ML20052B116

Public Version of Revision 11 to Emergency Plan Implementing Procedure 3100022E, Classification of Emergencies.

ML20052B116
Person / Time
Site:	Saint Lucie
Issue date:	04/07/1982
From:	Harris K, Williams J FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17212B554	List: ML17212B555 ML20052B116
References
3100022E, NUDOCS 8204300046
Download: ML20052B116 (20)

Text

.._

i . .

Page 1 of 20 t I.

FLORIDA POWEk & LIGHT COMPANY s';l j ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE

g #3100022E, REV. Il

?; <=

I 3i

. 1.0 TITLE:

CLASSIFICATION OF EMERGENCIES

2.0 APPROVAL

Reviewed by Facility Review Group August 8, 19_75_

Approved by K. N. Harris Plant Manager Aucunt 19_Zj Revision h Approved byRp //_/yieweg/5 s.by FaciRes.____

iey Review Group,Narej 2.a 4 2.

//// V.P. Pwr. NdrC4 2419[

! Revision 9 R ewe by Faci 1Jty Review Group / 1.1,;;1f 199/

Approved by_ t b "Jd/ F V.P. Pwr. Res. h 2., 19 P/

Revision 10 Rev w df ,by FKG /) Luw4V 2B 1982.

Approved by #4///m\/ Dir. , Sucl. Energy _ f./ 1982.

f L/

] Revision 11 Re "ef by FRG[/) /M g , c k lI 1982.

Approved by g2/ half, (/ V.P. Nucl. Energy y/ 1982.

]

3.0 SCOPE

[

', 3.1 Purpose This procedure provides instructions on the classi .

4 fication of emergencies at St. Lucie Plant.

)i

~'

3.2 Discussion -

In order of increasing seriousness, these are:

f 2 Unusual event Alert l ,1 Site area emergency I General emergency A gradation is provided to assure fuller response preparations j for more serious conditions.

3.3 Authority This procedure implements the St. Lucie Plant Emergency Plan.

1 e

?

m e rs_ .e m ~.-~ mmsa a r-I -CP

$UAOS Obf & - -- .- . - --

~ ' ~

• ~

k .

1 . .

• Page 2 of 20 l

l PLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 ,

l EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100022E, REV. 11 i

i wl t

3.0 SCOPE

(Continued) 3.4 Definitions 3.4.1 Unusual Event'- This classification is represented by Off-normal events or conditions at the plant for which no sig-nificant degradation of the level of safety of the plant has j l occurred or is expected. Any releases of radioactive material 1

which may have occurred or which may be expected are minor and constitute no appreciable health hazard.

A!

q j 3.4.2 Alert - This classification is represented by events jll j

which involve an actual or potential substantial degrada-cion of the level of safety of the plant combined with a i

' potential for limited uncontrolled releases of radioactivity j' ' from the plant.

t 3.4.3 Site Area Emergency - This classification is composed of t

) t

' events which involve actual or likely major failures of i

i plant functions needed for protection of the public combined with a potential for significant uncontrolled releases of j] j ,

j radioactivity from the plant.

1

3.4.4 General Emergency - This classification is composed ef

events which involve actual or imminent substantial core j degradation and potential locs of containment integrity 3

' combined with a likelihood of significant uncontrolled l l, releases of radioactivity from the plant.

t1 j 11 4.0 Precautions J! 1

! 4.1 Conflictina Information i '

When apparently conflicting information is available, the condition 1 I

shall be classified at the most serious level indicated.

i 1'

2 4.2 Judgmental Decision If, in the judgment of the Nuclear Plant Supervisor (Emergency i

j Coordinator), a situation is more serious chan indicated by instrument readings or other parameters, the emergency condition 1l! ! shall be classified at the more serious level. )

)

ii 1i

}I i' .

1 i

f!

I

• Pcg3 3 of 20 1 .

FLORIDA POWER & LIGHT COMPANY I

ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTLNG PROCEDURE .

1. 3100022E, REV. 11 m\

5.0 Responsibilities 5.1 Plant Personnel 1

1. All plant personnel are required to promptly report the l existence of an emergency condition to the Nuclear Plant Supervisor by the fastest means possible.

l 5.2 Nuclear Plant Supervisor 5.2.1 The Nuclear Plant Supervisor shall promptly classify abnormal situations into one of the four defined categories.

i

5.2.2 If the diagnosis indicates that the condition is i classified as an Alert, Site Area Emergency, or 1- General Emergency the Nuclear Plant Supervisor shall j, declare an emergency.

I 5.2.3 If an emergency has been declared the Nuclear Plant a

Supervisor shall become the Emergency Coordinator and retain this position until relieved.

, 6.0

References:

6.1 St. Lucie Plant Radiological Emergency Plan 6.2 E-Plan Implementing Procedure 3100029E, Duties of Individual j Discovering Emergency Condition l 6.3 E-Plan Lsplementing Procedure 2100021E, Duties of Emergency Coodinator l

! 7.0 Records and Notification

' .I 4 l1 The basis for classifying an emergency condition shall be recorded.

l ;

1

• l i l l 1 1 1 1

!'l ii I i .

