ML19354D439
| ML19354D439 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/25/1989 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-891025-01, NUDOCS 8911090058 | |
| Download: ML19354D439 (70) | |
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EPIP INDEX PROC NupeER TITLE REV DATE DISK i
BtP 200-0 Emergency Conditions INDEX N/A N/A 00018 BZP '90-1 Byron Emergency Action Level 00 89/01/31 0515A/0021A (Primary Responsibility - Station Director) f, BZP 200-Al Byron Nuclear Power Station PWR Emergency 11 89/10/12 0516A/0029A Action Levels (EALS)*
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4 STATION BLOCK INDEX DATE 10/25/89
-1 FINAL 1
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(01058/00038/4)
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{,,
,l' BZP 200-Al 17 - <
Revision 11 ff Bvnal tax 1 EAR PRER STATEMI i
p' ' -
r l
PIE DEREldEY ACTIml LEVELS (EALS)*
p e.....e.......e.................eeeeeeene...e eeeeeeeeeeeeeeeeen p
gg e
a 1.
After clastifying the event, go to BZP 316-1 Initial t
Ilottficattens and GSEp t,
- er BZP 316-5 Acting t
Statten Director.
g
',a --
?
e e
2.
It is the prerogative of the Station Ditector te-j epgrade the condition classification as he deems
[
7&
necessary.
l i
P 3.
If more than one distinctive EAL of different classificatten levels, ie. an EAL for Alert and an EAL for Site Emergency are reached ensure that the highest
- classificatten level reached (or a higher classtfication level) is declared.
e l
4.
If more then one distinctive EAL of the same classification level I.e., two EAL's for Site Emergency
- y are reached; consider classificetten at a higher i
classificatten level. This does not apply to two EALs which are worded identically but listed ender different
- conditlen nushers.
(
Values generated by inoperble er failed instrumentatten s
5.
shecid not be ottilmed for classificatten purposes.
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeseeeeeeeeeeeeeeeeeeeeene i
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- i.
APPROVED o,l ;
OCT 121969 (0516A/0029A/092789)
~
4.
i' S
,p j
j l~' /
$ZP 200-A1
i Revision 11 EVEL IRELEAR PthER STAfraN
^
l nei nsaaracy Acrian trwts trAtsia CIMEb1TItut M
j i
1.
Radioactive Effluent Release To The Envirennent 6\\
e A40edel Classification 3
o Geseous Effluent Releases - IIe Core Demoge 4
l e Geseous Effluent Releases - Core Damage 5
~
e Geseems Releases - Dese Projections available 6
o Liguld heleases 7
2.
Less Of,Fissiese Predect terriers e Less Of Barriers-8 i
o Core Damage /Centainment Parameters 9
- RCS Deense le 3.
System Malfuncitons o Degraded Equipment. ATWAS, Safety Limit. Deee Assessment Less 11 e Phone Less Annunciators Power, Less of Feeduster 12 4 Secondary System len1 functions o Steam / Food Brook, S/G Leekage Less of Feeduster 13 5.
Fuel Itandllas Accident e Radiation Levels, Feel Peel Level 14
- (
6.
lintural and Destrective Phenomene
~'
~ ~ ' ' '
e Degraded Equipment, Fire, CR Evacuation 15 l
e High Winds. Tornede. River Level, Aircesft Crash 16 l
e Earthquake. Emplosion. Turbine Failure, Safety Lleit 17 7.
Henardees. Toute er Flasamble Materials o Liquid /Ges Releases. Injured Person, CR Evacuation. Emplesien 18
^
l 8.
Security Threat o Sebetage, Bemb. Hostage, Forced Entry, Unesual Aircraft Emplosion 19 i
9.
Other Conditlens of Equivalent Magnitude e Aueroness Or Activation Of Emergency organisetten, Unusual Aircraft, l
Inadvertent Dilution, Uncontrolled Red Withdrous1, Fuel Pool Level, l
Plant Red Level Increase, Degraded Core Coeling 20 l
- 10. Personnel Injury 21
- 11. Transportatten Accident 22 l'o I
O.
APPROVED l.
OCT 121969
-2_
(0516A/0029A/092789) 8.O.S.R.
u.--..-..-.-..-
~.
g n.
2 B2P 200-Al
,y Revision 11
'"
- Cs SYRM EMIIGENCY ACTION LEVELS
{
CSIGITION 1.
hAD10 ACTIVE EFFLUENT RELEAKS TO YtE EWIROWENT M5E4 SITE lENERAL u '6.'
ALERT DEINENCY DERGENCY (a - g)
(h - p)
(q - )
(sa-ah) 3 One of the following:
One of the following:
One of the following:
One of the following:
i I
I I eAmaus RELEA m l
l SECTI0li I ENTRY CWWITIONS: A4WDEL IS SOLE 00SE PROJECTION MIDEL AVAILABLE FOR CLASSIFICATION.
l l NO ofter DOSE PROJECTION CALCULATIONS ARE AVAILABLE.
ISEN A RELEASE !$ NOTED, leNITOR THE A-800EL l i
l UN A 15-8ttlWTE INTulVAL TO ENSURE OPUIABILITY Afm STATUS.
l l ISTE: IntNAL DOSE PROJECTIONS WhL IST BE PDtFOIBED BY CONTROL ROON PDt90leEL.
l l
I I
- a. A-Model classification
- h. A4tedel classification
- q. A-Model classification za. A-Model classifica-of Unusual Event is of Alert is ande and of Site Emergency is-tien of General made and 15611 W6-11 sipifies actual ande and 156-11 Emergency is made l
sipifles actual release in progress.
si ptfies actual and W611 si ptfies release in progress.
release in progress.
actual release in progress.
O i d
[
l' l
l t
I i
~
Emergency Action Levels (EALS) b, c,1, r, s, & zb for Gaseous releases appear en next page.
Conditten I continued next page.
5 APPROVED 1
OCT 121969 8.O.S.R.
(0516A/0029A/092789)
b~,,
<ll g
~
s BZP 200-Al Revision 11 BYRON EMERGENCY ACTION LEVELS LONDITION 1.
RADI0ACT!YE EFFLUENT RELEASES TO THE ENVIRONMENT UNU$UAL SITE GENERAL EVENT ALERT EMERGENCY EMERGENCY (a - ni th - al la - 21 fra - rhi One of the followingt One of the following:
One of the followingt One of the following:
ll l
ll GASEDU$ RELEASE l
L SECTION 2 ENTRY CONDITIONS: A-M00EL !$ IN0PERA8LE AND NO OTHER 00$E PRO.1ECTION CAPABILITY !$ READILY l
j l
AVAILABLE ate! ALL OF THE FOLLOWING ARE MEf t l
[
A) AVERAGE OF TEN (10) HIGHEST CORE THERMDCOUPLES LESS THAN 1200'F l
l
- 8) CONTAINMENT RADIATION LEVEL LESS THAN 200 R/hr.
l C) RVLIS lilDICATION > 01C PLENUM.
l L 0) LESS THAN 5 R/hr ON FLML HANDLING ARMS.
l I
i l RELEASE RATES ARE ON A PER STATION BA$!$.
l l
l b.
Instantaneous noble
- 1. Instantaneous noble ab. Instantaneous noble-gas release rate is gas release rate is gas release rate is greater than or equal greater than or equal greater than or equal 5
5 7
to 2.52x10 vC1/sec.
to 3.30x10 vC1/sec.
to 1.01x10 uC1/sec.
(as indicated by WRGM (as indicated by WRGM, (as indicated by WRGM,
(
-RE-PRO 30 (RM-11
-RE-PR030 (RM-11
-RE-PR030 (R511
(
-PF 430))
-PF430))
-PF430)).
c.
Instantaneous lodine i
release rate is greater j
than or equal to 2
2.67x10 uct/sec.
(as indicated by grab
]
sample) j
- j. ',
- r. Noble gas release i
rate averaged for 2 minutes is greater than or equal to 6
5.817x10 uC1/sec.
(as indicated by WRGM,
-RE-PR030 (RS11
-PF430)).
p
- s. Noble gas release l
rate averaged for 30 a:inutes is greater g
than or equal to S
l 5.07x10 uCi/sec.
OCT 121989 (as indicated by WRGM,
-RE-PR030 (RS11 B. O. S. R.
1
-Pr4303).
l0 m
.' )
Emergency Action Levels (EALS) d, j, f, t, u & ac for Gaseous release appear on next rage.
1 (0516A/0029A/092789) l l
l
....__L
,(
e BZP 200-Al Revision 11 s
BYRON EMERGENCY ACTION LEVELS CONDITION 1.
RADI0 ACTIVE EFFLUENT RELEASES TO THE ENVIRONMENT (continued)
UNUSUAL SITE GENERAL EVENT ALERT DERGENCY ENERGENCY
_fa - e)
(h - n) fa - m) fra-th)
One of the following:
One of the following:
One of the following:
One of the following:
l l
l GASEOUS RELEASE l
l OECTION 3 ENTRY CONDITIONS: A-M00EL I$ IN0PERABLE AND N0 OTHER DOSE PROJECTION CAPABILITY !$ READILY l
l AVAILABLE Atg Atil 0F THE FOLLOWING ARE MET:
l l A) AVERAGE OF TEN (10) HIGHEST CORE THERMOCOUPLES GREATER THAN 1200'F l
l B) CONTAINMENT RADIAT!0F t.'. VEL GREATER THAN 200 R/hr l
ll C) RVLIS IISICATION = 0% PLENUM l
l l
l l Release rates are on a per $tation basis.
l l
I d.
Instantaneous noble j Instantaneous noble
- t. Noble gas release rate ac. Instantaneous noble pas release rate is pas release rate is averaged for 2 minutes pas release rato is greater than or equal greater than or equal is greater than or greater than or equal 4
4 6
(A to 4.09x10 9C1/sec:
-- to-5 84x10 uct /sec.
equal to 2.11x106 to 4.22x10 uct/sec.
,. i,
[es indicated by WF iM (as indicated by WRGM, uC1/sec.
(as indicated by WRGH,
-RE-PR030 (RS11
-RE-PR030 (RS11 (as indicated by WRGH,
-RE-PR030 (RM-11
.' ~
-PF 430))
-PF430))
-RE-PR030 (RS11
-PF430)).
~ ' - - " -
-PF430))
- u. Noble gas release rate averaged for i
l' 30 minutes is greater than or equal to
(_
5 2.11x10 uct/sec.
(as indicated by WRGM,
-RE-PR030 (R*ll
-PF430)).
J APPROVED j
p.
OCT 121989 a.o.s.R.
Lf 1
l, Emergency Action Levels (EALS) k. 1 v, w, x, zd, ze & zf for Gaseous releases appear on next page.
l (0516A/0029A/092789)
e,___.4a 4
s.
m._
-w:
4
(
6 82P 200-Al Revision 11 a?
)
SYRON ENERGENCY ACTION LEVELS i
COWITION 1.
RADI0 ACTIVE EFFLUENT RELEASES TO THE ENVIRONMENT (continued) l UNUSUAL
$1TE GENERAL l
' CERGENCY EVENT ALERT E!ERGENCY 7'
fa - al th - al la - 11 fra-rhl Sne of the fellowingt One of the following:
One of the followingt One of the following:
i I
i l GASEOUS RELEASE l
I l SECTION 4 ENTRY CONDITION $t DOSE PROJECTIONS FROM A-N00EL AND OTHER MODELS ARE AVAILA8LE.
l l
l l
d l NOTE: mNJAL DOSE PROJECTIONS WILL NOT BE PERFORNED BY CONTROL ROOM PERSONNEL.
l d
l l
4.
I I
l I
g g
- k. Whole body dose
- v. Whole body dose ad. Whole body dose pro-projections at the projections at the jections at the site site boundary are site boundary are boundary are greater greater than or equal greater than or equal than or equal to 1 Rom to 250 mRea for actual to 500 mRea for actual for actual or imuninent
(
or launinent releases.
or tuuminent releases, releases.
- w. Thyroid dose pro-ze. Thyroid dose pro-jections at the site jections at the site l
boundary are greater boundary are greater j
than or equal to than or equal to 5 Rom 1
2.5 Res for actual for actual or tsuninent or launinent releases, releases.
f
- 1. As the result of
- x. As the result of af. As a result of i.
confirmed releases releases from the releases from site, from the site, site, confirmed confirmed Field Field Teams are Field Team measure-Team measurements i
needed to assess the monts are greater are greater than i
magnitude of a than or equal to or equal to 1 R/hr.
l' release or its impact 50 mR/hr.
on the environment.
l l
t l
l-g irmergency Action Levels (EALS) e. f. g, m. n, o, p, y. 2, zg and zh for Liquid releases appear on next page Condition 1 continued next page.
APPROVED OCT 121969 l
(0516A/0029A/092789)
- 5. O. S. R.
1
d
.et 6
(
T
-q BZP 200-Al Revision 11
,em.
.[v} '
BYRON EMERGEN0Y ACTION LEVELS CONDITION 1.
RA010 ACTIVE EFFLUENT RELEASES TO THE ENVIRONMENT (continued)
+
UNUSUAL
$1TE GENERAL
~
EVENT ALERT EMERGENCY EMERGENCY
'la - al th - al fa - m) fra-th) 4 One of the following:
One of the following:
One of the following:
One of the following i
I I
-l LIQUID. RELEASE l
3 l
SECTION 5 ENTRY CONDITION: ANY LIQUID RELEASE.
l l
I.
I I
e.
Liquid release greater
?
less than measured by monitors 1x10-6uti/m1 as and confirmed by measured by monitors sample.
and confirmed by sample.
t y
~-.
