ML20077H597

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EI-6.1 Re Release Rate Determination from Stack Gas Monitors & EI-3 Re Communications & Notifications

ML20077H597
Person / Time
Site:	Palisades
Issue date:	06/29/1983
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18051A522	List: ML18051A520 ML20077H595 ML20077H597
References
PROC-830629-01, NUDOCS 8308110113
Download: ML20077H597 (100)

Text

_ _ _ _

Prec No EI-3 Revision 5 Date 5/23/83 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Summary TITLE: COMMUNICATIONS AND NOTIFICATIONS

~

1.

Prepared 2.

QA Concurrence

[N db ig ator

'Date Date Othn$

3.

Recommen royal /Q-List e

No 4.

PRC Reviewed

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// jf3 yJ-gig

' Dite D

tta t Head Date f

5.

Approved 6.

ATMS Incorporated W Set N3d/U M

Plant Mana'ger(~ ~

Date

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7.

Biennial Review Date eil180-00073154*

B308110113 830805 PDR ADOCK 05000255 F

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r gc 1.0 P_ERSONVEL RESPONSl!!!LITT.

t 2.0 PL*RPuSE t

30 INITTAL CONDITIONS AND/OR REQ, IRE.WNTS I

4.0 RELEASE RATE DETERMINATION RIA-2326/RIA-2127, ( l'N tARY 'tc ritoti t 4.1 STACE GAS NOll! TOR READING I

4.2 STACK TLOW RATE..

I 4.3 RELEASE RATE...

2 S.0 RE!J.ASE RATE DETERMINATION RIA;2318/RIA-2319 ( 16ACKt'I'.*lE rtl0D )

2

- -- Sri STACK GAS NONITOR READING 2

S.2 STACK TLOW' RATE I

y

?-

3.3 REI. EASE RATE..

'l 6.0 ATTAC30ENTS s

ATTACNNENTS J

'. " Stack Cas Monitor Conversion Factor, RIA-232b". " Stack Gas batter Conversion Factor, RI A-2327". " Stack Gas Naitor conversion Factor RI A-2 313/RI A-211'8" I

l 1O et0383-0028c154-A9

9

- 4 9

4 PALISADES Nt: CLEAR PLANT Proc No El-g.1 EMERCENCY IMPLEMENTATI,04 PROCEDURE Revanon 1 Pa g.- 1 et 3 TITLE:

RELEASE RATE DETER.'11 NATION FRO'1 STAG CAS MUSI Nhs i

1.0 PERSONNEL RESPONSIBILITY The Chemistry / Health Physics Support Group Leader shall emplerneut this procedure.

In the absence of a Cheatstry/llealth Physics Support Group Leader, the Site Emergency Director (SED) shall delegate this i

responsibility.

2.0 PURPOSE _

This procedure provides a release rate for radioactive effluents frors the Plant stack. This data is used as input to offsite done calculations.

3.0 INITIAL CONDITIONS AND/OR REQtJIREME.YTS a.

This procedure shall be implemented as required in E!-6.0.

b.

Data and results from this section should be recorded on the Dose

-V Assessment Jorksheet Attachmedit I to.EI-6.0 La Section I.1

' ~ c.. The preferred method of determining release rate is detailed

)-

.x

> q,.

Secties 4.0 The backup method is detailed in Section 5.0.

I 7

y

{

4.0', W REI. EASE RATE IETERMINATION RIA-2326/RIA-2327 (PRIMARY METHOD) f 4.1 STACK GAS NONI. TOR READING I

y

~.

.L,

, : u:-

4....~.

t,

[,

s.

Obtain the stack gas monitor reading for RIA-2326 froe chart l

'r recorder RR-2325 located behind the C-11A pasel in the Control i

i

/

Room. If unavailable, obtain the reading for RIA-2327 from chart

[

recorder RR-2327. Record on worksheet, itse (A).

Circle U

~

appropriate units and asek which monitor was used to provide the t c, - '

~ data.

C

(;

ii

.. e y..

k,

~.

.c

b.. Obtata the background reading from the same recorder used above, i

Record background on worksheet iten (B) circle the appropriate L

~.c unita.

e.

Obtais a net stack monitor reading by subtracting stack monitor background (B) frons current stack monitor reading (A).

Record on worksheet, item (C). Circle the appropriate units.

(

4 4.2 STACE FLOW RATE Obtata stack gas flow rate from the C-11A panel, located in the a.

Control Room on chart recorder FR-2318. Record on worksheet, ites (D).

If a reading is unavailable use 82,000 ft)/ min as a default value.

f 3

il b.