( i; l

l l

l _

~

l .

s

. Page 4 of 20 FLORIDA POWER & LIGHT COMPANY i ST. LUCIE PLANT UNIT NO. 1 i EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100022E, REV.11 .

ai m-m 1

8.0 Instructions

8.1 The Nuclear Plant Supervisor shall initially classify a situation as 1l

• soon as possible after becoming aware of the situation. The classification shall be made on the basis of readily available observations and/or calculations and should not rely on sampling and laboratory analysis.

NOTE: Within 15 minutes af ter the initial classification, the state and/or local agencies listed in the appropriate check list in EPIP 3100031E shall be notified.

) 8.2 If subsequent information of a more detailed nature (e.g.

sampling results) becomes available after the initial classi-fication has been made, the event shall be reclassified by

, the Emergency Coordinator if appropriate.

h

8.3 The Nuclear Plant Supervisor shall classify events in accordance with the attached Classification Tables. The event shall be

] classified by macching the actual situation to the one most closely approximating it in the tables.

}

j 8.4 Classification Tables are provided for the followin3 ij categories:

I

1) Primary Depressurization i

Miscellaneous

Abnormal Primary Leak Race i Abnormal Primary / Secondary Leak Rate Loss of Secondary Coolant lj 2) Abnormal Radiation, Contamination of Effluent Release Values /Rll 1-l Uncontrolled Effluent Release t

lj Eigh Radiation Levels in Plant

,], 3) Fires Lasting More Than 10 Minutes lJ' i 4) Accident Involving Fuel

,1 11 Fuel Element Failure

! Fuel Handling 1

i Natural Emergencies 5)

Earthquake Hurricane

, Tornado Water Level Abnormal

,j .

/Rll ,

1

• l l

)

~

l _ . __.

Page 5 of 20 l ,

i; FLORIDA POWER & LIGHT COMPANY

'l ST. LUCIE PLANT UNIT NO. 1

- E!!ERGENCY PLAN IMPLEMENTING PROCEDURE

' #3100022E, Rev. 11

.U

8.0 Instructions

}

} 8.4 (continued)

Miscellaneous Events /R11 6) l

' Contaminated Injury

' Abnormal Temperature Abnormal Shutdown

7) Electrical Malfunctions Loss of Power

8) Degradation of Control Capabilities Engineered Safety Features i Loss of Containment Integrity Loss of Alarms j 9) Hazards to Station Operation Aircraft Toxic or Flammable Gas Onsite Explosion

• Missile Turbine Failure Security

/R11 10) l e

eMe= +

a ma< e a y

j9}!  :' t .

.I

~

~

~ -

~ s i e T

~

_ t c

u l s

o d

n os e

g e

t t b nS o l.

d ci a dK I

o r m i n o.s n eC r o gd a t E pf nr J t a si t

. t i nc i C n l uh d e o a ot a md l Y

i l l nn N

C i

s t s n l e oh c i a a

sC nN R i e f t l At d oE f t eC ne i G a t R o ed uOot cE M 1 p h n t a f L cc a aM f h d ddJ e E

~

0 2

i u o i t

i r f t oe) eeerd.

mmmb e e

t L r r r r eA

~- ~ f o

2 w h t ont l .

i ii y o l R pE M f r o ie e uen e

ff f t t nnnis mN 6 C h t

sn ooor e oE e s r t yni CCCgr CC

~- ~. g s r nom Ai m . . . .

- . a o a f 123 1 P L b o ( t i

- ~-

M E

_- M

_- A E

~-

R A

n i

S N

O IT A

Z

. I R

U 4 S T Sf R .

E o I . .

R L P 1 A E

D e g

Y a R F A

M I

. R P_

l s ) -

e-ei e

ves

, S C D d

n D

.t f T f t d _l vt s R - N a m N if nS C snD al h l ( i cA o g aoA r e oI C yi N vas i di ,t en et ei dK L

- E S A vt a m r nt nri t , vl e e weisr s i us sea e eC a s ,noy I f os uop sa ri er t E sl l

_ f t o n gpt sib n e s li sot o ese nusl i C o v yf r acir ser i s pb e

_~

_ i n l neadi l s u and m ar c s s l o o isl et a f ss o e epe pe0d i e T

- i o n ot a v t n

oseeme .t r as cr r d or0p5 ut r as sN nE t C nr sac evh oV a uoici f a nrl t wuiy eeh d MV i

t e rt r ord n id l

e l o i opa os sS vnl s p d zt i i D_,l rnrr oaoo g i E t

cL E i nC p o ameni di t

e o t h c_ a g f of e r 0 n i r wN at h m_t ae A mat t sin aA U

A I_

yub mya

c. s o n r ,

c ued e p0 e r ioiev 6t usl sseeoest r r a.oii t eS d tp l ai r _ o d rl t l S1S uevv nnsstf t U eN e n d t o et nh eaaC nr eab eeiai U pl TA gt V cl lp U G n gS eS ni n gC t C es y s c I t r cvR < n o a i N

U a rC aC poR t l e . . a . .

c

. me oh l gE cE o pO e c R e b Ma b Ct p m f n { . . a o . .