- f. Total liquid release
- n. Total liquid release
- y. Total liquid release ag. Total liquid release in any consecutive in any consecutive in any consecutive in any consecutive 24-hour time period 24-hour time period 24-hour time period 24-hour time period is greater than or is greater than or is greater than or is greater than or 3
d equal to 4 Ci but less equal to 40 Ci but equal to 2x10 Cl but equal to 2x10 C1.
4 than 40 Ct.
less than 2000 ti.
less than 2x10 C1.
- g. Tritium release
- o. Tritium release greater greater than or than or equal to equal to 3x10-3uC1/mi 3x10-2 ci as sampled.
u but less than 3x10-2 ct/m1 u
as sampled.
- p. Total tritium release
- z. Tritium release in ah. Tritium release in in any consecutive 24 any consecutive 24 any consecutive 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period is hour time period is hour time period is greater than or equal greater than or equal greater than or equal d
5 2
to 2x10 Ci but less to 2x10 Cl.
to 5x10 Cl but less 4
5 than 2x10 C1.
than 2x10 C1.
APPROVED OCT 121989 B.O.S.R.
e-,
(0516A/0029A/092780)
..n
p
( l.
p B.'P 200-A1
- l.g' Revision 11 l
y
.[
BYRON ENERGENCY ACTION LEVCLS
' V CONDITION 2.
L0$$ OF FIS$10N PRODUCT BARRIERS UNUSUAL
$1TE GENERAL EVENT ALERT EERGENCY EHERGENCY la - h) f4 - ni fa - r1 in - u)
, i 1
One of the One of the One of the One of the following:
following:
followings following:
I I
I" l THE FOLLOWING INDICATIONS REPRESENT A L0$$ OF. OR CHALLENGE TO EACH OF THE THREE (3) F1SSION PRODUCT l l BARRIER $ FOR CLAS$1FICATION PURPOSES. USE THIS CRITERIA TO ASSESS THE CONDITIONS OF 1. o, and s.
l l
l
.l
- 1) Cladding l
l a.
Grab sample activity equivalent to 300 uti/g dose esuivalent of I-131.
I 1
l l 2) Reactor Coolant System l
(
l.
a.
RCS pressure less than or equal to 1829 PSIG etEl l
j l
b.
Containment pressure greater than or equal to 3.4 PSIG Algt l
t l
c.
No indications of Secondary $1de Break within containment.
l 1
l l 3) Primary Contairment l
l a.
Containment pressure greater than or equal to 50 PSIG QR l
l b.
Containment temperature greater than or equal te 2500F QR l
(n' l
c.
Unisolable breech of the containment QR l
l l
d.
Hydrogen concentration greater than or equal to 5%.
l j
l I
- 1. Loss of or challenge
- c. Loss of or challenge
- s. Loss of or challenge l
to one of the three to inn of the three to his of the three I
Fission Product Fission Product Fission Product Barriers.
Barriers.
Barriers with j
arabable loss of the third Fission Product Barriers.
- v)
' APPROVED OCT 121989
- 9. O. S. R.
Emergency Action Levels (fALS) a,b.c,d,e,j,k,1.p,q,t.u and v appear on next page.
,\\
Condition 2 continued on next page,
-S-(OS16A/0029A/092789)
+
t W
BZP 200-Al l
,1 c'
Revision 11 i- -
BYRON ENERGENCY ACTION LEVELS 2
'/
C00eIT10N 2.~
LOS$ OF F155 ION PRODUCT BARRIERS
,.V' (cont'd) 1
~
UNUSUAL
$1TE GENERAL j
'O EVENT ALERT
.EERGENCY EERGENCY i
f a - h) ft - ni fa - r) in - si i '
One of the One of the One of the One of the
' . 72 fellowlngI fc116wlngi fc110wingi foilowlng:
cort RAMAGE
- a. Dese equivalent I-131 coolant activity enceeds the allowable operational limits in i
the Technical Specift-
"<,s cations.
- b. Average of ten (10)
- j. Average of ten (10)
- p. Average of ten (10)
- t. The average of the highest incore.
highest incore highest incore
' ten (10) highest thermocouple readings thermocouple readings themocouple readings incere thermocouple
~l is greater than or is greater than or is greater than or readings is greater equal to 708'F but equal to 12000F but equal to 16500F and than or equal to 1,.
-' *a less than 12000F.
less than 1650'F.
decreasing within 5 16500F and in-(Using _TI-001/002)
(Using -TI-001/002) minutes after cooling creasing af ter cooling is established per is established for DFR C-1 (Using,,71-greater than 5 minutes 001/002) or cooling has not been established per 8FR C-1.
i f
(Using _TI-001/002)
(Same as 6sc. 9m)
- c. Failed fuel monitor
- k. Failed f9e1 monitor
(.REPR0068 (R bli
[.REPR0068 (R511
_PS206)) indicates
_PS206)) indicates greater than or equal greater than or equal to 0.22 vCl/ml indica-to 2.2 uCi/m1 Indica-tive of 0.1% fuel tive of 1% fuel g
failure.
failure.
1 CONTAlt#ENT
- u. Primary Containment radiation level is radiation levt1 is radiation level is radiation level is greater than or equal greater than or equal greater than or equal greater than or equal to 1x102 R/hr but to 2x102 R/hr but to 4x102 R/hr.
to 2x103 R/hr. etEl 2
2 less than 2x10 R/hr.
less than 4x10 R/hr.
probable loss of Primary Containment.
f^
- v. Events are in progress S@
integrity is degrcded or have occurred which such that a Technical involve actual or q'.,.
Specificatton Liniiting inuitnent substantial Condition for Operation core degradation or
. requires a shutdown and melting with probable power decrease for loss of containment reactor shutdown has (Same as 30.41.6ab.91) connenced.
Od Emergency Action Levels (EALS) f.g.h.m.n 8. r appear on next page.
APPROVED Condition 2 continued next page.
'a
'OCT 121969 (0M6A/0029A/092789)
B. 0. S. R.
~
W
\\
BZP 200-Al Revision 11 BYRON ENERGENCY ACTION LEVELS
- s
\\,
CONDITION 2.
LOSS OF FIS$!ON PRODUCT BARRIERS (con 6'd)
~
L UNUSUAL
$1TE GENERAL EVENT ALERT ENERGENCY ENERGENCY j
.' 7 fa - hl f1 - n) to - el fa - v) p One of the
'One of the One of the One of the followingt following:
following:
following:
i RCS DANAGE
'.i
- m. A greater than 50 ppe i
1eakage requires the-leakage rate as 7
initiation of a plant indicated by either shutdown per the leak rate calculations 3
Technical Specifica.
charging pump flow or tions and power decrease VCT level changes.
for reactor shutdown has commenced.
- n. Primary system
- r. Primary system leakage is beyond leakage is beyond makeup capabilities makeup capabilities of available of available ECCS.
7g, charging pumps.
- g. ECCS initiation signal and resultant injection to the vessel. (Not spurious)
- h. Failure of a primary
- 1 system safety valve to c1cse QR l
failure of a primery l
PORV to close and its isolation valve will 1
l-not isolate.
i 1
l
["
l l'.
llO
'.s.L APPROVED i
OCT 121989
_ig.
(0516A/0029A/092789)
S.Q.S.R.
c.
_.. _. ~..
~.
N'
.4 l
'iit, BZP 200-Al Revision 11 BYRON EMERGENCY ACTION LEVELS I
[
CONDITION 3.
SYSTEM MALTUNCTIONS V.
I UNUSUAL SITE GENERAL ~
EVENT ALERT EMERGENCY EMERGENCY l
la - el fi - 1)
(1 - n) to - ni One of the following:
One of the following:
One of the following:
One of the following e
- s. Equipment described
- f. Equipment is degraded J. Equipment is degraded
- o. Events are in progress j
in the Technical-such that only one such that only one or have occured 1
Specifications is system or means is system or means is which involve actual l
4 degraded such that available for achieving available for achieving or inminent a Limiting Condition and maintaining a Mode and maintaining a Mode 4 substantial core for Operation i condition (Cold Shut-(Hot Shutdown) condition degradation or melting requires a shutdown down) except during except during with probable loss of and power decrease controlled planned controlled, planned containment integrity.
for reactor shutdown-evolutions.
evolutions.
(Same as 2v,41,6 b,91) has cosmonced.
(Same as 6j)
(Same as 6v)
(Same as 6a) s a
9
- g. Failure of.the Reactor
- k. Failure of the Reactor p.
Reactor has not tripped Protection System in.
Protection System etEl the average of the strumentation to instrumentation to ten (10) highest incore initiate and complete initiate a reactor thennotouple readings is an automatic rea: tor trip which brings the greater than or equal to trip which brings the reactor subcritical 16500F and increasing reactor subcritical once a limiting safety-after cooling is l (
cnce a limiting safety system setting has established for system setting, as been exceeded etEl greater than 5 minutes specified in the Tech-fallere of manual QR cooling has not been nical Specifications reactor trip.
established per BFR C-1 l-has been exceeded.
(ATWS Event - Manual (Using _TI-001/002)
L (ATWS Event - Manual Trip Unsuccessful) frip Successful) h
- b. Loss of normal and l
l..
alternate means such i
l that accident classification or
.t offsite dose assessment l
cannot be made.
1 l
- h. Technical Specifications j
Safety Limit has been exceeded j-(Same as 6s).
l L
Emergency Action Level (E/,LS) d, e,1, e, n and q appear on next page.
I Condition 3 continued on next page l
APPROVED s
L. c.
1.,
OCT 121989 (0516A/0029A/092789)
B.O.S.R.
1' l'
~,
7.> 7,,s s
y<
.A
'iy: s.
1 l
q, '.99 BZP 200-Al L
L*. c.
Revision 11
]
BYRON EMERGENCY ACTION LEVELS l
4
,. m
' r'~N) ;'
C00SITION 3.
$YSTEM MALFUNCTIONS
{
i tl ii" F l "
. UNUSUAL SITE GENERAL l,.
EVENT
. ALERT-EMERGENCY EMERGENCY K.<-
. _13. el f f. 41 (1 - ni to - a)
(
L.'. 4, _
One'of the following:
One of the following:
One of the following:
One of the following:
q lF.
- c. Loss of cessercial si f.
telephone communica-f
,i
~tions and NAR$.
t gg.
Q,U loss' of commercial-telephone communica-tions, MPN and ENS.
)
e
. l. Unplanned loss of most..
4 "J
or all annunciators on ECCS Panel, heactor
- ,?,
Control Panel and Electrical Panel.
. d.' Loss of power to the
the Units's System Auxiliary Transformer-l in Modes 1-4.
~
i
,- \\,
' e. Loss of all Diesel.
m.' Loss of power to the 4-KV f
'\\ f
' Gen u ators sh offated ESF buses from the' Unit's
^'
.with the Unit in System Auxiliary Trans-'
Modes.1-4.
fonsors elf Loss of all Diesel Generators associated with that Unit.
t
- n. Loss of all Feedwater
- q. Loss of all Feedwater and all Auxillary Feed-and all Auxili wy Feed-water water ele ele the Residual Heat the Residual Heat Removal System is not Removal System has not available in Modes 1-4.
been available for (Same as 4h) 45 minutes or more in Modes 1-4.
(Same as 4j) r
.T
_(-
/
3._
APPROVED OCT i 21969
_iz_
(0516A/0029A/092789)
B. O. S. R.
m
. ~
n y
p 3 :..
BZP 200-Al i
y Revision 11 BYRON EMERGEhCY ACTION LEVELS
. /D
, l,]
CONDITION 4.
SECONDARY SYSTEN MALFUNCTIONS UNUSUAL SITE GENERAL.
f gw EVENT ALERT EMERGENCY EMERGENCY I
5 fa - c)
(d - a) f f - h) fi - ()
C' One of the-One of the One of the One of the
'"?
following following following:
following:
- a. Main steamline or
- d. Main steamline break
- f. Main steamline break i
feedline break that er feedline break or feedline break results in rapid with greater than or with greater than or depressurization of equal to 10 ppm equal to fifty (50) gpm the secondary system.
primary to secondary primary to secondary
{
j,,
leakage.
leakage Mit average of ten (10) highest incore thermocouple readings is greater than or equal to 708'F.
t
- b. Exceeding primary to
- 1. Events are in progress i
secondary leakage or have occured rates as specified which involve in Technical Speci-actual or cations. (See also Imminent substantial
,3
)
eat #2f.)
core degradation or l
\\,_,/
melting with probable loss of containment l
integrity.
(Same as 2v So, 62b, 91.)
l
'\\'
l-
- e. Rupture of Steam g.
pupture of Steam Generator tube (s) is Generator tube (s) is beyond the capability beyond the capability of evallable charging of available ECCS.
l pumps.
l L
- c. Any Feedwater malfunc-h.
Loss of all Feedwater J. Loss of all Feedwater tion resulting in a and all Auxiliary and all Auxiliary sustained feedwater Feedwater Feedwater inlet temperaturt Mg1 Mgl to the steam generators the Residual Heat the Residusi Heat of less than 70'F with Removal System is not Removal System has not primary / secondary sides available in Modes 1-4.
been available for l
200 psig.
(Same as 3n) 45 mins. or more in l
Modes 1 4.
L APPROVED cs,,,,, 3,3 L -Q OCT 121989 g
i..V a.o.s.n.
1.
-13 (0516A/0029A/092789) l
~
. [ ' {.,,
B2P 200-Al l
, 1* $.
Revision 11 BYRON EERGENCY ACTION LEVELS
- ? e-Q l
f s.
'(jj CONDITION 5.
FUEL HANDLING ACCIDENT
.(.
