (mR) 7.
Thyroid Dose Results a.
Total 800m dose for 95,900 1.25 1st two hours (mR) 8.
Accident Classi'ication Ceneral Alert Emergency 9.
Miscellaneous a.
Containment-free 7.36x1010 j.
volume (ce) b.
RCS Coolant Mass (gm) 2.4 x108
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 DATE 8/11/81 (h
TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS (This page intentionally left blank.)
i i
\\
U BER R-2 OIABLO CANYON POWER PLANT UNIT NO(S)
DATE 8/11/81 1
PAGE OF 35 57 TITLE:
RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS y
SLHMARY SHEET 1B MA. TOR STEAM LINE BREAK l
l l
FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 1.
Initial Conditions and Assumptions a.
Primary Coolant Activity (pCi/gm)
- 1) 2e-133 270 67.2 2)
I-131 2.6 0.65
- 3) Other Iodine 7.9 2.0 b.
Secondary Water Activity (pC1/gm) 1)
I-131 0.015 0.44x10
2)
Other Iodines 0.037 0.90x10
c.
Assumed Fuel Defects 1
0.2
(%)
d.
Primary to Secondary 1
0.014 Leakage (gpm) e.
Steam Release, 1st Two Hours (1bs) 1)
Failed generator 97,000 2)
Other generator (atmospheric dump) 520,000 f.
Total Steam Release During 8-Hour Cooldown (1bs) 1,600,000 g.
Liquid Release Fraction for Iodine 1)" Failed generator 0.1
- 2) Other generators 0.01 O
NUMBER E.P R-2 OlABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 DATE 8/11/81 I
TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET 1B (Continued)
FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 2.
Activity Release to l
Environs. First 2 Hours (C1) l a.
Xe-133 56.8 0.172 b.
Other Noble Gases 5.2 0.016 c.
I-131 0.157 0.00045 d.
Other Iodines 0.047 0.0013 e.
Effective Age of 65 65 Mixture (hrs) l I
3.
(X/4)CL(sec/m) 3 a.
800m (site boundary) 5.29x10 "
5.29x105
~
b.
10000m (6 mi. LPZ) 2.20x105 2.20x106 4
1.' hole Body Dose Results a.
Total 800m dose for 1st two hours (mR) 1.8 0.0006 l
b.
Total 10000m dose for 30 days (mR) 0.03 0.0010 5.
Thyroid Dose Results a.
Total 800m dose for 1st two hours (mR) 65 0.012 b.
Total 10000m dose for 30 days (mR) 66 0.012 6.
Accident Classification Alert Alert i
h 1
)
N BER M
DIABLO C ANYON POWER PLANT UNIT NO(S)
DATE 8/11/81 PAGE 37 OF 57 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS j
SUMMARY
SHEET IB (Continued)
FSAR FSAR PARAFTER DBA EXPECTED ACTUAL 7.
Miscellaneous a.
Fluid Mass /Sta Gen (lbs)
- 1) Vater 95,100
- 2) Steam 6,620 b.
Safety Valve and Steam Dump Valve Capacities (1b/hr/ valve) 1)
S.G. safety. valve 800,000 2) 10% atmospheric dump 380,000
- 3) 35% atmospheric dump 597,000 0
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION
-3 DATE 8/11/81 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
{
g
SUMMARY
SHEET IC MAJOR FEEDWATER LINE BREAK
~
The release from this accidant comes from release of steam by safety valves an'd/or atmospheric steam dump of steam generator veter during cooldown if the condenser is not available. The steam generator water is contaminated if there is tube leaka'ge. The feedvater itself which is released has very little activity in it and is ignored. This accident is basically the same as a steam-line break and summary sheet 9B can be used.
Note, however, that the steam release vill be through relief valves and so the iodine liquid release fraction should be 0.01 for the entire release.
This will reduce the thyroid dose somewhat from the steam-line break case.