U {1 2 St 1 2 l

) )

A B

_ S

_ S  % .

A L

C m S U

D

_ E N

A .

L I

N T F p N C T

' VE S C E IM

. Q .

l

_ i

. R C4h8" e /

_ l

_ i!! l' 1

\

1. ll

,; i

{']  ;,,j'  ! ' ll

.a -

..-.~ . - - . - - . . - ..

. _. .- . . . . _ . . . _ _a ..

[ Page 7 of 20 ,

PRtHARY DEPRESSURIZATION Sheet 2 of 4

. CIASS EVENT UNUSUAL. EVt.NT ALERT SITE AREA EMERCENCY CENERAL D1ERCENCY ABNORMAL PRIMARY RCS leakage greater than allowed RCS leak greater than 50 are - EUCAJ reater than capacity of A release I.as occurred or la in LEAK,, RATE _ by Technica LSpecificatione primary to atmosphere cggtg pumpe_ progress resulting in A. RCS uater Inventory balance indicates (1) Clearging/ letdown mismatcla (1) Unusual decrease in pres- IDCA Dose Calculation Ef tr

1. greater I give untJentified backed up by RCS water surizer level anJ pressure 3100033E Appendia a worksheet leakage OR_ inventory balance indicating with constant T(ave) AND values in excess of I R/IIR

2. greater than 10 spa identi- > 50 CPM and < l32 gpm (2) Hakeup rate greater than (whule body) or en integrated fleJ leakage OR_ leakage AND, capacity of 3 cliarging Jose of SR (thyroid) or (2) Contalement or plant vent pumps (132) spa) AND containment high range radiation l S. Inspection reveals any RCS radiation process monitor (3) Contalement pressure >2 monitor Rgenter than or equal to pressure tenulary leakage. reading above normal. pels, or containment I,47 x 10) p/itr (post toCA radiation monitors inJ1- monitors greater than 1000 ser/hr rate above normal values. If CllRRM inoperable) 4

.I 1

ll O

g ACTION 1. Complete artions listed on' l. Complete actions listed on 1. Complete actions llated I. Complete actions listed on g the UNUSUAL EVENT CHECKLLSTl. ALERT CllECELIST on SLTE AREA EMERGENCY GE14tML D1ERCENCY ClitCRLIST g CIECRLIST

/Rio

/ Ell .

t l

l L ___

5.i . & _m m . L_ u_ . . c_ _..%w... __i

5. . . E.25 . , , _ _., E . .[ _; - , _ .

~

l Page 8 of 20 PRIMARY DEPEESSURIZATION Sheet 3 of 4 x

UNUSUAL. EVENT ALERT SITE AkEA EMERCENCY GENERAL EMERGi n

~.

Ants)kMAL PalMARY RCS PRl/SEC Leakage Creater Than Rapid gross failure of one steam Rafid failure of steam u-TO SECONDARY I CPM. generator tube with loss of generator tubes with a loss of .

LEAK RATE of f site Power (w/t charglyg of f-site power (> clerging pg j

1. RCS Water inventory balance capacity L capacity L indicates:

1. Unusual decrease in pressurizes (1) Unusual decrease in pres-A. Creater than 1 GPM pressure and level with suriser pressure and level unidentified leakage AND constant T ave., followed by; with constant T(ave), AND B. Blowdoun process munitors 2. Above normal or increasing (2) Above normal readings on and condensate air ejector steam generator blowdown and radiation process monitors process monitor reading condensate air ejector radie- for steam generator blow-above normal or tion process monitor readings, down and condensate air increasing. D

_AND; ejector, AND

3. Loss of the 6.9 KV and 4.16 -(1) less of the 6.9 kV and KV busses (IA1, IA2, IBI, 182) 4.16 kV busses (IAl, IA2, OR 181, 182), AND Ray 1J failure of steam generat s (4) Simultaneous unusual tubes (> chargina PP capacity) increase in one stemas generator's pressure and

1. linusual decrease in pressuriser level.

pressure and level, with e constant Tave* M i

2. Simultaneous unusual increase in one steam generator's pressure and level followed by;

3. Above normal steam generator

] blowdown and air ejector i radiation process munitor readings.

+.

1 I

9 ACTION 1. Complete actions listed on 1. Complete actions listed on 1. Complete actions listed

• l r the UNUSHAL EVENT CllECELIST. ALERT CIIECELIST on SITE AREA utERCENCY 8 CitECELIST.

i"i

/Rll .

.i;-...._. . ....- .

. - . . ~ . . . . . . . . < . ...L, .m..,as. . ; -. . _ _ . - .w---..a . . . .

'E' j

, pulHARY l>LPRESSURIZATION Sheet 4 of 4

~.