UNUSUAL SITE GENERAL
=
1.,y EVENT-ALERT ENERGENCY ENERGENCY fa - c) id. f) m P,
One of the following:
One of the following:
- a. While handling fuel in
- d. While handling fuel in containment, an containment, an f,y,.
increase in radiation increase in radiation levels by a factor of levels by a factor of 1000 has been confirmed 1000 has been confirmed
,?
M M
~ Containment Charcoal Conta?nment Charcoal Units are in service.
Units are inoperable.
- b. Radiation levels in
- v. Radiation levels in the Fuel Handling Building Fuel Handling Building are greater than or are greater than or
~i equal to 100mR/hr as equal to 100mR/hr as
~ indicated by indicated by ORE-AR055/56 and ORE-AR055/56 and
( j$
confirmed confinned
\\
'~
m a
Fuel Handling Bldg.
Fuel Handling Oldg.
r Exhaust has been Exhaust charcoal filters 1
diverted through the are depleted or inop-charcoal filters.
erable.
\\
- c. Fuel Pool level with
- f. Fuel Pool level irradiated fuel in decreases below the the pool decreases top of irradiated below the Technical fuel.
Specification Limit.
(Same as 9j)
($ame as 9g) i
)
i I
\\
t f
Q APPROVED OCT 121989
-14.
(0516A/0029A/092789)
B.O.S.R.
.-+E..
.- - '. - ~ - -.
v
-. -, - - - ~,.,,. - - -,,, -
't BZP 200-Al
- y'S' Revision 11
p BYRON ENERGENCY ACTION LEVELS g
4 C0WITION 6.
NATURAL AND DESTRUCTIVE PHENOMENA (EARTHQUAKE, EXPL0S!ON, FIRE, FLOOD, TORNADO, $U$TAINED WIND $, AIRCRAFT CRA5H 98 HIS$1LES FROM WHATEVER $00RCE$)'
UNUSUAL
$1TF.
GENERAL EVENT ALERT EERGENCY EERGENCY fa - ()
ft - t) f u - mm)
(mb - me)
One of the following:
One of the following:
One of the following
_One of the following:
- a. Equipment described J. Equipment is degraded
- v. Equipment is degraded za. Events are in progress in the Technical such that only one such that only one or have occurred which Specifications is system or msans is system or means is involve actual or degraded such that available for achieving available for achieving inuntnent substantial.
a Limiting Condition and maintaining a and maintaining a Mode 4 core degradation or for Operation
- mode 5 condition (Cold (Hot $6utdown) condition melting with probable e
requires a shutdown Shutdown) except during except during loss of containment and power decrease controlled, planned controlled, planned integrity.
for reactor shutdown -
evolutions.
evolution.
(Same as 2v, 3o, 41, has comunenced.
($ame as 3f)
(Same as 3j) 91)
(Same as 3a)
- b. Damage is such that
- k. As the result of a ab. The average of the
}
off-site assistance natural or destructive ten (10) highest
[V is required to prevent phenonema a Safety incere thermocouple further degradation of' System is affected readings is greater-the level of safety such that it may not than or equal to of the facility, perfom its required 16500F. and function.
increasing after cooling is established for greater than 5 minutes or cooling has not been established per-BFR C-1.
(Same as 2t,9m)
- c. Fire that*cannot be extinguished within 10 minutes of arrival of the on-site Fire Brigade.
- 1. Control Room evacua-
- v. Control Room evacuation tion is anticipated is required ANQ control or required with is not established fro" APPROVED control established local station within from local stations 30 minutes.
gjgg within 30 minutes.
(Same as 7h)
A
( S*" 'S 70 B. O. S. R.
Emergency Action Levels (EALS) d, e, f, g, m, n, o, p, q, x, y, and z appear on next page.
Condition 6 Continued on next page. (0516A/0029A/092789)
V i
BZP 20041
- 't Revision 11 BYRbN EMERGENCY ACTION LEVELS I
'(
)
. v' CONDITION 6.
MTLRAL AND DESTRUCTIVE PHENOMENA (EARTHQUAKE, EXPL0$10N. FIRE, FL000 TORNADO. SUSTAINED WINDS. AIRCRAFT Y-CRASH E MI$$1LES FROM WHATEVER i '
SOURCES) i
.s UNUSUAL SITE GENERAL EVENT ALERT EIERGENCY EMERGENCY fd - al in - a)
(w - 21 frb - re)
.i One of the following:
One of the following:
One of the following:-
One of the following:
- m. Sustained winds
- w. Sustained winds (i.e. existing for 15 (i.e. existing for 15 minutes or more) of minutes or more) of greater greater than or equal than or equal to 85 mph.
to 75 mph.
- d. Tornado striking within n.. Tornado striking the protected area.
Vital areas within l
the protected areas.
f-
- e. River level prolacted to c. River level greater
- x. River level is greater
)
i
- rise above 702 Ft. (MSL) than or equal to 702 Ft.
than or equal to l
with less than two (2)
(MSL) with less than two 708.3 Ft. with a unit not
~{
6
~
deepwell pumps operable (2) deepwell pumps in Cold Shutdown R Refuel.
i or less than two (2) operable or less than two UHS basin leves) 182L (2) UH$ basin levels 182L
- f. River level oraiseted
- p. River level is less than i.
to fall below 664.7 f t.
or equal to 664.7 f t. (MSL) k (MSL) or flow less than or flow less than 700 cfs I
700 cfs with less than with less than two (2) two (2) deepwell pumps deepwell pumps operable operable or less than or less than two (2) two (2) UHS basin levels UHS basin leves1182L 182L
- g. Aircraft q, Aircraft
- y. Aircraf t isipacted impacted within impacted within l
onsite.
the protected the protected i -.
area but not area and is
(;
affecting vital affecting areas.
vital areas.
L L
1 Emergency Action Levels (EALS) h
- 1. r, s, t and sa appear on next page.
1.
i l
Condition 6 continued cn next page.
(
l a, '
APPROVED OCT 121989 5.O.S.R.
(0516A/0029A/092789)
L
- cef,
.'s.
6 p
S2P 200-Al Revision 11 e-BYRON EMERGENCY ACTION LEVELS CONDITION 6.
NATURAL AND DESTRUCTIVE PHENOMENA (EARTHQUAKE, EXPLOSION. FIRE, FLOOD, TORNADO, SU$TAINED WINDS. AIRCRAFT i
CRALH H MISSILES FROM WHATEVER
$00RCES)
UNUSUAL
$1TE GENERAL EVENT ALERT ETRGENCY EMERGENCY j
(h - i) ir - t) fra) frb - nel One of the following:
One of the following:
One of the following:
One of the following:
- h. Earthquake at a level
- r. Earthquake z.
Earthquake greater than or at a level experienced at equal to 0.02g greater a level greater (Alarm Setpoint) is than or equal than or equal confirmed (non-to 0.09 g to 0.20g (Safe spurious actuation)
(Operating Basis Shutdown Earthquake)
E Earthquate) is confirmed with a Notification of (Non-spurious unit not in Cold equivalent earthquake actuation)
Shutdown or Refuel, received from reliable M
M or-site sources in Notification of Notification of various plant locations equivalent earthquake equivalent earthquake or of fsite cognizant received from outside received from outside
(, /
sources.
cognizant sources.
cognizant sources.
- l. Explosion within the protected area.
(Same as 7d, 8h)
- s. Technical Spect-fication Safety limit has been exceeded.
($ame as 2g)
- t. Main Turbine failure causing casing penetration.
d APPROVED
...s OCT 121989 (051bA/0029A/092789)
B. O. S. M.
(
p,.
y.
BZP 200-Al Revision 11 BYRON EMERGENCY ACTION LEVEL $
m
. I
)
.Q CONDIT!0N'7. HAZARDOUS. T0x!C Oft rLAMMAsLE MATERIALS 1
UNU$UAL
$!TE GENERAL EVENT ALERT EPERGENCY EMERGENCY fa - di fa - f) fa - h)
One of the One of the One of the following:
following:
following!
4
- a. Uncontrolled
- e. Uncontrolled
- g. Uncontrolled release of release of release of toxic or flam-.
toxic or flan-toxic or flam-mable gas at moble gas at sable gas at life threat-life threat-life threat-ening levels ening levels ening levels
+
is confirmed on-site.
is confirmed within is confirwed the protected area.
within vital areas I
- b. Release of large j
quantities of
- flamable, explosive or toxic material p
such that l
plant operation t'
may be affected.
- f. Control Room
- h. Control Room evacuation is evacuation is I
anticipated or required and control l
required with is not established I
control established from local stations from local stations within 30 minutes.
within 30 minutes.
(Same as 6v)
I l'
(Same as 61)
L l
- c. As a direct result of hazardous material l'
a person is killed or hospitallred AND/OR estimated property damage exceeds $50,000.
(Same as 10b, 11a2) l L
APPROVED
- d. Exp1nsion within the
. (O protected area, m 1 2 1989
(
(Same as 61, 8h)
B.O.S.R.
- l (0516A/0029A/092789)
C e'
- e d'
Revision 11
~
j BZp 200-Al BYRON ENERGENCY ACTION LEVELS
.K
?
CONDITION 8.
$ECURITY THREAT UNU$UAL
$1TE GENTRAL 1
EVENT ALERT EERGENCY EERGENCY I
fa - h) it k) i n - n ',
in - el
'e
- ?
One of the One of the One of the One of the u.;
followingt following fc11owing:
followingt
- s. Obvious attempt to
- 1. Security threat of
- 1. Imminent loss of
- n. Loss of physical sabatope safety related increasing severity physical control of control of the equipment, that persists for the facility.
facility.
greater than 60 minutes l
- b. Internal disturbance
- f. Security threat that
- m. Security threat that
- o. Loss of physical j
(a disturbance that is generates an Unusual results in loss of control of the not short Ilved or is Event under control of any vital Control Room due to not a harmless outburst another condition, ates. (For control a security threat.
9 involving one or more Example: Bomb emplo-Room, refer to j
individuals within sion results in loss General Emergency.)
the protected area.)
of plant systems sufficient to classify as an Unusual Event.
(}
\\
- c. Bomb device discovered inside the protected area.
- d. Hostage situation which' disrupts t g normal operation.
- e. Civil disturbance t
L (spontaneous l.
collective group i
i gathering which disrupts normal i
operations.)
l 1
1' I.
- f. Armed or forced
- k. Armed or forced vital l
protected area area intrusion.
p intrusion.
l<
- g. Unusual aircraft activity over the protected area.
(Same as 9b)
APPROVED
- h. Explosion within l' O the protected area.
OCT 121969 V
(Same as 61. 7d)
B.O.S.R.
! (0516A/0029A/092789) l p~
p n
r
,mw, n
e
,e.
w-w
--w..-s-,
,rw,--
,m 7
-r
[
BZP 200-Al Revision 11
',y BYRON EMERGENCY ACTION LEVELS CONDITION 9.
ANY OTHER CONDITIONS OF EQUIVALENT MAGNITUDE TO THE CRITERIA U$ED TO DEFINE THE ACCIDENT CATEGORY A5 DETERMINED BY THE STATION DIRECTOR f..
h r
x UNUSUAL
$11E GENERAL EVFMT ALERT EMERGENCY EMERGENCY la i di f a hi it k) il - m)
One of the following:
One of the following:
One of the following:
- a. A condition that
- e. A condition that
- 4. A condition that
- 1. Events are in progress warrants increased warrants precautionary warrants activation or have occurred which awareness on the part activation of Techni-of the Emergency involve actual or of State andAr local cal Support Center and Operations facility imminent substantial offsite officials.
placing Emerguncy and monitoring teams core degradation or
{
Operations facility or or a precautionary melting with probable i
Corporate Commend Center notification of the loss of containment i
on standby, pubite near the site.
integrity.
(Same as 2v.3o,41,6*b)
- b. Unusual aircraft activity over the l
protected area.
(Same as 8g)
- c. Inadvertent dilution
- m. The ten (10) highest I
such that intore thermocouple y
- 1) Technical Spect-readings is greater f
fication shutdown than or equal to margin requirements 16500 and increasing are violated.
ef ter cooling is-E established for greater
- 2) The control bank than 5 minutes or cooling low low insertion has not been established limit is reached.
- f. ARM reading (s) and per BFR.C-1.
(Using j
survey results ITI-001/002)
.s E
(Same as 2t, 6*c) survey results alone l
confirm an unexpected increase in plant radiation levels by a factor of 1000,
- d. Continous uncontrolled rod withdrawal with entry into DOA R00-1.
i
?
- g. Fuel Pool level with
- j. Fuel Pool level trradiated fuel in decreases below the pool decreases the top of irra-g below the Technical disted fuel.
Specification Limit.
(Same as 5f)
(Same as Sc) h.
Status Trees require k.
Status Trees require APPROVED
'O entry into the entry into the Q
BFR.C2-BFR.Cl-OCT 121989 Response to Degraded Response to Inadequate Core Cooling.
Core Cooling B.O.S.R.
~'y; (0516A/0029A/092789) 1 J
y h,
B2P 200-Al
'a 0 Revision 11
,l
-BYRON EMERGENCY ACTION LEVELS CONDITION 10. PERSONAL INJURY
. UNUSUAL
$1TE GENERAL EVENT.
ALERT
~ EMERGENCY ENERGENCY fan
,r
- a. Transportation of a' radioactively contaminated injured r
person (s) to an offsite i.
medical facility for treatment.
- b. As a direct result of hasardous material a person is killed or.
hospitall ed g igt estimated property damage exceeds $50,000.
(Same as 7c. 11a2) s, i
\\.
L L,
I:
L r-L P
t l
L 1
I i
I l
u APPROVED
~
OCT 121969 (0516A/0029A/092789)
B.O.S.R.
r:
J BZP 200-Al s
Revision 11
}
BYRON DERGENCY ACTION LEVELS
': r '
CONDITION 11. TRANSPORTATION ACCIDENT D
a.