SUMMARY
SHEET 1D BLACKOITT (PLANT COOLDOWN WITH ATMOSPHERIC DLHP)
The release from this accident comes from release of steam by safety valves and/or atmospheric steam dump of steam generator water is contaminated if there
(
)
is tube leakage. This accident is basically the same as a steam-line break and summary sheet 9B can be used. Note, however, that the steam release vill be through relief valves and so the iodine liquid release fraction should be 0.01 for the entire release. This will reduce the thyroid dose somewhat from the steam-lino break case.
l l
NUMBER EP R-2 OtABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 DATE 8/11/81 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET 1E SMALL LOCA (RELEASE OF COOLANT TO CONTAINMENT),
FSAR FSAR PARAMLTER DBA EXPECTED ACTUAL 1.
Initial Coolant Activity (uci/gm) a.
Ie-133 270 45.7 b.
Other Noble Gases 30 5.6 c.
1-131 2.62 0.45 d.
Other Iodine 7.88 1.35 e.
Effective Age of Mixture (hr) 60 60 f.
Fuel Defects (%)
1 0.2 2.
Initial Release to Containment (C1) a.
Ia-133 65,430 16,280 b.
Other Noble Gases 7,95 0 1,980 16 c.
I-131 63 d.
Other Iodine 193 48 e.
Assumption 100% of coolant 100% of coolant N.G. activity N.G. activity
+10% of coolant
+10% of coolant iodines iodines 3.
Containment Spray Effacriveness a.
Removal Half-life (hrs) 0.022 0.0075 b.
Number of operable spray pumps 1
2 c.
Containment Leak Rate 0.1 for 1st day 0.05 for 1st day
(%/ day) 0.05 after 1st 0.025 after 1st day day
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 l
DATE 8/11/81 i
TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS I
I i
SUMMARY
SHEET 1E (Continted)
FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 4.
Containment Leak Rate (2/ day) 0.1 0.05 3
5.
(x/Q) CL (sec/m )
a.
800m (site boundary) 5.29x10 '
5.29x105
~
b.
10000m (6 mi. LPZ) 2.20x105 2.20x106 6.
Whole Body Dose Results i
a.
Total 800m dose for 1st two hours (mR) 0.18 0.004 q
b.
Total 10000m dose for 30 days (mR) 0.05 0.001 7.
Thyroid Doce Results a.
Total 800m dose for 1st two hours (mR) 0.2 0.0009 b.
Total 10000m dose for 30 days (mR) 0.03 0.0001 8.
Accident Classification Alert Alert 9.
Miscellaneous a.
Containment-Free Volume (ce) 7.36x1010 b.
RCS Coolant Mass (gm) 2.4 x101 c.
Liquid Release Fraction for Iodine 0.1 l
l
1
^
\\
l NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 DATE 8/11/81 PAGE OF 47 57 l
TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS SIDefARY SHEET IF TUBE RUPTURE FSAR FSAR e
PARAMETER DBA EXPECTED ACTUAL 1.
Initial Cc.tditions and Assumptions a.
Primary Coolant Activity (uci/gm)
- 1) Ze-133 270 67.2 2)
I-131 2.6 0.65
- 3) Other Iodine 7.9 2.0 b.
Secondary Water Activity (uci/gm) 1)
I-131 0.015 0.44x10 "
4 2-)
Other Iodines 0.037 0.90x10 c.
Assumed Fuel Defects (%)
1 0.2 d.
Primary to Secondary Leakage (gpm) 1 0.014 e.
Steam Release, 1st Two Hours (lbs) 1)
Failed generator 31,000 2)
Other generators (atmospheric dump) 380,000,
f.
Total Steam Release During 8-Hour Cooldown (lbs) 1,600,000 g.
Liquid Release Fraction for Iodine 1)
Failed generator 0.01 l
2)
Other generators 0.01 2.
Total Release to Envirols, First 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (C1) a.
Xe-133 10,980 2,383 b.
Other Noble Cases 1,067 234 c.
I-131 0.75 0.14
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION I DATE 8/11/81 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS i
i
SUMMARY
SHEET IF (Continued)
)
FSAR FSAR PARAMETER DBA EXPECTED ACTUAL d.
Other Iodines 3.1 0.62 1
e.