Convert f{cp g to a /see by multiplying stack gas flow rate (D)

{

by 4.72E 3

ft / min' E ', -

i oiO383-0028al%a-Ao

-.~,.:

q.

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E PALISADES NL' CLEAR P!.M1 Pru No El.o,g.

EMERCENCY IMPLE.% gATION PP.0CEDL*RE Reviston t Page.: at 3 T ;TI.E :

i:E:.I.ASE RATE DETERMINAT!CN FRGM STACK G',S P'.!it'W O

4 4.3 RELEASt. R.WE l

a.

Obtain the conversion factor as follows:

1.

For releases involving fuel sett or fuct fatture, obtain the conversion factor for RIA-2326, RIA-2327 f rom Attachment I or

• respectively using time af ter reactor shutdown as time post accident.

d 1

2.

For releases other than fuel melt or fuel f ailure use the l

following conversion factors:

,~'1 j RIA-2327 = 1.5E-2 RIA-2326 = 1.9 g 3 I

mR/hr q

Record conversion factor on workaheet, ites (F).

Circle the

-l appropriate units.

i I

b.

Calculate the noble gas release rate (QN) as follows:

QN (C1/see) e Net stack gas monitor reading (cpe) m

[

conversion facter (C dE*)*

r..

stsch gas flow rate

• C1 s

i J (g/e )

.t, o

r-N

.g jg h.

ll Record results on worksheet, item (G).

e

,.p

.y c.

Calculate the iodine release rate (QI) as follows:

-Ey QI = QN a (1.0E-3)

.-.. Ae Record results en worksheet, itse (3).

h 3.

Continue with mest procedure. Per EI-6.0.

{

~

L S.O RE!. EASE RATE DETERNINATION RIA-2318 /RIA-2319 (RACK 11p METHOD)

O E

S.1 STACE GAS MONITOR READING h.i V1 1

a.

Obtain the stack gas monitor reading from chart recorder RR-2300

[. i

- l located behind the C-11 panel in the Control Room. RIA-2318 as the preferred monitor. RIA-2319 should be used as a backup.

[g g

Record monitor reading on the worksheet, ites (A).

Mark which

[g monitor was used to provide the data.

b.

Obtain the background readtag f ree the same monitor taken at a r

time prior to t.he release. The default values for background are

j 1000 cpe for R!bt318 and 50 cpe for RIA-2319.

Record background

• [{

reading on worksheet ites (B).

{!

l

~

c.

Obtain a net count rate by subtracting stack monitor back-ground (B) from current stack monttor readius (A).

- i Record on worksheet, ites (C).

,5, e10383-00284154-89

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PALISADES NL' CLEAR PLANT Proc No El-6.1.

EMERGENCY I.*1PLEMENTATION PROCECL'RE Reviston 1 P.1ge 1 o r

.1 TITLE:

FILEASE RATE DETERMINATION FROM STACK CAS '!ONITCHS D

5.2 STACK FLOW RATE a.

Obtata stack gas flow rate feca the C-IIA panel, located in the Control Room on chart recorder Dt-2318.

Record on worksheet, 3

ites (D).

If a reading is unavailable, use 82.000 ft / min.is

.1 default value.

3 b.

Convert fjog3 g to m /see by multiplying stack gas flow rate (D) by 4.,2E w

ggj Record on worksheet, ites (E).

S.3 RELEASE RATE

~ i a.

Obtale the conversion factor as follows:

I

.a 1.

For releases involving fuel melt or fuel fatlure, obtain the conversion factor from Attachment 1, using time after reactor jj shutdows as the time poet accident, t.

2.

For releases other than fuel melt or fuel failure use the i. - _ '..

[~'T,, ["'

following converson factors:

g ;, -

=.,

RfA-2318 = 6.1E-8 Ci/m3 Q..} ' ~

cpe

,{

RIA-2319 = 7.5E-7 C1/m3 7

T.

c; cys y.

., ~. _ _

7 9

Record conversion factor es worksheet, ites (F).

I c.-

b.

Calculate the noble gas release rate (QN) as follows:

' $~

~

~ qW (C1/sec) = 5et stack gas monitor reading (cpe) x

~

' - 3..

j.

stackgasflowrateh C

conversion factor a

CP" Record results on workabeet, ites (G).

I' c.

Calculate the iodine release rate (QI) as foltows:

Q1 a QW x (1.0E-3)

Record results on worksheet, ites (NJ.

Coatisme with neat procedure, per El-6.0.