A vehicle transporting radioactive materials or non-radioactive Hazardous materials from a Commonwealth Edison generating station is involved in a situation in which:
1.
Fire, breakage or suspected radioactive contamination occurs involving a shipment of radicactive f
material Dili s
i.
As a direct result of Hazardous materials, i
r t
(a)
A person is killed; or (b)
A person receives injuries requiring hospitalizationi or k
(c)
Eettmated carrier or other property damage exceeds $50,000.
b.
Any other condition involving Hazardous material transportation and equivalent to the criteria in
[
Item a.
l b
i
.f) v l
?
1 l
l I
i i
l l
\\
L l:
l' 1,
l l
(Final) l -..[s APPROVED I.,
OCT 121989 (0516A/0029A/092789)
- 8. O. S. R.
l 1
.h I
.1
,$ 'AJ EP!P INDEX
~
a-j t
i
+*
-t PROC. IU SER TITLE REV DATE DISK
-l i
PWR Emergenty Action Level Philosophy 00 89/01/31 0514A/0021A BZP 210-1 BZP 210-Al Byron Station - PWR Emergency Action Level 02 89/10/17 0517A/0029A (EAL) Philosophy 4
BZP 210-A2 Byron Emergency Action Level (EAL) Philosophy 00 89/01/31 0518A/0030A i
! o-NUREG 0654 Example Initiating Conditions 0
l l
1.
l 1-l^
I "
l l...
STATION BLOCK INDEX
/
DATE 10/25/B9
- d
-i-FINAL l
ll::' i (0105B/0003B/5) 1 1.,
r e
, :. v _ -.,.i..
I-)$'
BEP 210-Al i
Revision 2
(
. f.,r^
1 l
\\~~-
BYRON STATICd l
4 f
l l'
{
PWR ENERGENCY ACTION LEVEL (EAL) PHILOSOPHY W
"* v v.;
[
4 i
T~
This document'is supplied as supporting information on the EALs. The j
purpose of this philosophy document is to provide' additional insight into the EALs in the training, interpretation and revision phases.
'i It serves as a cross reference to other basis documents such as the NUREG-0654 examples, FSAR, Tech. Spges, procedures, etc.
It also can
[
be utilised to include references to Company Directives, interpretations on NRC violations and NRC recommendations.
(The NUREG-0654 examples referenced in this document are contained at the
(
end.) This philosophy document should be referred prior to proposing
\\
changes to existing EALs to insure consistency with existing doc uments.
t
...................................................s............
NOTE
- This document need not be utilised for classification purposes. The EALs should be utilised for timely
- classification purposes as a stand alone document.
f
?
1-APPROVED
(
.t ^
OCT 171969
- o B.O.S.R.
_3_
(0517A/0029A/051389) w-
<--,-e-,--
.--,,we
,----,,n-,
.m u
r,-,,-.,
--,,,,u--,-,,,--.,--,,,,,--,-,--,-,,,n
h.J
.t
..4-g BZP 210-Al 1
i Revision 2
}'
. BYRCRt ENERGENCY ACTICBI LEVEL (EAL) PHILOSOPHY j
Condition 1.
Radioactive Effluent Release i
J Calculation of reportable gaseous release rates and projected
]
y
. downwind dose (rem) will be performed in the TSC tising both P- ?,
WR(Bis. All release rates stated in Condition 1 and explained in j
the basis are for the purpose of classification. Unless
?
otherwise stated, dose rates are gamma whole body.
j
]
EALila A-Model Unusual Event Runnortina datat
- ~
'This EAL is based on output from the A-Model when an actual
- L
. release is in progress.
EALO'1b Noble Gas Release Rate NUREG 0654 amample: UE $2 s
Enunortina datat Classification' release rate is calculated in such a way that release of an normal operation noble gas six will not exceed the Tech Spec dose rate limit of 500 mrom/yr at the site boundary.
The classification release rate is calculated in the " worst" direction (1006m, Southeast) for vent release mode, using annual
(
average (ODCM)' meteorology. This release rate was reduced by a factor of 7 (to 70 mRom/yr.) to avoid situation when EALs based on annual average meteorology (EALs.lb, c, d, 1, j) result in higher release rates than EALs based on a worst case meteorology (EALs Ir, 1s, it, lu, sb, sc). Normal operation noble gas mix used-as a basis of this EAL (and other "no core damage" conditions) is taken from the Byron /Braidwood FSAR Table 11.3-6.- This release rate is determined based on a MRGM monitor j
reading.
EALilc Iodine Release Rate i
NUREG 0654 example: UE 82 g rtino datat The release rate of Iodine is calculated in such a way that dose rate to a thyroid of an infant due to inhalation won't exceed 1500 mrem /yr. at the site boundary. It is based on a vent release mode, annual average meteorology, and the " worst" direction (Southeast). Iodine release rate is determined from the grab samples. All lodine is assumed to be I-131.
APPROVED OCT 171969 (0517A/0029A/051389)
~
_. _.. _. _., ~. _ a -.
-~.
._.~ -
4 BZP 210-Al Revision 2
. fy
]!j BYRGt EMERGENCY ACTION LEVEL (EAL), PHILOSOPHY Condition 1.
Radioactive Effluent Release i
EALl16 Noble Gas Release Rate L
i:.t
- / ]*
MUREG 0654 examples-UE $2
.I
",, b
.sunnartina datas J
Classification release rate calculated in such a way that 0
j' release'of any assumed accident noble gas als at time 0 to 24 hrs post shutdown will not exceed Tech Spec dose rate limit of 500 mres/yr at the site boundary. Assumptions for the calculation (meteorology, release mode, etc.) and conservative 4
i
correction factor are the same as for Condition.la. Given-
{
release rate is' determined based on the WRW( monitor reading.
EALile Liquid Release ***
Supporting datat This emergency action level is based on Table 5.1-1, Emergency Action Levels for Radioactivity in Liquid Effluents, of the Generating Stations Emergency Plan.
EALilf Liquid Release
'l lI ~[
Sunnartina datat This emergency action level is based on Table 5.1-1, Emergency
, ~
Action Levels for Radioactivity in Liquid Effluents, of the Generating Stations Emergency Plan.
EAL91g Liquid Release ***
sunnartina datat This emergency action level is based on Table 5.1-1, Emergency Action Levels for Radioactivity in Liquid Effluents, of the Generating Ste,tions Emergency Plan.
EALilh A-Model ALERT Supportina datat This EAL is based on output from the A-Model when an actual release is in progress.
l l-li
- Values have been converted from uC1/ml to uCi/g to coincide with L
Tech. Spec. values and chemistry procedures which assume a l
11guld at STP with density at Ig/cc.
1; l
APPROVED OCT 171989 B.O.S.R.
(0517A/0029A/051389)
o i
e-s t
i k BZP 210-Al i
7 7,..
Revision 2
- .'/ p.
t J
BYRON EMERGENCY ACTION LEVEL (EAL) PHILOSOPHY
.v
?q Condition 1.
Radioactive Effluent Release EALill Noble Gas Release Rate
,,, a s, "f* :
MUREG 0654 exemples' AL $15 A ;,
Supporting data Classification release rate calculated in such a way that-release of a normal noble gas mix will not escoed 10 times Tech Spec. dose rate limits at the site boundary, i.e.,
5000 t
-arem/yr. This release rate is established at a level 1.4 times q; '.
the EAL lb release rate. All other assumptions and correction
,4 factors are the'same as for EAL lb.
Given release rate is based
- c -
on the WRGN monitor.
EALllj Noble Gas Release Rate s
(;
NUREG 0654 examplet AL $15 Supporting datat Calculated for the same dose rate limits as EAL 11.
All other assumptions, correction f actors and monitor channel are the same as EAL Id.
I EALilk. Whole Body Dose Projec'tions EUREG 0654 examples GE lla (gradation}, SE 813a Sunnortina datat Since the State of Illinois evacuates based on a 1 rem dose projection, and since evacuation should not be required except E
in General Emergency, a 1 rem dose projection is established as the General Emergency criteria. Site Emergency and Alert are arbitrarily established at one half and one fourth of this value, respectively.
Control Room personnel are not espected to classify based on this EAL.
Dose projections and classification are provided to i
the Control Room by the A-Model if available. If the A-Model is not available, Control Room personnel are not espected to perform dose projections.
The words "for actual or imminent releases" were inserted to
)
indicate that classification based on this criteria would not occur if there is no motive force for a release (i.e., there is activity in the containment, but containment isolation is complete and containment pressure is significantly lower then design).
. /~'s
~ (g
. APPROVED
,9'
~
OCT 171989 aj (0517A/0029A/051389)
+
. -... - -.... ~...
-.. -.. -.. - -. ~.. -,. -...... _,.. -.
-w-,
s BET 210-Al Revision 2 t.
.O
}
BYR(El EMERGENCY ACTION LEVEL (EAL) PRILOSOPHY condition 1.
Radioactive Effluent Release (Cont'd)
EAL411 rield Measurements s.,
MumEG 0654 amamples GE $1b (gradation), 85 013b sa--artian datai This EAL is worded such that if field tomme are needed to assess the magnitude of a confirmed release or its impact on the environment, an Alert would be declared. An alert As not meant to be declared if a field team is dispatched as a precautionary measure when no release is espected such as lifting of the steam generator PORV's without
,1 s'
confirmed tuba rupture. Field teams are not available from the plant staff during off hours. Field team operation 6 require the TSC to be manned. Augmentation by off duty personnel is required during off hours.
The words "as the result of releases from the site" were inserted to distinguish messurements that may be due to the presence of unosplained, 11:ed radioactive materials.
EALilm Liquid Release ***
sunnartina datat This emergency action level is based on Table 5.1-1, amorgency Action Levels for Radioactivity in Liquid Ef fluents, of the Generating Stations Bmergency Plan.
EALila Liquid Release Supporting datan j
This emergency action level is based on Table 5.1-1, 1
Amorgency Action Levels for Radioactivity in Liquid Effluents, of the Generating Stations Bmergency Plan.
j j
eat.1.
tiquid Reiease...
r Engpgrtina datat I
This emergency action level is based on Table 5.1-1, Bmergency Action Levels for Radioactivity in Liquid i
Effluents, of the Generating Stations Emergency Plan.
.b/
APPROVED OCT 171989 II. C). $I. Pl.
(0517A/0029A/051389) m
i REP 210-Al Revision 2 BYRCM B48RGENCY ACTION LEVEL (EAL) PHILOSOPNY Condition 1.
Radioactive Effluent Release (Cont'd)
FALily Liquid Release surpartina anta This emergency action level is based on Table 5.1-1, amergency Action Levels for Radioactivity in Liquid Effluents, of the Generating Stations bmergency Plan.
Values have been converted f rom uCi/ml. to uC1/g. to coincide with Tech. Spec. values and chemistry procedures which assume a 11guld at STP with density of Ig/cc.
EAllig A-Model Site bmergency Rupportlan dataL This EAL is based on output from the A-Model when an actual release is in progress.
EALllr Noble Oas Release Rate munna 06E4====rla SE013 1mpportina anta Release rata is calculated in such a way that release of normal operation aim averaged for 2 minutes
- will not onceed dose rate or 500 mrom/hr at 400 meters downwind distance, based on the worst case meteorology (stability class r, wind speed 1 m/sec), ground level release. Noble gas mis is defined in EAT. Ib.
This release rate is determinto based on the WRGM monitor reading.
EAL41s Noble Gas Release Rate g'712G 06E4 amm=ple: SE $13 Egggertina datan The basis for this EAL is the same as Ir.
Encept the release rate is average over 30 minutes
- and dose rate is not to onceed 50 mrom/hr.
APPROVED CNDI 171989 II. C). SI. f%.
~~
(0$17A/0029A/051389)
I BEP 210-Al Revision 2 i
'{
SYR(36 EMERGENCY ACTICEI LEVEL (EAL) PHILOSOPHY Condition 1.
Radioactive Effluent Release (Cont'd) 1
.s, EALilt Noble Gas Release Rate l'
MUREG QASA maamples SE $13 Eury rtina Agtgt i
Classification release rate is calculated in such a way that release of any assumed accident noble gas mis at time 1
)
0 to 24 hrs. Post shutdown and averaged over period ot minutes
- will not escoed a dose rate of $00 mrom/hr at 400 meters.** All other assumptions, correction factors acd monitor channel are as in EAL lir.
l
- Based on the best instantaneous monitor reading available.
l
EAL61u Noble Gas Release Rate i
MUSEG 0654.saanglet SE 013 i
Supporting datat I
The release rate is based on the same mis as in EAL lit.
(
Other EALs are as in EALilu.
L EAttly Whole Body Dose Projections gymna 0854 an==rlag SE 013a l
ARRygrtlan datan Since the State of Illinois evacuates based on a 1 rem dose projection and since evacuation should not be required escept in General Bmergency, a 1 rom dose projection is established as the General Emergency criteria. Site Emergency is arbitrarily established at one half the General Emergency value. This value correlates to a 50 mr/hr dose rate at the site boundary for ten hours or 250 mr/hr for two hours. Normal default for release duration is two hours.
Control Room personnel are not espected to classify based l
on this EAL.
Dose projections and classification are 4
provided to the Control Room by the A-Model if available.
I If the A-Model is not available, Control Room rersonnel are not espected to perform dose projections.
F The words "for actual or imminent releases" were inserted C3 to indicate that classification based on this criteria UI GC 3'
would not occur if there is no motive force for a release gj p,
(
(i.e., there is activity in the containment, but j
l containment isolation is complete and containment pressure g,
p.
is significantly lower than design).
g, gg 03 4
-7 (0517A/0029A/051389)
.1
+-
BEP 210-Al l
Revision 2 1
,~
'i BYRQt DIERGENCY ACTTCW LEVEL (EAL) PHILOSOPHY i
Condition 1.