Effective Age of Mixture (hrs) 65 65 l
3.
(X/6) CL (sec/m )
3 j
a.
800m (site boundary) 5.29x10
5.29x105
~
b.
10000m (6 mi. LPZ) 2.20x105 2,2cxto 6 j
1 4.
Whole P.3dy Dose Results a.
Total 800m dose for 1st two hours (mR) 360 7.7 b.
Total 10000m dose l
for 30 days (mR) 15 0.3 5.
Thyroid Dose Results i
a.
Total 800m dose for 1st two hours (rR) 340 4.3 b.
Total 10000m dose for 30 days (mR) 15 0.2 6.
Accident Classification Alert Alert 7.
Miscellaneous a.
Fluid Mass / Stem Gen.
(1bs) 1)
Water 95,100 2)
Steam 6,620 b.
Safety Valve and Steam Dump Valve Capacities (1bs/hr/ valve) 1)
S.G. safety valve 800,000 2) 10% atmospheric 380,000 l
l dump 3) 35% atmospheric dump 597,000
I, NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 D/.TE 8/11/81 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET IG LOCKED ROTOR ACCIDENT e
FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 1.
Total Release to Environs, 1st Two Hours (C1) a.
Is-133 97 0.73 b.
Other Noble Gases 19.6 0.21 c.
I-131 0.24 0.003 d.
Other Iodines 0.36 0.003 e.
Effective Age of Mixtura 50 50 f.
Assumptions 1)
Coolant Activity 1% fuel defects 0.2% fuel defects
+3% of gap
+3% of gap activity activity 2)
Primary to Secondary Leakage (gpm) 1 O.014 3)
Secondary Steam Release, 1st Two Hours (lbs) 617,000 617,000 4)
Total Steam Release During 8 Hour Cooldown (1bs) 1,600,000 1,600,000 2.
(X/6)CL(sec/m) 3 a.
800m (site boundary) 5.29x10 "
5.29x103
~
b.
10000m (6 mi. LPZ) 2.20x105 2.20x106 l
v
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION
'3 DATE 8/11/81 OF PAGE 44 57 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
(
I
SUMMARY
SHEET IG (Continued)
FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 3.
Whole Body Dose Results a.
Total 800m dose for 1st two hours (mR) 4.4 0.004 b.
Total 10000m dose for 30 days (mR) 0.5 0.0004 4.
Thyroid Dose Results a.
Total 800m dose for 1st two houts (sR) 82 0.06 b.
Total 10000m doce
{
}
for 30 days (mR) 27 0.02 i
5.
Accident Classification Alert Alert 6.
Miscellaneous a.
Fluid Mass /Stm Gen.
(lbs)
- 1) Water 95,100 2)
Steam 6,620 b.
Safety Valve and Steam Dump Valve Capacity (lbs/hr/ valve) 1)
S.G. safety valve 800,000 2) 10% atmospheric dump 380,000 3) 35% atmospheric dump 597,000 c.
Liquid Release Fraction for Iodines 0.01 l
l
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3
DATE 8/11/81 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET 1H FUEL HANDLING ACCIDENT IN FUEL HANDLING BLDG FSAR FSAR
{
PARAMETER DBA EXPECTED ACTUAL 1.
Initial Conditions a.
Radial Peaking Factor of Damaged Assembly 1.65 1.26 b.
Elapsed Time Since Ranctor Shutdown (hrs) 100 100 c.
Type of Release to Pool 100% of assembly 100% of assembly gap activity gap activity d.
Bundle Submergence (ft) 26 26 e.
Pool Decontamination Factor for Iodine 100 760 f.
Total Assembly Gap Activity at Time of Accident 1)
'100,000 8,137
- 2) Other Noble Cases 4,500 1,500 3)
I-131 52,670 5,282 4)
Other Iodines 7,000 220 5)
Effective Age of Mixture (hr) 600 600 2.
(x/6)CL(sec/m) 3 a.
800m (site boundary) 5.29x10 ' 5.29x105
~
b.