1 6.0 ATTACMMENTS 1

l

^. "St.ek Cas Monitor Conversica Factor, N! A-2.120" i

~. " Stack Gas Monator Conversion Factor. R!\\-2!27"

<. ** Stack Gas Mons ter Conversion Factor. RIA-21181RIA-li:'F I

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I et0383-00284154-89

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PALISADES NUCLEAR P!.AST EMERCE.fCY IMPEENENTATION PROI'EDt'u'

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Revtsion and Approval Sumary TITLE: C0!CfUNICATIONS AND NOTIFICATIONS 1.

Prepared 2.

QA Concurrence KG/LM s-12-r2 WA Originat'or &

Date Date r

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PALISADES NUCLEAR PLANT Proc No El-3 FMERGENCY IMPLEMI.NTATION PROCEDURE Revar.non e 1

'i T.TLE.

COMMUNICATIONS AND NOT!TICATir 'iS P.'s RP i O

Tabic _of Contents i

P i.ce 1.0 PERSONNEL RESPONSIBILITY,

1 2.0 PURPOSE s

1 3.0 INITIAL CONDITIONS AND/OR P. EQUI' 2NTS..............

1 4.0 COPCfUNICATIONS AND NOTIFICATIONS.................

1 4.1 ONSITE NOTIFICATIONS.......................

1 4.2 OFFSITE NOTIFICATIONS......................

2 4.2.1 Power Controller /' Ceneral Office Control Center /Emergenc Facility, Sta te. County and Imc............ y Opera t ions 2

4.2.2 Hospital Notification......................

2 4.2.3 Messate Authentication.

2 4.3 DOCIRfENTATION OF NOTIFICATION 3

5.0 ATTAC10ENTS 3

i-Ar.t % ts, " Emergency Notification Form"

-. " Hospital Notification Form". " Communications Matrix", " Emergency call List"

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PA!!SADES NLCLEAR PLANT Prm

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COTfUNICATIONS AND NOTIFICATIONS I

r P

l.0 PERSONNEL RESPONSIBILITY, C

h a.

The Site Emergency Director (SED) shall.nssure offsite r

notifications are performed per El-2.1 and unsste notaticattuns f

are performed per this procedure.

l k

b.

Upon activation of the Technical Support Center (TSC), the Communicator (described in EI-4.1) shall perform the.totifications 4

requiring regular updates, including Power Controller /Gener.s1 rj Office Control Center / Emergency Operations Factlity, St. ate. County

[

and Nuclear Regulatory Commission. Prior to activation of the ej TSC, the SED shall delegate this function.

[

)

2.0 PURPOSE g

To provide for emergency coansunications to onsite personnel.and offsite agencies.

l y

3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS Cm h

a.

Initial notification shall be made at Unusual Event.

Followup 3

notification shall be saade as conditions warrant or the emergency e

escalates.

{A t

)f b.

Alert and above followup notifications shall be made at approximately 15 minute intervals.

4.0 COPtfUNICATIONS AND NOTIFICATIONS B

4.1 ONSITE NOTIFICATIONS j

v s.

The emergency stren shall be sounded at the Alert, Site Area W

Eacrgency or General Emers:ncy. When possible a public address

[

announcement should be made prior to sounding the siren (see pd Section c below.

dil b.

The emergency siren shall be a continuous two minute blast.

M f&

The Plant Public Address System should be used to notify Plant-p c.

personnel of the emergency classification, location, and nature of

[';

the emergency.

{

C:

d.

Additional information shall be provided to Pl ant personnel over g

the Public Address System as conditions warrant or tt e-emergency

' i-escalstem.

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PALISADES NUCLEAR PLA.17 1*rce No ri-,

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l F..'fERGENCY IMPLEMENTATf0N PROCED*RE Rev a:. ion n P.s ce ' ut 3 TITLE:

COM*.4! CATIONS AND NOTIFICATICN3 h

4.2 OFFSITE Nor!FICATIONS 4.2.1 Power dontroller/Ceneral Of fice Cant rol Center 'E ner:yney_ppLry,tj ws Facility, State, County and NRP a.

The Commmunteator shall use Attactueent I to provide notificattnn to above listed agencies as required in initial Condittoos and/or Requirements.

b.

Information to co.plete Attachment I raay be obtained from TSC s

Status Boards.

j c.

Notifications to the State, County and NEC should be cuaned over y

to the General Office Control Center or Emergency Operations t

Facility a.; soon as possible.

n'j d.

A final call should be made to all agenetes before notitication 3

turn over is. completed to clearly establish the new point of E

contact.

t 4.2.2 Hospital Notification T

s A

Notification of hospitals receiving contaminated injured victims should be performed using Attachment 2, " Hospital Notification Form".

4.2.3 Measame'Authe'ntication In th'e event commercial telephones are used to send or receive a.

emergency notifications, the following method may be used to ensure the authetticity of a message.