Radioactive Effluent Release (Cont'd)
)
i EALG tw Thyroid Dose Projections 3
i NUREG 0654 amamplet SE 013a k,
Eupportina datat l
C As stated in NURBO 0737, Page ll, F.1-7, lodine gaseous effluent monitors for t.he accident condition are not considered to be practical at this time and that sampling of radiolodines by absorption on charcoal media followed t
by laboratory analysis is acceptable. Laboratory analysis
{
As not practical for instantaneous EA', classification.
In addition, espected post accident source terms would be j
dominated by noble gases.
Nowever, EALs related to thyroid dose projections may be useful to TSC, CCC and EOF personnel. Control Room personnel do not have the espertise to develop dose projections, nor are they espected to classify based on this EAL.
The value chosen is five times the W.B. dose projectione
[
\\O The words "for actual or imminent releases" were inserted to indicate that classification based on t.his criteria would not occur if there is no motive force for a release (i.e., there is activity in the containment, but containment isolation is complete and containment pressure is significantly lower than design).
j EALilm Field Measurements NUEEG 0654 an =yle SE 013a and 413b.
juggortina datat The word "as the result of releases from the site" were inserted to distinguish measurements that may be due to the presence of unexplained, fised radioactive materials.
The words " confirmed" was inserted to indicate that such reading has been verified with more than one instrument, or verified by more than one field team.
EAL41y Liquid Release Kupportina datan This emergency action level is based on Table 5.1 1, I
F.mergency Action Levels for Radioactivity in Liquid Effluents, of ti.e Generating Stations Emergency Plan.
APPROVED OCT 171989
~
- 8. O. S. R.
(0517A/0029A/051389) 1.
REP 210-Al Revision 2
/
\\
G SYRCEI ENERGENCY ACTICM LEVEL (EAL) PMILOSOPHY Condition 1.
Radioactive Effluent Release (Cont'd)
EAL41s Liguld Release
..,[ - ]
Bunnartina datan This emergency action level is based on Table 5.1-1, Emergency Action Levels for Radioactivity in Liguld Effluents, of the Generating stations Emergency Plan.
j EAL61sa A-Model General Emergency Sunnartina antat Th!'s EAL is based on output from the A-Model when an actual release 16 in progress.
)
EAL61sb Noble Gas Release Rate l
1 l
supportina datat Release rate is calculated in such a way that l
instantaneous release of normal operation mis will nct escoed dose rate of 1 rem /hr at 400 meters downwind i
distance based on the worst case meteorology (see EAL lt for all assumptions). This worst case meteorology is a conservative substitute for an actual meteorological condition specified in NUREG-0654. This release rate is based on the WRCM monitor reading.
EAL61sc Noble Gas Release Rate 3RREG 0654 an=7 3: Gell i
1 gunnartina datat t
l This emergency action level is based on the same mis as EALs Id and it.
All other conditions, assumptions, and monitor channel are as in EAL 1sc.
c l
l APPROVED OCT 171989 B.O.S.R.
(0517A/0029A/051389)
l i
l BEP 210-Al I-Revision 2 7
NYRON EMERGENCY ACYICBf LEVEL (EAL) PM11080PHY V
r Condition 1.
Radioactive Effluent Release (Cont'd)
EAL61sd Whole Body Does Projections NUREG 0654 esemple GE lia l
~
supporting datan Slace the State of Illinois evacuates based on a 1 rom i
dose projection and since evacuation should not be required oncept in General Emergency, a 1 rom dose j
projection is established as t.he General Emergene.v criteria.
)
Control Room personnel are not espected to classify based j
on this EAL. Dose projections and classification are provided to the Control Room by the A Model if available.
If the A Model is not available. Control Room personnel
{
are not espected to perform dose projections.
4 The words "for actual or imminent releases" were inserted to indicate that classification baseo on thic criteria t
would not occur if there is no motive force for a release (i.e., there is activity in the containment, but containment isolation is complete and containment pressure is significantly lower than design).
l 4
EAL61se Thyrold Dose Projections l
MUREG 0654 amamplat GE lle Susanttina datal As stated in NUREG 0737, page II.F.1-7, lodine gaseous effluent monitors for the accident condition are not considered to be practical at this time and that sampling of radiolodine by absorption on charcoal media followed by 7
laboratory analysis is acceptable. Laboratory analysis is not practical for instantaneous EAL classification.
In addition, espected post accident source terms would be dominated by noble gases.
}
However, EALs related to thytold dose projections may be useful to TSC, CCC and EOP personnel. Control Room personnel do not have the espertise to develop dose projections nor are they espected to classify based on this EAL.
The value chosen is five times the W.B. dose projection.
OW k
The words "for actual or insninent releases" were inserted to indicate that elsesification based on this criteria ON would not occur if there is no motive forc6 for a release E
O F
k d
j (i.e., there is activity in the containment, but v
containment isolation is complete and containment pressure
(
is significantly lower than design).
a
, (0517A/0029A/051389)
B8P 110-Al Revision 2 t
)
erRaw musmanner AcT1ou tryst (SAL) pu1Losorur i
N _/
Condition 1.
Radioactive Effluent Release (Cont'd)
- 1 EAL61st Field Measurements NUREg 0654 maamplet GE $1a supporting datan The words, "as the result of releases from the site" were i
inserted to distinguish measurements that may be due to the presence of unosplained, fised radioactive material.
The word " confirmed" was inserted to indicase that such reading has been verified with more than one instrument or I
verified by more than onn field team.
EAL61sg Liquid Release sumpertins datan This emergency action level is based on Table 5.1 1, bmergency Action Levels for Radioactivity in Liguld Effluents, of the Generating Stations Emergency Plan.
j EAL91sh Liquid Release supporting datat This river level chosen is the design elevation of the pump invert which supplies makeup to the essential service water cooling tower basins from the Rock River, (F8AR 2.4.11.6).
Escalation to the site emergency condition will be through EALS 92; and $6u.
i t
i i
I l
l
\\
s
{
l i
APPROVED O
xn vm B.O.S.R.- (0517A/0029A/051389)
-~
6
,e' I
BEP 210-Al Revision 2
!.d'
'+
NYRCN ENER0ENCY ACTION LEVEL (EAL) PHILOSOPNY Condition 2.
Loss of Fission Product Barriers i
EAL$2a Coolant Activity l
puREG 0654==- 7 a UE 43b 1
Eupporting datat l
This BAL is based on the Technical Specification operational limit for dost equivalent I-131.
The allowable operating conditions in T.S. 3.4.8 accommodate lodine spiking which may cicur following power changes.
4 EAL42b Incore Thermocouple Readings f
NUREG 0654 ammaple UE 03, UE $4 ggggartina datat l
Core esit thermocouple readings which are indicative of 0 to 50 percent cladding danage are utilis&d.
j EAL 02c Failed Fuel Monitor MUREG_0151 aanissles UE 43c Eunnortina datal l
[
}
The uC1/g increase in I-13"5 is equivalent to 0.1% fuel
\\/
failures as measured by the gross failed fuel monitor
-channel 2 (RE-PR006).
EAll2d Primary Containment Radiation Level
[
mumma 0654 an= rlas Gradation of Af.ll, AL66 and Atl12 Supporting datat l
The lower boundary for containment radiation level will be the alert setpoint for the containment Fuel Handling T
Incident ARN (100 R/hr.).
P l
i 1
l APPROVED OCT 171969 l
B.O.S.R.
32 (0517A/0029A/051389)
~_
BEP 210-Al Movision 2 i
5YR(BI ENERGIslcr ACT10st LEVEL (EAL) PHILOSOPNY Condition 2.
Loss of rission Product Barriers j
EAL42e Loss of Primary Containment Integrity i
a puREG 0614 amamplet UE $8 f
supporting datat l
The words "and power decrease for reactor shuteown has commenced" were added to clearly define when the Unusual l
Event is to be declared.
EALl2f Primary System Leakage
{
i EM&&G.9654 an===lat UE $$
t I
sunnartina data!
A11'wable' primary system leakage limits are specified in l
o Technical Specification'3.4.6.2. The time from identification of leakage until shutdown allows a time t
period during which calculations can be verified or j
leakage identified.
j EAL42g ECCS Initiation MUREG 0654 a===_=las UE $1 j
sunnartino datat f
The wording indicates that the signal should be judged
" valid" and "not spurious" for classification purposes.
t EALl2h Safety or Relief Valve Closure NUREG 0654 amample UE $6 l
i Supporting data This EAL also includes the PORV isolation valve as a means
{
to isolate the PORV.
i t
i l
i r
h APPROVED CH t 171989
. B.O.S.R.
(0517A/0029A/051389)
m l
j
)
i SEP 210-Al Revision 2 l
BYRCBI INERGENCY ACT!cel LEVEL (EAL) PN!!480PHY Condition 2.
Loss of Fission product Barriers (Cont'd)
I EtLl21 Loss of One Fission product Barrier i
MUREG 0654 maample Gradstion of GE $2 a
U' Ruanartina datat This RAL provides indications of a LOCA or an undesired release of coolant and/or fission products to the primary j
containment.
a)
The indication of cladding failure chossa is high j
coolant activity. Esemple 41b under Alert in NUREO 0654, indicates 300 uC1/cc equivalent of I-131.
Using NEDO.12215 this correlates to approsimately 6.5% fuel cladding failure. Classification under this criteria can only be accomplished after isotopic analysis has been performed.
b)
The indication of reactor coolant system failure is the omsrgency core cooling initiation signals. These signals are related by an "and" as a single signal can also be indicative of a loss of containment cooling. Setpoints represented are the pressuriser O'
low pressure safety injection setpoint and the HI-1 containment pressure safety injection setpoint.
c)
The indications of primary containment failure are the containment design parameters and the words "unisolable breech of containment." An unisolable breach of containment refers to a loss of primary containment integrity as required by Technical Specification 3.6.1.1.
Containment design paremeters are referenced in the Technical Specifications section 5.2.2.
EALt2)
Incore Thermocouple Readings Egga 0654 emanals: AL ll Aupputing datat
~
This emergency action level used core emit thermocouple i.'
readings that are indicative of 50 to 100 percent cladding damage.
APPROVED EAL42k Failed Fuel Monitor 00i 1 7 1989 E REG 0654 eKamples AL lic auppa ting datat B. O. S. R.
The uC1/g lacrease in I-135 is equivalent to 1% failed fuel as measured by the gross failed fuel monitor channel 2 (RE-PR006).
-14 (0517A/0029A/051389)
i 4
s-
?
i SEP 210-A1 j
Revision 2
]
I
(
?
()
WYRON ENERGENCY ACTION LEVEL (EAL) PHILOSOPHY Condition 2.
Loss of Fission Product Barriers (Cont'd)
EAL421 Primary Containment Radiation Level MUREG 0654..amample AL ll, AL $6, AL 612.
EALl2m Primary System Leakage
)
MUREG 0654==- rla AL $5
)
EAL92n Primary System Leakage I
MUREG 0654 ammaple: AL 02, AL $3, AL $5.
j i
EAL920 Loss of Two Fission Product Barriers
{
MURE0 0654 amampige Gradation of GE $2.
supportina datan l
This EAL provides indications of a LOCA or an undesired release of coolant and/or fission products to the primary containment.
(See EAL 021 for setpoint references.)
EAL42p Incore Thermocouple Readings
\\\\
MUREQ 0654 ammaple: SE $2 sunnartina antan This emergency action level uses core esit thermocouple readings indicative of fuel Pellet over tosperature and/or fuel melt and the ability to cool the core per SFR C-1.
i If adequate cooling can not be provided (i.e., temperature is still increasing?, a Genern1 Emergency should be declared.
EALl2q Primary Containment Radiation Level MUREG 0654 amamples Gradation of SE $2, SE 010 inaentting_datat i
As long as containment failure remains unlikely, there is no primary containment activity which will cause escalation to General Emergency.
EAL42r Primary System Leakage NUREG 0654 emmania: SE $1, SE $3 APPROVED 001 1 7 1989
- 5.O.S.R.
(0517A/0029A/051389)
i
,~
BEP 210-Al 4-Revision 2 j
u -.
' ;i r
BYRON ENERGENCY ACTION LEVEL (EAL) PHILOSOPHY l
Condition 2.
Loss of Fission Product Barriers (Cont'd)
EALl2s Loss of Two Fission Product Barriers With Probable Loss Of The Third j
.. +
NURRG Q6he an==alog GE $2 Egyportime antan This EAL provides indications of a LOCA or an undesired
[
release of coolant and/or fission products to the primary j
containment. (See EAL $21 for setpoint references.)
" Probable", as defined by the GSEP manual, refers to a condition supported by evidence strong enough to establish f
presumption but not proof. It represents an event that is likely to occur with a probability of greater than or equal to 50%.
EALl2t Imminent Core Melt i
NUREG 0654 amample s GE $4
[
Sunnortina datan f
This emergency action level uses core exit thermocouple
\\
readings and ability to provide core coollag per BFR.C.1 i
to pr, ject imminent core molt. The core thermocouple l
readings and percent hydrogen adopted by this EAL are Indicative of fuel pellet over temperature and fuel melt if maintained for a period of time.
i f
f k
APPROVED OCT 171989 (0517A/0029A/051389)
EB. C). fi. Ft.
1 l
)
BIP 210-Al J.
l' Revision 2
/
BYR(Bt EMERGENCY ACTION LEVEL (EAL) PHILOSOPHY Condition 2.