10000m (6 mi. LPZ) 2.20x105 2.20x106 O
NUMBER
. EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3
DATE 8/11/81 PAGE 46 OF 57 RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
(
l TITLE:
SUMMARY
SHEET 1H (Continued FUEL HANDLING ACCIDENT IN FUEL HANDLING BLDG FSAR FSAR
'P'ARAMETER DBA EXPECTED ACTUAL 3.
Total Release to Environs, ist Two Hours (C1) a.
Xe-133 100,400 523 b.
Other Noble Cases 4,100 101 c.
I-131 80 0.005 d.
Other Iodines 10 0.0002 l
e.
Effective Age of Mixture (hrs) 600 600 l
I 4.
Whole Body Dose Results a.
Total 800m dose for 1st two hours (mR) 2.450 1.5 b.
Total 10000m dose for 30 days (mR) 102 0.06 5.
Thyroid Dose Results I
a.
Total 800m dose for 1st two hours (mR) 22,200 0.08 b.
Total 10000m dose for 30 days (mR) 923 0.003 6.
Accident Classification Site Faergency Alert 7.
Miscellaneous a.
Fuel Handling Building 3
Volume (ft )
435,000 b.
Fuel Handling Building Exhaust Rate (cfm) 35,700 35,700
{
l c.
Filter Cleanup Factor 0.10 0.01
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3
DATE 8/11/31 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET II FUEL HANDLING ACCIDENT IN CONTAINMENT FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 1.
Initial Conditions a.
Radial Peaking Factor of Damaged Assembly 1.65 1.26 b.
Elapsed Time Since Reactor Shutdown (hrs) 100 100 c.
Type of Release to 100% of assembly 100% of assembly Pool gap activity gap activity d.
Bundle Submergence (ft) 26 26
~
e.
Pool Decontamination Factor for Iodine 100 760 f.
Total Assembly Gap Activity at Time of Accident (C1) 1)
Ie133 100,000 8,137
- 2) Other Noble Gases 4,500 1,500 3)
I-131 52,670 5,282
- 4) Other Iodines 7,000 220 j
5)
Effective Age of Mixture (hrs) 600 600 2.
(x/6)CL(see/m) 3 a.
800m (site boundary) 5.29x10' 5.29x105 b.
10000m (6 mi LPZ) 2.20x105 2.20x106 Oi
NUMBER EP,R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3 DATE 8/11/81
(
l TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET II (Continued)
FUEL HANDLING ACCIDENT IN CONTAINMENT FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 3.
Total Release to Environs, 1st Two Hours-(C1) a.
Ie-133 12,460 38 b.
Other Noble cases 557 7
c.
I-131 65 0.033 d.
Other Iodines d.7 0.0013 e.
Effective Age of Mixture (hrs) 600 600 I
I 4.
Whole Body Dose Results a.
Total 800m dose for 1st two hours (mR) 0.31 0.0001 b.
Total 10000m dose for 30 days (mR) 0.013 4x106 5.
Thyroid Dose Results a.
Total 800 m dose for 1st two hours (mR) 18.4 6x10' b.
Total 10000m dose for 30 days (mR) 0.76 3x10~5 6.
Accident Classification Site Emergency Alert 7.
Miscellaneous Activity Release Mechanism Activity released from cavity to containment atmosphere is confined directly above the cavity water level.
It is picked up by the fan coolers and sent out through the i
l containment purge.
{
l
i NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3
DATE 8/11/81
)
PAGE OF 49 57 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS SLMfART SHEET IJ l
ROD EJECTION ACCIDENT FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 1.
Total Release to Containment Free Volume (C1) a.
Ze-133 2.01x105 1.52x105 4
4 b.
Other Noble Gases 6.82x10 6.22x10 c.
I-131 7.32x103 7.28x103 4
4 d.
Other Iodine 1.11x10 1.09x10 e.
Effective Age of Mixture (hrs) 40 40 f.
Release Assumption Coolant activity Coolant activity (1% defects)
(0.2% defects) plus 10% of core plus 10% of core gap activity gap activity times a liquid times a liquid releasa fraction release fraction of either 0.1 of either 0.1 (for I) or 1.0 (for I) or 1.0 (for N.G.)