CLASS UNUSUAI. EVENT ALEkT SITE AREA EMERGENCY CENERAL NtLRCLNCY EVENT IDSS OF SFOmDAki kaptJ depressurtaation of Major steam leak with greater  !!ajo n tese leak with areater Ox)lANT secondary slJe with no primary than 10 gra primary / secondary , than 50 gym primary /secondar t to secondary leakage. leak rate leak rate and fuel damage inJi-dated t 1. Unusual Jecrease in pressuriae 1. Unusual decrease la pressurizei pressure anJ level with pressure and level, with 1. Unusual decrease in ,

decredelag 7,v, AND decreasing T,y , AND; pressuriger pressure and level witti decreasing Tave.

2. Simultaneous at, normal drop in 2. Abnosmal drop in main steam _AN!jL ttate Steam or steam or steam generator pressure generatur pressure to less to < SOO pela, AND; 2. Abnormal drop in main steam st.an 500 psia. or steam generator pressure

3. Steam generator blowJown and to < $00 psia, gi

conJenaate air ejector

) raJiation ,rocess monitors 1. Steam generator blowdown and indicate at .ve normal, (OR. condensate air ejector known pri-sec leak of > 10 raJiation process monitors gym). InJicate above normal, (OR,,

kiuswn pri-mec leak of >SO gle) .

? 4. Fuel damage as indicated by i lent known primary sample.

\

i l .

i .

l l

I . _ - _ _

l D u TION ~ 1. Complete actions listed un I. Cumplete actions listed on 1. Complete actions Itated N the UNUSUAL EVENT CllECKLIST. ALERT CalECKLIST. on SITE AREA EMERCENCY I S CllECKLIST.

l 5 l

l- /pii I

l ,

I

- .. . - . . . _ _ _ . ~ . _ _ _ . _ _ . . . . . _

4 I

i II l

l i

i Fage 10 og 20-ABNORMAL RADIATitM ' Q1NTAMINATItm OR EFFl.ljtNT REl EASE vat UES l

I-I:  % GENERAL EMERGENCY UNUSUAL EVENT ALERT SITE AREA utERGENCY e

LtkRT i

tWOWTuol l ED Radiological ef fluent Tech. Specs. A release has occurred or is in A release has occurred or is A release has occurred or is in progress resulting tas b h

progress that is 10 times the in progress resulting inn tFFlUENT BFl.tASE Limita exceedeJ IDCA Dose Calculation EFir

1. Plant affluent monitor (s) 7.5. 11mit (as shown by sample / LOCA Dose Calculation EPlr

-} survey) 3100031E AppenJim B wusksheet 3100033E Appendia B worksheet esceeJ alarm setpoint(s) ,

followed by values in excess of 50 MR/itt values in escess of I t/ttR .

2. Cont treed analysts results f or (wtele body) 250 MR/tta (whole body) or asi lategrateJ (thyroid) for 1/2 twur OR_ Jose of 5 k (thyrotJ)or gaseous or !!qutJ release 500 MR/ tit (whole body) 2500 containment bish rante esJiation which exceeds Technical Spect-iscation !! mite.

MR/ Ilk (thyro 1J) for two sin at monitor > I.47 a 105 R/hr El.e site bounJry. or (Post I or 2 M witter >1000 mr/br Containment tilgh Range if CllRkM inoperable)

RaJiat ion Monitor >7.3 m 10 3 t et/hr /RIO l tilGli RADI ATION liigh radiation levels or high

! I EVElS IN PLANT altborne contamination which indicates a severe degradation in the cc.ntrol of radioactive materials (1) lastalled raJiation monitor-lug stations indicate al,nosmally high radiation levels. OR (2) Installed airborne particu-late or iodine activity moultura indicate abnormally tilgh levels. AND_,

p+

. (1) 1.evels >l000 times normal are con (trmed by area h:

surveys and/or analysis of

.s< grab samples.

n

^** 1. Co*Plete actions !!sted 1. Cameplete actions listed I. Cumplete actions listed ou

i. Compiete actions u.ted on on A nkT CHECE W ST on SITE AREA EM D GENCY C D ERA 1. EMERC DCT CHECEW ST UNUSUA1. EVMT CHECEWST CllECELIST

/Iti l 4

e _. . _.,_ J . .- -- --~

I 1

I I l

? I l

I e.

6 e

'? 5 W

=

o b

d N n

l l i a u

=

Se lk *

. i 3

l 5 l1 l.. C=

$ ee a i

hs ** O 8

se se m Q k eW

' 15 l 5 C E

=*

~

w x

"E g-

"2.

w E e aC te

= h 9 W q ee a eW

m == 9>.=4

[

• 3 h =e == ad

, a6 2 ** & ttl U D # W

( E~

hf he me l

W C0 t#5

.hse es .