Loss of Flasion Product Barriers (Cont'd) l*
EALl2u Primary Containment Radiation Level With Probable Loss of l**.
Containment Integrity MUREG 0654 amamples GE $1b, GE 42 f
Rumpartina datat j
l If primary containment activity is greater than or equal 3
to 2 10 R/hr and primary containment integrity is intact and is espected to remain intact, then the classification j
remains Site Emergency.
j i
If primary containment activity is less than 2x10 R/hr I
3 and primary containment integrity is espected to be lost, 1
the classification remains at Site Emergency. It is only
)
when primary containment radiation is greater than or 3
equal to 2x10 R/hr and when loss of containment j
l Integrity is probable that a General.amorgency would be j
declared.
" Probable", as defined by the GSEP manual, refers to a condition supported by evidence strong enough to establish i
presumption but not proof. It represents an event that is likely to occur with a probability of greater than or l
equal to 50%.
EAL42v General Emergency Class Description NUREG 0654 emmaples GE l4 Supporting datat For definition of " probable", refer to EAL $2u.
" Imminent", as defined by the GSEP manual in Table 6.3-1 Footnote 8, signifies an event that will occur in less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with a projected probability of 100%.
1 1
4 APPROVED L
OCT 171969 I
(0517A/0029A/051389)
IB. C). S.1%.
ij BZP 210.Al Revision 2
]
RYRCBI EMBRGEIICY ACTIGt LEVEL (EAL) PHILOSOPHY Condition 3.
System Halfunctions EALl3a Technical specification Requiring Shutdown
]
MUREG 0654 amample UE $9, UE $11, UE 015 nunnartina datan i
The EAL is provided to allow for equipment degradation
~
combinations which could place a unit in jeopardy. Rather than listing all possible combinations of equipment i
failures, reference is made to esisting Technical 1
Specifications.
]
The wordc "and power decrease for reactor shutdown has l
commenced" were added to clearly define when the Unusub Event is to be declared.
1 r
EALl3b Loss of Instrumentation For Classification Purposes NUREG 0654 amample UE $3a, UE 011 1
Runnortina datat No attempt to detail the specific instruments that are critical to accident classification or to offsite dose i
assesament has been made. As an esemple, as long as manual procedures for o'.'f site dose assessment and the necessary input parameters are available, this event need not be declared.
EALl3c Loss of Communication Capability MUREG 0654 amample UE $11 i
l Supporting datat
[
The losses identified by this EAL are as follows:
i l _
a.
Loss of the Nuclear Accident Reporting System and Commercial Lines i
OR b.
Loss of the National Narning System and Commercial lines OR i
c.
Loss of the Emergency Notification System, 7
Health Physics Network and Conenercial lines.
~
l This is deemed as a significant loss of communication
.d C8Pability.
OCT 171989
,1,,
(0517A/0029A/051389)
- 8. O. S. R.
-~.
....t j
B2P 210-A1 Revision 2
- . [
BYRON 34tRGENCY ACTION LEVEL (EAL) PHILOSOPHY
, \\.
I Condition 3.
System Malfunctions (Cont'd)
EAL43d Loss of Station Aus111ery Transformer and Unit Ausillary Transformer.
?-
NUREG 0654 a=--la e UE 47 i
t l
Runnartina datan For purposes of the emergency action level, credit is not j
taken for unit tie breakers. Therefore, declaration of an Unusual Event cannot be evolded if the only source of l
offsite power is through the unit tie breakers.
The words "with the Unit not in Cold Shutdown or Refuel" i
emphasise the fact that such a loss of power should not constitute an Unusual Event as long as the Diesel i
Generators are available and the Unit is not at power.
C eat 03e Loss of All Diesel Generators MUREG 0654 amample UE $7 SuBPartl== datal Loss of all Diesel Generators associated with a unit refers to only the normal diesel supplies.
O*
It does not refer to Diesel-Generators related administratively through Technical Specifications. For esemple, the loss of 1A and 18 Diesel Generators is an l
Unusual Event for Unit 1.
Although the 2A Diesel l
Generator is assocle.ted administratively to Unit 1 by j
Tech. Specs., it does not apply to conditions for Unusual Event declaration on Unit 1.
[
I The words "with the Unit not in Mode 5 or 6" emphasise the j
fact that such a loss of power should not constitute a j
l 4
Unusual Event as long as the Unit Ausilary Transformer or associated Station Ausillary Transformer is available and I
the unit is not at power.
f j
i l
f l,
i i
i i
(
APPROVED OCT 171969 (0517A/0029A/051389) w.
c...-.,._..
,__._,..v-.--,.
.e l
BEP 210-Al i
1-Revision 2 i
/
BYRCBI EttERGENCY ACTICat LEVEL (EAL) PNILOSOPHY Condition 3.
System Malfunctions (Cont'd) s.
Loss of Ability To Reach Cold 8hutdown
{
EALl3f 3U110 casa== ;1a AL $10 Runnartina datat I
The use of the term "any function" la the NUREG could i
result in inappropriate G5tp activation and was therefore avoided. For esemple, t.he 3oss of a single system would not generate an Alert declaration if numerous methods esist for achieving Cald Shutdown.
i Note that the wording chosen for the EAL doog not require that "all rods be inserted" or that " shutdown margins be met" but rather that the reactor be "subcritical".
Suberitically is a condition that can be indicated by rod insertion and/or decaying power level. This condition
't also assumes that only one means of maintaining l
temperature X 2000r esists. In considering the number of ways to keep coolant X 2000F, all normal and alternate means must be considered. If two means or systems esist, an Alert need not be declared.
The words "escept during controlled, planned evolutions" O,
were inserted to avoid declaration if significant proplanning and specific controls have been established by i
Station Management before knowingly entering this condition.
EALl3g Failure of Automatic Reactor Trip MUERG.0654 anaegist AL lli l
Kupporting datat t
This EAL contains wording with respect to having reached a
" Limiting Safety System Setting" as specified in the Technical Specifications.
If also supposes that a manual trip was successful.
i EALl3h Technical Specification Safety Limit t
Supportina datat Although not specifically addressed in NUREO 0654.
~
violation of a Technical Specification Safety Limit constitutes a degradation in the level.of safety of the l
Plant consistent with the Alert class description provided r
in the NURto.
APPROVED OCT 171969 (0517 A/0029M051389 )
- 5. O. S. R.
F
--...-..,,m.
,_-_,--.-v.
_,e.
- i 9
I l
BEP 210-Al Revision 2 j
3-~l j
WYRGl ENERGENCY ACTION LEVEL (EAL) PMILOSOTHY j
s/
j s
Condition 3.
Systow Malfunctions (Cont'd) t EAL931 Loss of Annuciators
[
?
{'
NU110 0854 amample: AL 014 l
6 supporting datan i
The term " unplanned" was added to indicate that there may j
be planned losses of power to the annunciators. For l
esemple, D.C. ground search procedures may result in i
temporary loss of power to annunciators. The listing of
[
panels specifies certain annunciator panels to be i
critical. The NRC has indicated that this condition f
should be an "and" condition. Loss of power to all of the
[
indicated panels is required before declaration is made.
.i During the period when such a loss has occurred, j
additional personnel should be stationed at those panels
}
with the sole responsibility to monitor and respond to conditions as appropriate. Specific measures to avoid i
transients should be identified.
{
EAL43)
Loss of Ability to Reach Not shutdown l
/~
NUREG 0654 am-rlag SE $6
(
ggggartina datat The use of the term "any system" in the NUREG could result in inappropriate G8tP activation and was therefore avoided. For esemple, the loss of a single system would not generate a Site Emergency declaration if numerous methods esist for achieving a Hot Shutdown condition.
4 This condition essumes suberiticality.
In considering the number of ways to maintain Hot Shutdown, all normal and alternate means must be considered. If two means or systems esist, a Site Rmergency need not be declared.
~
The words "escept during controlled, planned evolutions" were inserted to avoid declaration if significant
{
proplanning and specific controls have been established by i
Station Management before knowingly entering this condition.
j EAL43k Failure of Automatic and Manual Reactor Trip NURga ossa an==rla St 69 1HRPortina datat This EAL contains wording with respect to having reached a
" Limiting Safety System Setting" as specified in the
(
Technical Specifications. The additional wording ALPPFt()\\fECD
\\,d clarifles when the SCRAM should have occurred.
OCT 171989
- ' I' !I' (0517A/0029A/051389)
BEP 210-Al Revision 2
,.m
)
NYRGE MERGENCY ACTION LEVEL (EAL) pMILOSOPHY
]
I Condition 1.
System Malfunctions (cont'd) 1 i
Estell was of DC co.e, MilRAG 0454 a=
1
~.
jt otioc r t ima _datat
{
The NUREG addresses an Alert condition for a loss of all
}
DC power and upgrades to Site Emergency if loss is for greater than 15 minutes. The 15 minutes is of no 5
consequence. 'the time to restore power once lost and to j
complete notification is espected to take more t.han 15 minutes. The event is of such magnitude that offsite i
assistance would be required. Therefore, the 15 minute time frame and the Alert EAL has been dropped. This EAL is more conservative than the NUREG without being more restrictive. Such a massive degradation of power sources wou13 more appropriately justify a Site Emergency declaration without an interim Alert declaration.
EALl3m Loss of All AC Power MUREG 0654 an=$3s AL $7, SE $6 gggggrtInn datan The NUREG addresses an Alert condition for a loss of all AC power and upgrades to Site Emergency if loss is l'or greater than 15 minutes. The 15 minutes is of no consequence.. The time to restore power once lost and to complete notification is espected to take more than 15 minutes. The event is of such magnitude that offsite assistance would be required. Therefore, the 15 minute time frame and the Alert EAL bas been dropped. Such a massive degradation of power sources more appropriately justifies a Site Emergency. This EAL la more conservative than the NUREG without being tr. ore restrictive. Credit is not taken for the unit cross ties. This EAL is based on the loss of all Diesel Generaitors associated with a unit in conjunction vit.h loss of the Station Ausiliary Transformer and of the Unit Aus111ary Transformer.
EALl3n Loss of Feedwater and Auxiliary Feedwater MUREG.0654 ammaple:
SE $2 Supporting antatt This emergency action level is based upon a loss of Feedwater Residual Heat Removal Systems for core cooling.
If this condition esists for greater than 45 minutes declaration of General Emergency is warranted.
(Refer to EALl3g )
l k
APPROVED OCT 171969 (0517A/0029A/051389) 5.O.S.R.
a A
BEP 210-Al Revision 2 BYRCEI StEk0ENCY ACTION LEVEL (EAL) PHILOSOPHY Condition 3.
System Malfunctions (cont'd) i EALl30 General Emergency Class Description j
(
MUREG.0654 amamplaa GB $4
?
M Bupporting datat
[
The term " probable" was substituted for the term i
" potential" to be consistent with GREP and with other EALs.
(Refer to EAtt 2u tad 2v for definitions of
(
" probable" and "im inent".)
,i t
I EALl3p Inuninent Core Nolt i
MUREG 0654 example GE $4 I
Eupporting datat l
This emergency action level uses core omit thermocouple readings and ability to provide core cooling per BPR-C-1 l
to project immineut core molt. The core thermocouple readings adopted by this RAL are indicative of fuel pellet over temperature and fuel melt if maintained for a period of time.
i r
EALl3g Loss of Feedwater and Aus111ary Feedwater
'. \\
NUREG 0654 an 7 ag GE lsb l
1' I
ys f
I i
O V
APPROVED p
l oci ) 71989
~ *~
(os17A/oo29A/os13es)
- 5. O. S. R.
)
Ti,
i C
7
)
i BIP 210-Al i
Revision 2
{
im l
BYRCBI ENERGENCY ACTION LEVEL (EAL) PHILOSOPNY
]
CONDITICM 4.
SECONDARY SYSTEN MALFUNCTIONS EALtda Main Steenline Break j
o IEUREG 0654 maample UE $17 EALlob Primary to Secondary Leakeage
[
MUREG 06E4 an =rles UE $5 f
Eunnartina datat This leakage rate is Specified in Technical Specification 3.4.6.2 EALl4c Decreased Feedwatsr Temperature MUREG 0654.amample UE $4 gaggprtina datu l
The te*Perature chosen for this EAL is based on the steam generator RTypy limitations sufficient to prevent i
Drittle fracture (Technical Specification 3.7.2 Bases).
t EALl46 Main Steamline Break or Feedline Break
\\
MURE0 0654 an== ales AL 04 l
EAtlee Steam Generator Tube Rupture
[
l MUREG 0654.amample AL $3, AL $5 i
EALl4f Main Steamline Break or Feedline Break NUREG 0654.amample SE $5
{
Eunnartina date The core emit thermocouple reading is indicative of some cladding damage.
i EALl49 Steam Generator Tube Rupture
~
puREG 0654 amm=nia SE $1, SE $3 EALl4h Loss of Feedwater and Ausiliary Teodwater MUREG 0654 an==nige SE $2 Supporting datat This emergency action level is based upon a loss of i
j reedwater and residual heat removal for core cooling.
If i
t.his condition esist for greater than 45 minutes l (
declaration of General Emergency is warranted.
(Refer to I
EAL an.)
APPROVED i.
OCT 171969 24-(0517A/0029A/051389)
B.O.S.R.
_m.. -.. -.. - -, -, -
-_.--.,----,,,___,--,,s.~.w._
,-..._.-----.-,....--.,,-wr,.-,,,.-----
. e BEP 210-Al Revision 2
(
BYRW EMERGENCY ACTICH LEVEL (EAL) PHILOSOPHY i
CONDITION 4.