(for N.G.)
2.
Containment Spray Effeetiveness a.
Removal half-l'fe 1
(hrs) 0.022 0.0075 b.
Number of operable spray pumps 1
2 3.
Containment Lask Rate
( / day) 0.1 C J5 4.
(X/6)CL(sec/m) 3 a.
800m (site boundary) 5.29x10
5.29x105
~
~6 b.
10000m (6 mi LPZ) 2.20x105 2.20:;10 l
o
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S)
REVISION 3
DATE 8/11/81 OF 37 PAGE 50 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS l
l
SUMMARY
SHEET IJ (Continued)
ROD F_IECTION ACCIDENT FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 5.
Total Release to Environs, 1st 2 Hours (C1) a.
Ie-133 11.2 5.6 b.
Other Noble Cases 4.1 2.0 c.
1-131 0.0098 0.002 d.
Other Iodine 0.015 0.002 e.
Effective Age of Mixture (hrs) 40 40 l
I f.
Release Mechanism Containment Containment Imakage Leakage 6.
Whole Body Dose Results f.
a.
Total 800m dose for 1st two hours (mR) 0.73 0.04 b.
Total 1000m dose for 30 Days (mR) 0.13 0.006 7.
Ihyroid Dose Results a.
Total 800m dose for
' ilst two hours (mR) 3.3 0.04 b.
Total 10000m dose for 30 days (mR) 0.14 0.002 8.
Accident Classification Alert Alert 9.
Miscellaneous a.
Containment free volume (cc) 7.36x1010 b.
RCS Coolant Mass (gm) 2.4x108
NUMBER EP R-2 O!ABLO CANYON POWER PLANT UNIT NO(S)
DATE 8/11/81 i
l PAGE 51 OF 57 TITLE:
RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS SU9fARY SHEET IK
_CAS DECAY TANK RUPTLTE FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 1.
Total Release to Environs, 1st Two Hours (Ci) a.
Xe-133 65,400 16,300 b.
Other Noble Cases 7,300 2,140 2.
(X/6)CL(sec/m) 3
~4 c.
800m (site boundary) 5.29x10 5.29x10~3 b.
10000m (6 mi LPZ) 2.20x105 2.20:106 3.
Whole Body Dose Results a.
Total 800m dose for 1st two hours (mR) 2,010 44 b.
Total 10000m dose for 30 days (mR) 84 2
4.
Accident Classification Site Emergency Alert 5.
Miscellaneous a.
Tank Volume (cc) 2.18x107 b.
Tank Press 100 psi 8
c.
Volume Released (cc) 1.48x10 ee O
0 DIABLO CANYON POWER PLANT UNIT NO(S)
S N DATE 8/11/81 PAGE 52 OF 57 I
I TITLE:
RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS SL'MfARY SHEET IL LIQUID HOLDaF TANK RUPTURE FSAR FSAR EARAMETER DBA EXPECTED ACTUAL 1.
Activity in Holdup Tank (C1) e,. Ie-133 51,000 10,200 b.
Other Noble Cases 4.710 930 c.
I-131 492 99.3 d.
Other Iodines 1,086 217 e.
Effective Age 7f Mixture (hrs) 60' 60 2.
Cleanup Parameters a.
Liquid Release Traction for Iodines from Tank to Auxiliary Building
~
~
Atmosphere 10
10
b.
Charcoal Filter Cleanup Factor 0.1 0.01 c.
Release Duratica (hrs) 2 2
3.
Activity Release to l
Environs, 1st Two Hours (C1) a.
Ia-133 51,000 10,200 b.
Other Noble Cases 4,710 930 c.
1-131 0.00492 0.0098 d.
Other Iodines 0.01086 0.00217 4.
(X/6)CL(sec/m) 3 l
l a.
800m (site boundary)
- 5. 29x10
5.29x105 1
b.