Ine Q **

I

.h.

g eC e 3 em 4 ee "k eie es .e aS S e

& E b **

a ea me be l

W O =* 3 t/t hea 3w

1. h id J": , 3" Jd se h == es W hlg*E to M

== ** e us W I l

j W:C 4W E 3 ** I Wk M <C "D eQ w2 Uge =

n. 'E

m W 5 o m .a. .a e l g w wk C m ta

$g 3 u~e e

$ me 3 5 3 3 to se a

N G ts

• f#1

= 2 D **

g 3*

== he .C. 7 1

3* me a D 3 e me M

1. C F G G "=

=e a sme j =U he me te en Q 68 3 3 E

G 3 A

8 se 3>

2 ao M 4 9 e e, e ,

> me a me g I es W *e g as3 3g J

• • 9 y L 4,, E, 3 yG & O $ 4%

D e h 'J g as 3 m == a m . ese 32 3 ame g 3 =

am 3 2 = I 3 Q ne to h .9e .A ' s s

=e W= 3 J g em a w e # 8 9 9 W 3 *e n 2 == .is .

3 4 3 ra. ==

i M

8 M b

o .

If 5

w

=

l,m#

e

/ ;al h

.e em W

mW-g ,, y .,--m_-- --w- . _ w

~ - - - - ~* ~~ ~ ~

Page 12 of 20 j ACCIDENT INVOLVING FUEL _ j UNUSUAL. EVElff ALERT SITE AREA 1.MERCENCY CENERAL FMERCENCY .

EVEfff (UER. EIENtNT Fuel damage indication fevere lose of fuel cladJing , Core damage with inadequate core A release has occurred OR is Fall.ilRE inclinling cools,t pue d allure cooling determined by in progress resulting in:

A. Letd.nen toJine process monitor leading ~to grose fuel failure ~ ~

Loca Duse calculation

) alarm followed by (1) RCS 1-131 activity , ErlF 3I00033E Appendix B work-

8. Confirmed RCS sample indicating (1) Letdown todine process 275 uC1/mt, sheet values in excess of I R/ lit

1. Coolant activity greater monitor alarms. AND (2) RCS temperature within 20 (wholebody) or an integrated than the Tech Spec limit for (2) RCS l-131 activity ~> of T(mat) . AND dose of SR (thyroid) or todine spike Figure 3.4-! M 275 uC1/ml (3) toop AT >44*F containment high ragne radiation

2. Coolant activity greater than monitor 3 1.47 m 10 R/Hr IOO/r uct/ gram specific act- (post I.DCA monitors >1000 mr/hr 9 if CitRRM loogjeratile)  !

H!EL_ lLANDLING Fuel hanJIing accident uhtch H_alor damage to spent fuel ACCIDENT /RIO results in the release of radio- in containment or Fuel Handlina activity to containment or Fuel Building Handling Building:

(1) Step increase in the (I) Direct information from fuel readings of radiation handling personnel indi- monitors in the plant vent cating that an irradiated and/or in the fuel hand!!ng fuel est.embly has been building, AND damaged and gas bubbles are (2) Damage to more LLan one escaping,_AND., f uel assembly, OR (2) Associated area or procese (3) Uncovering of more than one monitor channels are spent fuel assembly in the alarming. spent fuel pit.

i l

l l

p ACTION 1. Complete actione listed on 1. Complete actions listed 1. Complete actions listed 1. Complete actions listed on N the UNUSUAL EVENT CitECKLIST. on Al.ERT CitECKLIST on SITE AREA EMERGENCY CENERAL EMERGENCY CitECKLIST.

O CllECELIST M

l n

/Rll ,

I i

i

n . . . . ~ . . . - - . ~ . . . - - - - . . . -- - . .y

_ .. . . .. - - ~---.

l Page I) of 20 NATt;RAL EMERCENCIES

! CIASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY CENERAL EMERCENCY I I

~EARTi>JUAKE ,

An earthquake has occurred as An earthquake occurs which An earthquake occurs which l j andicated on earthquake force registers >oBE (0.5g) on NOAA registers >SSE on NOAA seismic }, ;

. monitor SMI-42-!! (post accident seismic equipment. equl geent i '

f panel) and annunciated on R1CB 106 (S16 and S46).

l_lUR RME_ Notification by NOAA (Weather Notification by the Weather Notification by the Weather Bureau) that a hurricane warning Bureau of the approach of a Bureau of the approach of a is in effect. hurricane with winda up to hurricane with winds > design

, design basis (120 mph) levels basis (120 mph) levels I

TORNA!10 Any tornaba em alts. Any tornado striking facility Sustained winds or tornadoes e in excess of design.

WATER I.EVEl._, 50 year flood or low water, Flood, low water, hurricane Flood, !aw water, hurricane hurricane surge OR other abnormal surge OR,other abnormal water surge OR other abnormal water ABNORMAL water level Condit ions level conditions cause the storm level conditions cause vital drainage system to be exceeded. equipment to fall. e

!. Notification by NOAA (Weather Bureau) that abnormal water level conditions are i espected or are occuring, or l 2. Visual site'ings d by station I personnel that water levels l are approaching storm ,

drainage system capacity.

s 9

Il Act'10N 1. Cumplete actions listed on 1. Complete actions listed 1. Complete actions llsted j h'4 the UNUSUAL EVENT CHECKLIST. on ALERT CHECKLIST on SITE AREA EMERCENCY CatECKLIST u.

e k

/Rll ,

e

i l

', , g -!

f l

.. 6 Y

C N

E C

R E

u M E

L A

R E

, N E

C .