SECONDARY SYSTEM MALTUNCTIONS 2
EALl41 General Emergency Class Description
)
MUREG 0654 amamplet GE $4
.* 1 I
Supporting datat j
The term " probable" was substituted for the term i
" potential" to be consistent with GSEP and with other EALs.
(Refer to EAL4 2u and 2v for definitions of " probable" and "lumninent".)
EALl4j Loss of Feedwater and Auxiliary Teodwater i
4 ElREG 0654 aumles GE 45b
.[
[
i t
i O
\\
APPROVED OCT 171989 25-(0517A/0029A/051389)
B.O.G.R.
-,m, v.
e--,
,w-,o
-,--w
---.--.s.,,,..-,--.-,w---,--
e
.---,m-n-,
BIP 210-Al (c
Revision 2 BYRCM EMERGENCY ACTION LEVEL (EAL) PHILOSOPHY condition 5.
Fuel Mandling Accident j
EAL45a Damage to Irradiated Fuel and Containment vent System Diverted MUREG 0654 an==ple AL 06, AL $2
- .y EALl5b Damage to Irradiated Fuel and Fuel Handling Buildia.g
,s'
'Enhaust Diverted MUREG 0654.examp!e: AL $6, AL 012 Eggggrtina data 1 Fuel pool enhaust monitors were nnt chosen to initiate this 4
i EAL since their isolation signal is set relatively low and would essentially halt the tracking of higher readings.
In i
addition, the eshaust monitors may not provide a sufficiently
)
high reading in the case of an esposed spent fuel element.
.s The 100 mR/hr on the Fuel Mand 1Ang Building ARN was chosen 1
based upon the high alarm setpoint for this ARN.
Confirmation of the reading was specified to avoid classification based on erroneous failure of the ARM, out of service conditions or planned evolutions during which the detector is removed from service (planned movement of highly radioactive material from containment during an outage.)
EAL45c Fuel Pool Level MUREG 0654 an =ple SE 010 i
EAL65d Donage to Irradiated Fuel and Containment Vent System Charcoal Depleted or Isoperable.
+
MUREG 0614====p13:
SE 010
+
+
5 l
l' APPROVED OCT 171989
- 5. O. S. R.
(0517A/0029A/051389) 1 1
i t
i BEP 210-Al i
Revision 2 i
t BYROM EMERGENCY ACTICat LEVEL (EAL) PHILOSOPNY Condition 5.
Fuel Mandling Accident l
.t i
~
N EAL45e Damage,to Irradiated ruel and ruel Handling Building
- d Eshaust Charcoal Depleted or Inoperable.
,_s supaa ossa==- rlas 88 410 junnarting datar
{
Fuel pool exhaust monitors were not chosen to initiate this EAL since their isolation signal is set relatively low and would essentially helt the tracking of higher readings.
In addition, the ashaust monitors would not
'J provide a sufficiently high reading in the case of an esposed spent fuel element.
The 100 mR/hr on the Fuel Mand 11mg Building ARM was chosen based upon the alarm setpoint for this ARN.
Confirmation of the reading was specified to avoid classification based on erroneous failure of the ARN, out of service conditions or planned evolutions during which the detector is removed from service (planned movement of highly radioactive material from containment during an outage.)
EAL95f Fuel Poul Level O
MUREG 065a an== ries SE 010 i
t l
3 l
i I
e 1,.;
I
(
APPROVED l
~
oci 171969 1 (0517A/0029A/051389)
II. C). S lI.
. ~
t e,
t SEP 210-Al i
Revision 2
{
(
BYRON EMERGENCY ACTION LEVEL (EAL) PHILOSOPHY Condition 6.
Natural and Destructive Phenomena EAL46a Technical Specification Requiring Shutdown MUREG 0654 ammaple UE $9, UB til, UE $15 Runnertina dat.,
i The EAL is provided to allow for equipment degradations the combinations of which could place a unit in jeopardy.
Rather than listing all possible combinations of equipment failures, and thereby establish a " pseudo", technical specification, reference is made to esisting Technical Specifications.
The words "and power decrease for reactor shutdown has commenced" were added to clearly define when the Unusual Event is to be declared.
EAL66b Offsite Assistance Euroortina datat Although not specifically addressed in NUREG 0654, this emergency action level addresses several esemples listed in the NUREG. This EAL provides a symptomatic approach N
based on damage to the facility and/or equipment. This approach allows other initiating events to be covered by the same EAL, for esemple, esplosion, fire, flood, earthquake, etc. The statement "to prevent further degradation..." was used to segregate events which might i
require of f-site assistance for " clean up" measures but which would not constitute an Unusual Event.
EALG6c Fire l'
MunEG 0654 anameles UE 010 EALl6d Tornado i,,
l MUREG 0654. example: UE $13c l-(
EALl6e High Lake or River Level
{
l NUREG 0654 ammanlas UE 013b 33gportino datat For this condition, the Technical Specification 3.7.5 p
value is utilised.
l i
APPROVED OCT 171989,
(0517A/0029A/051389)
B. O. S. R.
9 4
I REP 210-Al Revision 2 i
. t 1
BYRON ENERGENCY ACTION LEVEL (EAL) PRILOSOPNY l
I \\~ /
Condition 6.
Natural and Destructive Phenomena (Cont'd) i EALl6f Low Lake or River Level
'i.
i EUREG 0654 an==rles UE $13b l
- g..a Supporting datas t
The Technical Specification 3.7.5 value is utilised.
l
~'
l EALltg Aircraft Crash Onsite t
EUREG 0654 an==rles UE $14a EALl6h Earthquake j
.e I
MUREG 0854-thhEpit UK ll3e f3 Supporting datan The term "in house" was added to alleviate the problem of i
free field monitors which are often activated by trains or thunder.
r Notification of earthquake by outside cognisant sources provides a mechanism to classify for earthquake conditions even if the "in house" earthquake monitors are k
out-of-service. Cognisant sources include, but are not' _
limited to: Television and radio station broadcasts; national weather bureau information; local or national government agency notifications national earthquake center i
and/or university centers.
j EALl61 Emplosion l
gyREG 0854 amample UE 014c i
i l
l..!
i l
N
\\
APPROVED
~
OCT 171989 (0517A/0029A/051389)
II. C). S. II.
,,n--
c-,, -, - -,..,,.
., - ~ ~.,,,,
}
- s t
BEP 210-Al i
Revision 2 I
j
.i BYROM EMERGENCY ACTION LEVEL (EAL) PHILOSOPHY Condition 6.
Natural and Destructive Phenomena (Cont'd)
EAL46)
Z,oss of Ability To Reach Cold Shutdown f
.+
.g i
NUREG 0654 amamples AL $10 t
i Rupporting data The use of the term "gny function" in the NUREG could i
result ir inappropriate G8EP activation and was therefore t
avoided. For esemple, the loss of a single system would l
not generate an Alert declaration if numerous met. hods esist for achieving Cold Shutdown.
Note that the wording chosen for the EAL does not require that "all rods be inserted" or that " shutdown margins be met" but rather that the reactor be "subcritical".
I Subcritically is a condition that can be indicated by rod lasertion and/or decaying power level. This condition a
also assumes that only one means of maintaining temperature X 2000F esists.
In considering the number of ways to keep coolant X 2000r, all normal and i
alternate means must be considered.
If two means or i
systems esist, an Alert need not be declared.
I The words "escept during controlled planned evolutions" f
s were inserted to avoid declaration if significant
.i preplanning and specific controls have been established by i
Station Management before knowingly entering this condition.
l EALl6k safety Systems i
MUREG 0654 emmania: AL $13 l
I L
Eupporting datan The wording of this EAL requires some indication that the system may not perform its required function. It also l
applies this criteria to damage caused by emplosion, tornado, earthquake, etc.
l t
EALl61 Control Room Evar:uation t
Wi/ REG b654 emannig AL $2o l
SMPPS111nqJ1&L&1 The words "within 30 minutes" were added to provide a definitive distinction between Alert and Site Emergency while allowing a reasonable time period to gain control.
L APPROVED t
i i
OCT 171989 B. O. S. R.
l' (0517A/0029A/051389) l
SEP 210-Al Revision 2 r
$ < y'"%y
{
BYRCEt ENERGENCY ACTICBI LEVEL (EAL) PHILOSOPHY Condition 6.
Natural and Destructive Phenomena (Cont'd)
EALl6m Sustained Winds
. ^
NUREG 0654 azample: AL $17d sunnartina datan
~
~
Sustained winds are winds which esist for 15 minutes or i
more. The wind speed chosen should be approalmately 90%
of the design basis wind speed for the containment.
(FSAR 2.3.1.2.2)
EALl6n tornado NUREG 0654 azample: AL 817c Rupportina datat This EAL addresses vital areas of the plant.
EALl60 High Lake or River Level l
NUREG 0654 example: AL 017b L apport t ua data 1p The lake / river level chosJn should be the same as the
' ()
level projected in EALl6e for the Unusual Event. This EAL is declared when the projection described in EAtl6e has been reached.
EALl6p' Low Lake or River Level 3,,
i NUREG 06B4 exampig AL $17b Eupportina datat The conditions specified are the same as those projected in EAL 66f for the Unusual Event. This EAL is declared when the projection described in EAL 66f has been reached with specified equipment conditions not met. The river level referenced is the design elevation of the pump invert which supplies makeup to the essential service water cooling tower basins from the Rock River.
(FSAR
+
2.4.11.6) Escalation to Site Emergency condition will be through EALs $33 and $6u.
EALl6g Aircraft Crash Inside Protected Area NUREG 0654 amannle AL llBa
[
/
(
APPROVED Oct 171989
> (0517A/0029A/051389)
II. CI. SI. II.
w-e e-e, e
--e n--mee
-e-,
---,---~-,.-,-,-v e--,-----,-
e v,---.-
---,.-,,e
~-,,,rve--v.c-m,--
-e BEP 210-A1 Revision 2 BYR(El ENERGENCY ACTICES LEVEL (EAL) PHILOSOPHY v
Condition 6.
Natural and Destructive Phenomena (Cont'd)
EAL46r Earthquake NUREG 0654 amample: AL $17a supporting datan The level selected is that of the Operating Basis Earthquake. The words "is confirmed" were added for stations which do not have direct readout instrumentation and to avoid declaration due to spurious actuations.
(r8AR 2.5.2.7)
^
Notification of earthquake by outside cognisant sources provides a mechanism to classify for earthquake conditions even if the "in house" earthquake monitors are out-of-service. Cognisant sources include, but are not limited to: Television and radio station broadcasts; national weather bureau information; local or national 9evernment agency notification; national earthquake center and/or university centers.
EALl6s Safety Limit f
Sunpartina datan 7s)
Although not sPecifically addressed in NUREG D654,
{
4 violation et a Technical Specification Safety Limit constitutes a degradation in the level of safety of the i
plant consistent with the Alert class description provided in the NUREG.
l EALl6t Turbine Failure
[
[
NUREG 0654 amample: AL $18e f
supportina datan I.
This EAL is word for word from the NUREG and, although concerns are covered by other EAL statements, is retained at the request of the NRC.
i 4 l $4
.c APPROVED 001 1 7 1989
' i. >
E (0517A/0029A/051389)
II. C). II. EI.
1 L
-. ~. ~, _ _. - _ _ _ _.. _. _ _ _ _.. _ _ _. _ _. _. _. _ _. _ _. _. _
'.s i.
.m
,i BZP 210-Al C
Revision 2 BYRCEI EMERGENCY ACTICBI LEVEL (EAL) PHILOSOPHY Condition 6.
Natural and Destructive Phenomena (Cont'd) y EALl6u Loss of Ability to Reach Hot Shutdown M. I NUREG 0654 emansple SE $8
%t AJ Sunnartina datat The wording of this (EAL) is an attempt to clarify the concern of NUREG 0654. The use of the term "any system" la the NUREG could result in inappropriate GSEP activation and was therefore avoided. For esemple, the loss of a single' system would not generate a Site Emergency y.j declaration if numerous methods exist for achieving a Hot
'7 Shutdown' condition.
This condition assumes suberaticality. In considering the nur.ber of ways to paintain Hot Shutdown, all normal and alternate means must be considered. If two means or
.l
,7
. systems exist, a Site Emergency 2.!ed not be declared.
The words "escept during controlled, planned evolutions" were inserted to avoid declaration if significant proplanning and specific controls have been established by Station Manage.eent before knowingly entering this condition.
\\
EALl6v Control Room Evacuation NUREG 0654 example: SE $18 i
Eunnartina datan Stations with Remote Shutdown Panels may be able to meet the 15 minute requirement. However, stations with local f
contrci modifications may not meet the arbitrary 15 mint,tc.'. The words "within 30 minutes" were added to l
provide a definitive distinction between Alert and Site Emergency while allowing a reasonable time period to gain r
- control.
i n.
[. >
1-p L
I j'
..r, APPROVED 4, ',
1.
OCT 171989.
'-(0517A/0029A/051389)
B.O.S.R.
+
r,
6
~
}
-Q S
4 BZP 210-Al Revision 2 BYRCEt ENERGENCY ACTICEE LEVEL (EAL) PHILOSOPHY
\\/
Condition 6.
Natural and Destructive Phenomena (Cont'd) t EALl6w Sustained Winds 31R10 0654 ex pie: SE 115c j
Eupporting datat Sustained winds are winds which esist for 15 minutes or more. The wind speed chosen is the design basis wind speed for the containment;. The words "with a unit not in Cold shutdown or Refuel" were added to indicate that if units are in Cold Shutdown or Refuel, a Site Emergency need not be declared.
(FSAR 2.3.1.2.2)
EALl6x High River Level MUREG 0654 example SE 015b Runnartina datat This level corresponds to the probable maximum flood (FSAR l
Table 2.4 12).