10000m (6 mi LPZ) 2.20x105 2.20x106
NUMBER EP R-2 OlABLO CANYON POWER PLKIT UNIT NO(S)
DATE 8/11/81 PAGE 53 OF 57 TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET IL (Continued)
~
LIQUID HOLDUP TANK RUPTURE FSAR FSAR i
PARAMETER DBA EXPECTED ACWAL 5.
Whole Body Dose Results a.
Total 800m dose for 1st two hours (mR) 1,440 37 1
i b.
Total 10000m dose for 30 days (mR) 60 1.6 6.
Thyroid Dose Results a.
Total 800m dore for O
1st two hours (mR) 1.93 0.003 b,
Total 10000m dose for 30 days (mR) 0.08 0.0001 7.
Accident Classification Site Emergency Alert 8.
Miscellaneous a.
Tank Volume (cc) 3.03x10e O
NUMBER EP R-2 DIABLO CANYON POWER PLANT UNIT NOfS)
REVISION 3
DATE 8/11/81 PAGE 54 OF 57 l
l TITLE: RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS
SUMMARY
SHEET 1M VOLI:ME CONTROL TANK RUPTURE
~
FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 1.
Activity in VCT (C1) a.
Xa-133 3,330 828 I
b.
Other Noble Cases 198 42 c.
I-131 12.1 3.0 d.
Other Iodines 35 8.7 e.
Effective Age of Mixtur6 (hrs) 60 60 l
l 2.
Cleanup 2arameters a.
Liquid Release Fraction for Iodines from Tank to Auxiliary Building
~
~
Atmosphere 10 "
10 "
b.
Charcoal Filter Cleanup Factor 0.1 0.01 c.
Release Duration (hrs) 2
2 3.
Activity Release to Environs, 1st Two Hours (C1) 1 a.
Xa-133 3,330 828 b.
Other Noble Cases 198 42 c.
I-131 0.00012 0.000003 d.
Other Iodines 0.00035 0.00009 4.
(x/h)CL (sec/m )
3 a.
800m (site boundary) 5.29x10 "
5.29x105
~
b.
10000m (6 mi LPZ) 2.20x105 2.20x106 l
NUMBER EP R-2 DIABLO CAN, YON POWER PLANT UNIT NO(S)
RF. VISION 3 DATE 8/11/81 PAGE 55 OF 57 TIT m RELEASE OF AIRBORNE RADI0 ACTIVE MATERIALS SUMMART SHEET IM (Continued)
VOLUME CONTROL TANK RUPTURE l
)
FSAR FSAR PARAMETER DBA EXPECTED ACTUAL 5.
Whole Body Dose Results a.
Total 800m dose for 1st two hours (mR) 465 9.3 b.
Total 10000m dose for 30 days (mR) 19 0.4 6.
Thyroid Dose Results a.
Total 800m dose for 1st two hours (mR) 0.03 0.00004 b.
Total 10000m dose for 30 days (mR) 0.001 0.000001 7.
Accident Classification Site Emergency Alert 8.
Miscellaneous a.
Tank Volume (cc) 1.1x107 l
O
NUMBER, EP R-2 DIABLO CANYON POWER PLANT UNIT NO(S) 1&2 REVISION 3
DATE 8/11/81 PAGE 56 OF 57 TITLE:
RELEASE OF AIRBORNE RADIOACTIVE MATERIALS l
)
APPENDLT 7
SUMMARY
OF FIELD MONITORING FORML7.AE THAT_
ARE USEFUL IN CLASSIFYING ACCIDENTS Relationship Between Whole Body Dose Rate and Noble Gas Release Rate 1.
it can If a whole body dose rate measurement is taken in the environment, be related to the release rate using the equation:
5 9 x 10 xg y,4 gg x (gf4)L DR
=
WB,L Where: DR
= Whole body dose rate at location L WB'L (mR/hr.)
l fy
- average gamma energy (mev)
(default value - 0.1 mev) k
= noble gas release rat.e (C1/sec) 3g (X/6)
= dilution factor at downwind
{
location L This equation cau also be used to calculate downwind dose rate if the NOTE:
I release rate is know.
2.
Relationship Between Thyroid Dose Race and Iodine Concentration Assuming all iodine is I-131:
DR
= 1.85 x 10
{g131] L 6
Where:
D
= Thyrcid dose rate at location L (Rem / hr).