Y C

N E

, G R

, Et k

k A

E R

A -

- E T

I S

S T

N V E -

V E

2 s

ta f t

E o -

N 1 A T

t. t E e R E e E C h L S

I S A M

b T

- l u s nS e u r

e r

oF s

t ee1s rh ut 0e i

l o l. l t

u f

l t

i 0 aw.lp r oeul a

uaf dE e C.

a a n2 el r oe d o tsiFl r m o peucu i o e r p o mna mbt uf e am i vt t n

i C l

m n nh t Frrl d ee T

- e b i t

• e ea nt m _ sN nL T g s0 mt ph sm E

N t

t a

r s as l e2 e o .

I isa d - e t

_ loV L t

V n e nt ens ef r cl.

a E

L l

a r o

u o

meet g

l ns .ht oc ohnoar rb e u

t f t ao n r aA

_ teSUU A o b e i e inet id o _

U c e r l t gt st it a mef _

eN S

U r u p t oans sa ar at t rl s

_ l U l ocie ert ce p N a a cil hl unip noae opt i me U m R r bd og t ad m oh r O e unol aal ne c sir npu o / p Si cI l mPit l Ct nD m yasj bN e . . . nr on _ .

1 AAt 1 2 3 At hi _

S S

A t L D .

c E F T

R

.!t A l .TE N AAR I N

MRU M V RE S A k O_P S NME 1

TU NI s N IO~

T C-t Ek ATP OI A-l i

N PyQ, /

) I (ill

. .s.,... s m a s.- - - . .~ i w - . . .: ,_: L. m --- u+ w n s -~ .-. :- . --. ......n.

s,_.. _. i 4

1 i

Page 1% of 20 MISCEll.ANEOUS EVENTS Sheet 2 of 2 1

CLASS UNUSUAL EVENT ALERT SITE AREA EMERCENCY CENERAL EMERGENCY EVENT

{ m\

uTHFR CONDITIONS 1. A plant shutdown is required The Technical Support Center 1. The Emergency Centers are An event resulting in escalation Rty11 RING IN- by Technical Specifications; AND/OR Near Site Emergency activated; AND, of the Emergency Classification j CNEASED AWARE- OR Operations Facility are activated 2. Honitoring Teams are to Ceneral Emergency with

,j yS_

N 2. The plant is shut Juwn under for other than drill purposes. mobilized; AND, , lassinent Substantial Core Damage d

• abnornal.conJirions (e.g.. 3. A precautionary public and potential for release of eaccedin g coolJmm rates or nottitcstion is made con- large amounts of radioactivity 3 primary system pipe cracks cerning an abnormal plant in a short period of time; such t

'l are foanJ Juring operation). condition for other than ass drill purposes.

1. IDCA with f ailure of ECCS.

2. Loss of Secondary Heat Sink.

3. Sustained station blackout with loss of secondary heat sink. ,

4. Failure of containment heat removal systems in the later stages of an accident result-i; ing in loss of containment.

I 9 >

i ;.1 8 _ _ _ _ _ __ .__

!3 ACTION 1. Caumplete actions listed on 1. Complete actions listed I. Cumplete actions listed 1. Complete actions IIsted

• ~~

the UNUSUAL EVENT CHECKLIST. on ALERT CHECKLIST. on SITE AREA EMERGENCY un CENERAL EMERGENCY CHECELIST. CllECKLIST.

/ Nil

i l

I!$ . ,

lI{ . I l[!*;  !

l I

w

_ 0 Y 2 C

_ N f E o C R

6 E 1 M E

e g L a A P R E

N E

C h r e t - o s oa C f p l b - br D d d i a e B c eY n r l f n 5 e J t C

~ a r t pa i oeg 1 t s

d v n

sN i E e i s e r w ruv; e > a0 l G e rl r n t R s o ot aD 7 Y n p t r aa nuAN_

ueor o o u n

A o

sE nH C a t s nt oE N gC rt t etf l i E ess , air a m i i G n r e fd aet t s t A R yAe et ec z i v

5 pe cE

~

E M

E t t f

si s e s

gnmi el or ar v d ysi ec nnoos n . R O l 1

ras.

og dt e aR .

e AT S

f n t n pf e .iet r e l l t t E l.

A o o u i ss ag ht a r d ou eTI

~

E n bh n t r scu o evn l I E pSC R f f r t ar ser nn f f n i E

~ A o o im uir o umoyi o i sm m Twtf S et sm s r

e au unl l E s s 5 t b5 C oC s s

~ u s 1 w 1 T

I

o. o > . . o o uC .

S Il 1 2 R p SD> 1

~

D

~~

N O l s

s o

• . n ,

s N

A, yr ca nt t

r I pal es e d e

T d ir a g w

~~ C n rt n o

ro o p

t s

N a t et .

U r pt m sa i .