EALl6y. Aircraft Crash Affecting Vital Areas
. j 1
r NUREG 0654 examples SE 016a l
J EALl6s Earthquake MUREG 0654 examples SE 015a Runnartina datan The level chosen should equate to the Safe Shutdown Earthquake. The words "with a unit not in Cold Shutdown 5
or Refuel" were added to indicate that if units are in i
Cold Shutdown or Refuel, a Site Emergency need not be 3
declared. (FSAR 2.5.2.6) i Notification of earthquake by outside cognizant sources l
l-provides a mechanism to classify for earthquake canditions l.
even if the "in house" earthquake monitors are out-of-service. Cognisant sources include, but are not limited to: Television and radio station broadcasts; national weather bureau informations local or national I
m+
government agency notifications national earthquake center and/or university centers.
J q
1 APPROVED I^
OCT 171989 (0517A/0029A/051389)
B. O. S. R.
1' 1
l'
,_..~ _. _
i
il
}i BZP 210-Al Revision 2
. jA BYRCBI ENERGENCY ACTION LEVEL (EAL) PHILOSOPHY
\\-
+
Condition 6.
Natural and Destructive Phenomena (Cont'd)
EALl6sa General Emergency Class Description MUREG 0654 maample GE $4 supporting datan
^
The term " probable" was substituted for the term
" potential" to be consistent with GSEP and with other EALs.
EALl6sb Inuninent Core Melt MUREG 0654 amample GE $4
.1 Supporting datan This emergency action level uses core exit thermocouple readings or percent hydrogen in conjunction with core uncovery to project inuninent core molt. The core thermocouple readings and percent hydrogen adopted by this EAL are indicative of fuel pellet over temperature and fuel melt.-
t
' '\\,
-~~
~ ~,..
s
'9 t
I t
APPROVED OCT 171969
,y_
(0517A/0029A/051389)
B. O. S. R.
'J t
e
,v.
ye-
,nr.
- =
..w-
--,-v--.-u.
m f
t BEP 210-Al
},,
Revision 2
'1 BYROM ENERGEllCY ACTION LEVEL (EAL) PHILOSOPHY Condition 7.
Hasardous, Toxic or riammable Materials EALl7a Life Threatening Levels Onsite MUREG 0654 amample UE lied e
w;
", J:
Rupportina datat The significant wording is " life threatening levels" and I
L
" confirmed". Placing specific limits for all the toxic, hasardous and flammable materials in the table would be difficult. However, to determine if the release of these
[
Pa materials'is life threatening may be easier to assess.
Unless personnel have been affected and until analysis 1
confirms the release and quantity of such materials, the k.,
GSEP condition need not be declared.
Flammable is defined as'any substance capable of
(
self-igniting at temperatures below 140 degrees F.
Toxic is any chemical known to cause and can reasonably be
~
anticipated to cause significant adverse human health effects.
EALl7b Plant Operation Affected n
NUREG 0654 example: UE fled
-( j Bupportinef datal, This particular EAL addresses releases that may occur l
offsite but which impact plant operation.
See EAL 67a for definitions of flenmable and toalc.
EALl7c Hasardous Material i,
i MUREG 0654 examnia: UE lied l
REB 2prtina datar This EAL addresses the State of Illinois Public Act 79-1442 Hamatdous Materials Regulation.
.s EALl7d Emplosion 1,
NUREG 0654 amamrdas UE 014c L
l-l:
l, i
h APPROVED
> 1. j OCT 171969 Y (0517A/0029A/051389)
B. O. S. R.
-- ~-.
s.-
8
-.c
.]
BEP 210-Al gf Revision 2.
BYROM ENERGENCY ACTION LEVEL (EAL) PHILOSOPHY I
- (
\\
Condition 7.
Hasardaus, Tonic or Flammable Materials i
EAL97e Life Threatening Levels Within Protected Area MUREG 0654 maanple: AL $18d 4-munportina datan
/
The significant wording is " life threatening levels" and
" confirmed within the protected area. Placing specific j
d limits for all the toxic, hasardous and flammable materials in the table would be difficult. However, to determine if the release of these materials is life threatenisg may be easier to assess. Unless personnel have been affected and until analysis confirms the release and quantity of such materials, the GSEP condition need J
m-not be declared. See EAL 47a for definitions of flammable and toxic.
l-d
^
EALl7f Control Room Evacuation
~
MUREG 0654 amapple: AL $2o
- Sunnartina da m j
l' E,
Toxic or flammable material entry into the Control Room is l;
foreseen as one possible cause for a Control Room evacuation.
The wordo "within 30 minutes" were added to provide a definitive distinction between Alert and Site Emergency while allowing a reasonable time period to gain control.
EALl7g Life Threatening Levels Within Vital Areas l
NURPG 0654 nu m le: SE 016c l
[
ggggottino datat, 3
L The significant wording is " life threetening levels" and
" confirmed within the vital area."
Placing specific lj limits for all the toxic, hasardous and flammable i
H-materials in the table would be difficult. However, to l
determine if the release of these materials is life l.
threatening may be easier to assess. Unless personnel I.
have been affected and until analysis confirms the release l*,.
and quantity of such materials, the GSEP condition need t
not be declared. See EAL 47a for definitions of flammable i
ll,
and toxic.
)
Is APPROVED L
OCT 171989 F (0517A/0029A/051389)
B. O. S. R.
I.
4 1,.
.., - - _ _ _ ~,
t BZP 210-Al 1;
Revision 2 p-~
BYR(BI ENERGENCY ACTICM LEVEL (EAL) PHILOSOPHY Condition 7.
Hasardous, Tomic or Finanable Materials (cont'd)
EALt7h Control Room Evacuation l
i MUREG 0654 amamples SE 018 Runnartina datan
.The words "within 30 minutes" were added to provide a definitive distinction between Alert and Site Rmergency-while allowing a reasonable time period to gain control.
Toxic or flammable material entry into the Control Room is foreseen as one possible cause for Control Room evacuation.
c.
l' l
1 l '.
~
l i
I l
s l
a
" 6' l
APPROVED OCT 171989 (0517A/0029A/051389)
IB.C).!i.Ft.
. ~.
a 4
BEP 210-Al Revision 2
- ,.f)
"_ ' t '}
BYRCBI EMERGENCY ACTION LEVEL (EAL) PHILOSOPHY I
Condition 8.
Security Threat EALl8a Attempt to Sabotage MUREG 0654 examplet.UE 012 Supportina datat This is adopted from the list of Security Plan Contingencies.
EALl8b Internal Disturbance MUREG 0654 example
'UE 012 I
Supnerting datat This is adopted f rom the list of Security Plan Contingencies..
EALl8c Bomb Device Discovered i
MUREG 0654 example UE 012 Bunnortina datat h
ThFs is adopted from the list of Security Plan
-Q Contingencies.
EALl86 Hostage l
4.
NUREG 0654 mmmenle: UE 012 i
Sunnortine datat This is adopted from the list of Security Plan l
Contingencies. A hostage situation, which does not disrupt normal operations, should not be declared as a GSEP event.
l EALl8e Civil Disturbance l
NUREG 0654 example: UE 012 Supportina datat This is adopted from the list of Security Plan L
Contingencies.
li-EALl8f Armed or Forced Protected Area Intrusion NUREG 0654 example: UE 012 Supportino datat This is adopted from the list of Security Plan Contingencies.
gV APPROVED L
OCT 171969 l' (0517A/0029A/051389)
B.O.S.R.
1 t
4 BZP 210-Al i
Revision 2 m
BYR(at EMERGENCY ACTION LEVEL (EAL) PHILOSOPHY Condition 8.
Security Threat EALl89 Unuaual Aircraft Activity r
MUREG 0654 example: UE $14a l
Egggertina datat Unusual aircraft is any aircreft which touches down or l
appears to be surveying the site without having received proper authorisation.
EALl8h Explosion t
NUREG 0654 example UE $14c EALl81 Ongoing Security Threat t
l, MUREG 0654 example: AL $16 EALl8j Security Threat That Generates An Unusual Event MUkEG 0654 example:
3 f
Eupportina datat
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This particular emergency action level is not required by j
NURAG 0654. However, some criteria for escalation was needed above and beyond that presented in EALl81.
~ Thio emergency action level provides guidance for an escalating security event. For example,'Af a bomb device were to explode, there is no EAL that requires escalation I
above Unusual Event. However, if as a result of the detonation, equipment degradation meets the criteria for an Unusual Event, escalation to an Alert would be required by this EAL.
EALl8k Armed or Forced Vital Area Intrusion NUREO 0654 examnle AL 816 Sunnortina datat This is adopted from the list of Sucurity Plan Contingencies EALl81 Imminent Loss of Physical Control of Facility HUBE.Q 0654 example: SE $14
'! D ls)
APPROVED OCT 171969 B.O.S.R.
(0517A/0029A/051389)
l
\\;
.. s.
I BIP 210-Al Revision 2 i
BYRON ENERGENCY ACTICW LEVEL (EAL) PHILOSOPHY l
' Condition 8.
Security Threat (Cont'd) j 4
i i,
l!"
[
EALl8m Loss of Control of Vital Areas
\\
t' MUREG 0654 example:- SE $14 p
s L
Supporting datat i-This is a gradation upward from EALl81 and is more definitive than 683 l'
EALl8n Loss of Physical Control of Facility I
s NUREG 0654 exemples GE $3 j
EALS8o Loss of the Control Room j
't NUREG 0654 examples GE $3 Runrert ina datat This is a gradation upward from EALl8k and is more I
definitive than 81.
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t APPROVED OCT 171969 B. O. S. R.
(0517A/0029A/051389)
l
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i L
('3.
I KiS'A BEP 210-Al 1.,
g, Revision 2 I 4 ;'
f c-BYRCBI EMERGENCY ACTION LEVEL (F.AL) PHILOSOPHY c? x j
l ~
Condition 9.
Other Conditions of Equivalent Magnitude EALl9a Unusual Event Class Description j
l' i
Ruggg 0654 amample: UE $15 t
"[
EALl9b Unusual A12 craft Activity NUREG 0654 amample: UE $14a
{
Eunnertina datat I
Unusual aircraft is any aircraft which touches down or i
~~
appears to be surveying the site without having received
[
prior authorisation.
i EALl9c Inadvertent Dilution Eupportina datan This is an FSAR analysed transient which meets the general class description for Unusual Event and is not covered by other EALs.
EALl9d Control Rod Withdrawal l f
Supporting datti
.(
This is an FSAR analysed transient which meets the general class description for Unusual Event and is not covered by other EALs.
EALl9e Alert Class Description NUREG 0654 example: AL $19 e
EALl9f ARM Readings and Survey Results
.~
NUREG 0654 example: AL 66 EALl99 Fuel Pool Level NUREG 0654 example: SE 810 i:
EALIPh Degraded Core Cooling Eupportina datat This emergency action level is adopted from Westinghouse Dnergency Operating Procedure Guidelines and is consistent with the general class description for an Alert.
Classification occurs upon orange path classification for core cooling in status trees and entry is made into BFR.C2.
I i
APPROVED
'7 OCT 171969
, (0517A/0029A/051389)
II. C). SI. II.
n o ).
s, BZP 210-Al
", ',. ~
Revision 2 j.
i BYRCH ENERGENCY ACTION LEVEL (EAL) PHILOSOPHY a
Condition 9.
Other Conditions of Equivalent Magnitude (Cont'd) g EALl91 Site Emergency Class Description MUREG 0654 emmaple SE $17 l
c EALt9)
Fuel Pool Level i
MUREG 0654 amample SE 010
+
EAL49k Inadequate Core Cooling Bunnart ine datat This emergency action level is adopted from Westinghouse Emergency Operating Procedure Guidelines and is consistent with the general class description for a Site Emergency.
)
Classification occurs when a red path on core cooling is classified in the status trees and entry is made into BFR.C1.
EALl91 ~ General Emergency Class Description NUREG 0654 mmmenle GE $4 i
['
Supportino datas
(,
The term " probable" was substituted for the term
" potential" to be consistent with GSEP and with other EALs.
l EALl9m Imminent Core Melt MUREG 0654 examples GE $4 REgportina datat This emergency action level uses core exit themocouple readings or percent hydrogen in conjunction with core uncovery to project inuninent ccre melt. The core thermocouple readings and percent hydrogen adopted by this EAL are indicative of fuel pellet over temperature and i
fuel melt.
i l.
n l,
1 a
' O APPROVED H:
OCT 171969 i
(0517A/0029A/051389)
B.O.S.R.
4 6...
P BEP 210-Al i
Revision 2
'Y]N.
BYRON ENERGEllCY ACTION LEVEL (EAL) PHILOSOPHY o
j Condition 10.
Personal Injury Transportation of Contaminated Injured Person
<1 RAL610a MUREG.0654 example UE $16 EAL610b Hasardous Material MUREG 0654 emmaple UE $146 supportino datan This EAL addresses the State of Illinois Public Act 79-1442 Hasardous Materials Regulation.
5 1'
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A APPROVED OCT I 71989 h l (0517A/0029A/051389)
R. 43. S. R.
o
_ o.:.. o
)
L BZP 210-41
.,,m..
Revision 2
.I' l
s BYRCBI ENERGENCY ACTICtf LEVEL (EAL) PHILOSOPHY
{
s.
Condition 11.
Transportation Accident t
6 EAL611a supportiner datan l
This condition is derived from GSEP and is related to the l
laws governing transportation of hasardous materials.
1.n.,
EALillb Supporting datat
'l This condition is derived from GSEP and is related to the laws governing transportation of hasardous materials.
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.r APPROVED (Final)
OCT 1 7 1969 p,
8.O.S.R.
(0517A/0029A/051389)
...... -.. -.