{I
= I-131 Cgncentration at location L (pCi/cc o r C1,t m )
3.
Relationship Between Thyroid Dose Rate and Iodine Release Rate Assuming all iodine is I-131:
6 (1.85 x 10 ) (4) (X/d)L Dg 7
Where:
DR
= Thyroid dose rate at location L g
(Rem /hr).
Q
= iodine release race (Ci/sec) 7 (X/h) = dilution factor at location L (sec/m3)
OfABLO CANYON POWER PLANT UNIT NO(S) 1&2 NUMBER EP R-2 REVISION 3 DATE 8/11/81 PAGE 57 OF 57 TITLE:
RELEASE OF AIRBORNE RADIOACTIVE MATERIALS APPENDIX 7 (Continued)_
4.
Extrapolation of Dose Rates, Doses or Concentrations to Other Locations If a dose or dose rate value is available at one location in the environment, it may be extrpolated to another location if the respective (X/4) values are know.
(DR) A.
A B
(X/4)3 or
= (X/4)A (D)B (X/d)B A
(X/h) A b Of x
Q'Ss (X/h)3 Where:
DR = dous rate QR /hr, mR/hr, R/hr)
D = dose $R, mR R)
X = concentraticn (pC1/cc or C1/m )
A,B
= locations A and B a
Status #
- 18 1.h62 0/81 (100) t e
Sheet 1 or_ *_
Pacific Gas and Electric Company Department of Nuclear Plant Operations Diablo Canyon Power Plant Unit.Nos. I and 2 4
m Part A: Radiolacical Emeroency Status Form Provide as much information as is available at the time of notification or update. That
. indicated by a
- should be given for initial notification at a minimum.
Date: -
/
/
Time:
a.m.
p.ci.
Person Authorizing Report:
(DCPP only) 4
- 1. _ Notification Type: O Initial Update
- 2.
- Emergency Classification:
Unusual Event O Alert Site Area Emergency General Emergency
- 3.
- Description of Incident:
Date
-/
/
Time Incident Bega'ri:
a.m.
p.m.
a.
Site Emergency Signal Sounded:
Yes O No b.
What Happened:
i 4
Radiological Release Information:
Time Data Collecte'd:
a.m.
p.m.
a.
b'.
- Release:
Occurring C Anticipated--When:
a.m.
p.m.
- 5.
- Location of Release: O Plant vent C Steam O Surface tiouie Discharge
- 6.
- Estimated Duration of Release:
Hours Form and Quantities of Release Materials:
- 7.
- Release Monitored:
Yes O No Describe:
- 8.
- Physical Form:
Liquid O Gas Particulate
- 9. *!odine: O ouantity O Release Rate Ci(Ct/sec)
- 10. *Particulates: O Quantity OReleaseRate Ci(Ci/sec) 4
- 11. Soble Gases: O ouantity 0 Release Rate Ci(Ci/sec) 2 12.
Estimate of Surface Contamination:
dpm/100cm '
- Where:
- 13. Unusual Radiation Levels in Plant: Where:
mR/hr:
- 14. ' Meteorological Date (Use 10m elevation on primary met tower or
)
Nind Velocity:
mhecx2.2
=_mp h Direction (from):
deg
- 16.
- Weather Conditions:
Rain
- Clear O Fog O Cloudy y
._i y
4
=-,y--m,-,-q-y-
,-y_-
y
Part 1. Radiological Emercency Status Form Status v Sheet 2 of a O
Stability:
Class:
Sigma A (deg):
T:
C/m (10 m to 76m) 18.
Plume Center Line Arrival Dose Projections Time Dose Rate Integrated Dose Affected Sectors Site Boundary 2 Miles 5 Miles 10 Miles
- 19. cRecommended Emergency Ar.tions/ Protective Measures (who is to do what -- provide standard message to county / states using EP G-3):
20.
Emergency Response Actions Underway by PGandE:
- 21. (Prognosis for Escalation or Termination of Accident:
g Data Transmitted By:
This Data Sheet Filled Out By:
Date:
/
/
Time:
a.m.