F r e rut es C ut l T e w ot c D Bl S A w o t r n i r o o sI H o p aau tt t e e C v nL p rt f oar t D oK L C es - brt i 0 i C A e A n n e n s B7 t E C t et o f no n cII I T i e gnn oer R o d< aC R R s t a gh O n T E f i el s npr e c l aot eT t R L L f s rl n l A o n i e uey a A e E.

E. o bh m t s s s l 1 l

E f rt r l e f ne pA o l uio air o i g m on s

l s a Twf FJ o s s

pt ol a o a

C o

~ o fo 1 2

l o Dv 1 l

~

e y h R n s t o i t

ir s O_3 Ar I o o .

l l we: f dT r b i

s meh g a ct s t

eS

~ o pa i oioe . sl l.

- rf vbss iK r a t sr sd

- e r w

n e n u, n ras ot o l C.E or or c si l nC

-- T pe w

t t reV e a o gE s o ir

- N E

eo t p r pf a eu t65 t ff cE x V E

i s C nt el ert o 1 1 aVL

~ - A ganv4 n e

l

. f t a a t L A f e esl f ) h eA

- U o t n l o5 1t l U S i it a pS U f s b nv s e mU N o - r aa mD r oN M U n ul neN u CU s o Tput A s s

s .

l o fo 1 2 1 a

S S

L A L

R E

C W .

O P

F O

n. T S N

io N S T E _ D C V.

4 I

A

- 1 O48Q "

8R

/

, :\ *

! l , f'

. .a u >m.a . w- . . sw - ~~. ~ w :-+u. ~ ~ ~ - -~- --

.~ ~~ ". . "." . ~ ~ " . . ' ~ . ~ - - - . - . . -

. , . .. . . . . - .. a.

- . . - . \

Page 17 of 20 DECMADATION OF CONTROL CAPAhlLITIES }

Sheet 1 of 2 t.

I

-.N e

N UNUSUAL EVElff A1.ERT SITE AREA EMERCENCT CENERAL t)tERCENCY 9

EVt.NT L'l '

t>qlNEER&D SAJETV 1. A malety featurve actuation 1. Lose et functione needed for Loss of any function or system system functional unit shown cold shutdown. OR which precludes placing the k i NATUkES/REA_CTOR I PRO.[EfTlyN_ M STEM' in Technical Specification . plant in llot Shutdown. OR SYSTFHS TO PIACE table ).3-3 becomes inoperable 2. Failure of the Reactor PI _A_NT. IN_ _COR D per Tecimilcal Specif! cation Protection System to bring Control Room is evacuated g SHUTylnnlNf_ 3.3.2.1 AND requirea plant the reactor subcritical when (for other than drill purposeul fa O WTROL N00M,._ minaldoun. OR needed. 11 and shutdown control cannot be k OPERATION AND established locally at the llot l-FlkE PRtyrECTION. 2. The fire nuppsematon system 3. Evacuation of control room ShutJuwn Control Panel within SYSTEM or a portion thereof becomes (for other than Jrt!! pur- IS minutes.

tuoperable per Technical poses) with shutdown control i Specification 3.7.11.1 Ala) established locally at the tequires plant shutdown. Hot ShutJown Control Panel.

, idSS OF AIARMS Significant tous of effluent All annunc tJtors lost, All annunciator alarms lost

• monitoring capability, meteroto- >15 minutes with plant not in gical munitoring instrumentation cold shutdown; OR

<l' i

commsunica t ions, indication asul Plant transient occurs with e alarm panels, etc.. which impatra all alarms lost, ability to perform accident or emerr.:ncy asmemament.

.l O

i ;4

' 8 4

ACTlHN 1. Complete actfuns llated on 1. Complete action:3 listed on 1. Cumplete actions listed UNUSUAL EVENT Ct!ECKLIST. ALLRT CatECKLIST. on SITE AREA EMERGENCY CllECKLIST.

/8:l l

t >

' , i %

e i

1 i

i .

0

_ 2 Y C

f N o E C

8 R 1 E M

e E

-- g a L P A -

R -

E N

E C

e, -

Y

- C

- - N E

C

- R E

M E

. ~.

A E

. k A

E

._ T I

S S

E s IT l.

it

_ b A

P A

~ C L

O

& R

- T 2 N) f

, F 0 o 2 *

. O t

N e _

- O e T I h R _.

T S E A L D

A R

A C

E _

D _

. s - y sf c l b ao e

. y e

p el b su d s rt2 n o

eo n

l i - nrb l _ no t o e e ip- t

- i S. oc s v bt oooa .

- rh t o l ic hc e e 6.t i on aa gr c si ,re dT eS c t l a t t x3 a st aasp yTe d n c v rmn a e c sR ei r wo t I sL

- ee ei i O pf t

g oi mt on _ i K n rd l auislf e ; c l C i y ii n a ,t nbi u el i _

. b uc i u ud oac ltdt e t nl ne em sH E

a T t

n n qc ea eN nsmeiTert _

bOae p , tataeop nS apb e a

nC o

N E

e w m o r

gT: r f

, m gd u i n S R_l necsi O esl l a

( ,o m

i T

- V nd snt oS yat ea l t mia c, emla dsce t N E

l.

i t

a u t

h niN or i uel Sd eF Abl aspd a;n f v i sddi ec1 edki3(

mncn gi le b l

. e cE aV E

A n s t d rbE edts encvsvh e i n 3. ipaoli;nww)s

. U o g a aa peoial ooc 6 ud r l ce 3. l d .,gn i

._. t L S

U c

n rd t es ahl l eal r e qeiT1 ae et gi lea pS U

N f i esnCt Cbd v c pT 3 ema U o ir noo o r6 sa .r mU el i . . nl ne l e- oN s u P ct1 2 A cA p3Ac(0 CU s q . .

o. r e . .

I A B C. D  !

L _

. S -

. A NY _

T I

C IAI TR

_ NC _

. DE

( T N FI N

O N_

O

.' T T l N SN f E Sf "

(

' V DM _

A

' E _ I 0

1 9u8Q o N

/

i

_lil, i,ll

• il;

_ ,_ .. . .m . . . . -- - - - * + 4 'A * ~ " ~*"~~~~~~ ~~ ~ ~ ~

Page 19 of 20 t

ilAZARDS To STATION OPERATION N CLASS ALEMT SITE AREA EMERCENCT CENERAL EMERGENCT UNUSUAL. EVENT EUENT AlstruAFT Visual, ugght ing of aircraf t crest, Aircraft crash onsite damaging Aircraft crash on site on-mite or of e nusual aircraf t plant structures. damaging vital plant mystems activity over facility, or structures. 3 ONSITE _ Visual or audio indication of Damage to facility by emplosion Damage to safe shutdova EXPl.OSION an emplostun near or cet-site. whicle af fects plant operation. equipment from missiles or emplosion TOXIC ou FINt- Indication (winual or otherwisa) Entry of toxic or flamunable Alarm indication is received I

HAbtE CAS of a near or on-site tosic or gas onto dress potentially on Detecto-Chlor or toxic or flammable gas release. affecting plant operation, flamenable gas has dif fused  !

into vital areas.  !

{

HISSil.ES Visual or audible indication Damage to safe shutdown equip-of missile impact on plant ment from missiles or structuses. emplosion.

~

TtfRblNE Fall.ilkE Visual indication that the turbine casing lean been penetrated by blading.

i g _ _ - ._ _ . _ _ _ _ _ _ _ .-

Q ACTION 1. Cumplete actions listed oen 1. Cumplete actions !!sted 1. Complete actions listed 8 the UNUSUAL EVt24T CliECKLIST. on ALERf CilECKLIST. on SITE AREA EMERCENCY Q CilECKLIST.

e i

9

/Ril

I! . : t r +

,l.  ! j i!'- Il:

!!I-.

?!

1 T

nS e o l.

l hl dK t o eC r t E f t sH on o i C l

Y rC Y i C e sC N ve nN E oh G

R k et d.e oE i C t R E agr cE H t inru aM E E 0 l d c e 2 L uuc t L

_ A fl o eA f R sc R o E sns lpE N eia mN 0 E c h oE 2 G ct CC e

unm sao .

g l o 1 a A pR r

t n-a oK h C t

dE l s s el at i t C Y s hn i Y C it l C N yon N E cpa sE C n l nG R eep oR E gh i E M rt e t M E e h cE mot a A et A E f eE

~

~ T S

A E

yd o t e isr e rsel uevb t R eA lpET.

mTS

~ I S

cr egeb oa oI I

~

sok o CSL

-~ r ar .

Apt p

' 1 S

" E I

~ C s

~ N a n

~ E n o

~ G ee R ec d E b r e

~ t J sfd os t a s

" t Y hya r

l i

T t u

" I R

U yi g cr e nuf eca s .

nT oS C geS n. i I E t L S T r s a cK R e el aC

'- E. mehP E

_ ' t A

eht t y el t C l

y t yi n nc e ib e l T pR

_ r d g mE ud en oL

- ceni el i t slf n ae o CA 1

" A cdC

- s d m

~ e e l

l - i t n

~~ as cee s

o dT o .

rh t eS n t o e t I en u enk sL eif r coi i E b o t nir l C e en ast E sce cit b us sl a

" T N

ar r h oo n pt r nC E aamut e o f m

~~-

V E

t r yr t tb eet nc arr t e uatad isir o i T t N c E let o . art af aV L i eh sd e E

- A U

aruno ew h r t i eel ry dt gaat e

t l.

- S ycol t k can i eA

- U t e e cl et rl r l U N i sob bmt aitvot teeau

- pS U r t t c mU ue d ot ir anie oN ch ee BACPSI VS CU et st s

yoi ns . . . . . . . . .

.- 1 2345678 1 Ab pl S

S - -

- A I

C ,

~ y .

t N i

r O

I

. u T y c C

-. e A

- S l

l R

PM8Q - /

- ., .. / ~