_p.m.
cc DJBaxter/Public Information Recovery Manager WHFujimoto/ Engineering & Logistics Recovery Manager WBKaefer/ Advisor to the County Emergency Organization RFlocke/ Corporate Law Department Coordinator SMSkidmore/DPSerpa/ Radiological Emergency Recovery Manager JDTownsend/ Operations and Analytical Recovery Manager EOF Status File EOF Emergency Status Board UDAC JDShiffer/ Recovery Manager O
Status #
' Sh'" 3 #4 Pacific Gas and Electric Company-Department of Nuclear Plant Operations Diablo Canyon Power Plant Unit Nos. 1 and 2
[~'T -
Part A: Miscellaneous Emercency Information Form
()
Provide as much information as is available at the time of notification of update.
Date:
/
/
Time:
a.m.
p.m.
Person Authorizing Report:
.(DCPPonly) 1.
Notification Type: O Initial C update Time oata Collected:
a.m.
p.m.
2.
Personnel Injuries: How Many?
a.
Type:
Contamination:
Yes O No -
b.
Injured Person Location: O Plant O Ambulance O Hospital
-3.
Fires:
a.
Location:
Time Reported:
a.m.
p.m.
b.
Type:
Electrical O Fuel c.
Contamination Present: 0 Yes No d.
Fire Assistance Requested: 0 Yes No
( 7 e.
Fire Assistance Onsite: O Yes No V
~ - -
4 Security / Safeguards:
a.
Bomb Threat:
Search Conducted: O Yes O No Search Results:
Site Evacuated: Oyes ONo b.
Intrusion:
Insider:
Outsider:
Point of Intrusion:
Extent of Intrusion: _
Apparent
Purpose:
c.
Strike / Demonstrations:
Size of Group:
Purpose:
d.
Sabotage:
Radiological: 0 Yes CNo
. Arson: 0 Yes O No Equipment / Property:
e.. Extortion:
Source (phone, letter, etc.):
(
/^\\
Location of Letter:
U l
Demands:
y
Part'A. Miscellaneous Emercency Informatica Form Status d Sheet a of 4 f.
General:
Firearms Involved: O ves no violence: O ves O no g
Control of Facility Compromised or Threatened: 0 Yes no Stolen / Missing Material:
Agencies Notified (FBI, State Police, Local Police, etc.):
5.
Press Information:
Location of Press Release:
San Francisco O San Luis obispo 0 0ther:
Time of Press Release:
a.m.
p.m.
News Media Interest: 0 Yes O no Local / national:
Data Transmitted By:
This Data Sheet Filled Out By:
Date:
/
/
Time:
a.m.
p.m.
DJBaxter/Public Information Recovery Manager
(
WHFujimoto/ Engineering & Logistics Recovery Manager WBKaefer/ Advisor to the County Emergency Organization RFlocke/ Corporate Law Department Coordinator SMSkidmore/DPSerpa/ Radiological Emergency Recovery Manager JDTownsend/ Operations and Analytical Recovery Manager EOF Status File EOF Emergency Status Board UDAC JDShiffer/ Recovery Manager 1
O 9
a
.?
4 nv I
C l
E l
Si S
I W
I S
E 6
t I
l l
A l
l
'S N
N E
0 V
I 1
G T
A t!
l l
E l
t El u
G C
A a
l'OM E
S l'
S l
K I
l' N
l l
1 l
A1 l
i 1 E T
l l' n A
i Al l'
C o
EN l
l f
O i
ICY f
UN Q
NA H
C F
Y Y
0O C
B N
l l
l 2
=
i iA lt f
l l
IHt
~H D
i l
k E
E A
l l
l' EA K
E t
+
I m
EH I
I NO I
TA N
I O
L I
I T
F A
F
)
0 C
A 0
I F
1 I
(
T D
N E
0 f
E 0
i I
l A
/
E
. O7 Y
C N
N O
1 S
2 I
t 2
E l
9 R
E I'
K 8
1 E
I t
i4