-j f

b.

Message authenticatan should be performed in the to11nwing cases:

1.

The validity of the message is in doubt.

2.

The identity of the callec is in Joubt.

{

3.

The message requires extreme or unusual action (for example, I

public evacuation).

4.

At the option of the SED, Communicator, or offstte contact.

c.

Message authentication by the Palisades Sta f f shall be performed by informing the offsite caller that you will return the call.

Return the call ustna the telephone naaber listed in r!-2.1 or EI-3.

Re-establish contact with the original caller.

d.

Message authentication by ofisite organizations shall be perf ormed at their request.

Request that the organization return the call using the Palisades Plant telephone ceamber listed in their

mergency plan, procedure or call list. After contact is re-established, re-transmat the message.

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PAL!SADES NLTLEAR PL\\NT l' sac L L[ a L'tF9CF..N.C..Y..IM.PLEME..TA. TI.O. N PROCf.r,17E F v - ; c,n e,

'.4.* P I *i l TITLE:

COMML'ilCAT IONS \\ND h0 tit :( A * :. V f

a l

..s DOCl4 NTATICN of NOTIFICAT!nN Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of completion of Attactment 1 or 2, these f.,im 4.

should be forwarded to Plant Ltcensang to verif. t h.i t requ i re.1 notifications have been made.

l t

i b.

The Attachments shall be forwarded to Paltsades Document Control and Retained for 5 years.

l 5.0 ATTACletENTS 5.1, "Emargency Notification Form" 5.2, " Hospital Notification Form" f

5.3, " Communications Matrix" 5.4 Attachwnt 4., "Ehrgency Call Lis t" l

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NA.'!E/ TITLE /Tt.LEPHONE a P! ANT CO:MCNICATtiR.

2.

LOCATION - PALISADES PLANT 1

1 A.

Message &

Date:

Ttme:

B.

Control Room C.

Teshnical Support Center._

3.

THIS IS IS NOT A DR!!.L OR EXiRCISE (CHECK ONL) 4.

CLASS OF EMERGENCY (check one)

A.

Time declared D.

Site Area 8.

Unusual Event E.

General C.

Alert 5.

DESCRIPTION OF EVENT; CHANGE 0.? STATUS:

L b*

6.

PROGNOSIS (CHECK ONE)

A.

Stable C.

De-Escalatinx

~, _ '

B.

Escalating D.

Terminating r

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PLANT EMERGENCY RESPONSE ACTIONS UNDERWAY (CHECK) 7.

i A.

Offsite assistance previously requested:

Yes No C.

Police E.

Hospital f[

B.

Fire D.

Ambulance F.

Other 11 G.

Site Evacuation:

Yes No I.am s t ed i}

li H.

Onsite Monitoring Teams D :; patched: _

Yes No Offsite Monitoring Teams Dispatcheit:

Yes N o, _,.,

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A.

nA*. i o!Jn,i..".L 1:f.l.LAs!. 's17 4 A.

Pn t en t s.a ! for trie ne H.

Actu.il Release:

C.

Time of Helease.._.- _

D.

Aarborne __ __.

E.

Waterburne _.

l'.

Surisee Spa 11 G.

Potenttal Release _ _.,Itu r.s t a n.

h e i. r :.

s t... - t 9.

METEOROLOGICAL, DATA A.

Stability Class _ _ __ _,,.,_,_

alm Based on AT" (*C) or 8.

Wind Speed, mph

. tun.

t.r t. i. :r g r e e :. '

C.

Wind Direction, degrees (trom)

D.

Downwind Sector:

10.

OFTSITE DOSE RADIOLOGICAL REI. EASE DATA

~

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A.

Estimated Measured (check onel 8 ],,.

B.

Effluent Point:

~

C.

Noble Gas Release Rate, Ci/See:

D.

Average Energency per Disintegratton, E, MeV:

E.

Equivalent I-131 Release Rate, Ci/sec:

F.

Potential Release Duration, hours:

11.

CALCUTATED OFFSITE DOSE Site Boundary A.

Distance, miles

.5 2

5 10 8.

Whole Body Gamma Dose Rate, ree/hr j

C.

Whole Body Gasuna Dose, ree D.

Child Thyroid Dose Rate, ree/hr E.

Child Thyroid Dose, rem F.

Additional Data:

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E'iF.K r r.s ND T ! F. C a !! ON 5 '91'*!

12 PROTECTI\\ E ACTION RECtti.'1ENDAT IONg Seetor(sJ

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A.

None B.

Shelterang Precauttonary Lvacuatir,n D.

Evacuation E.

Coatsannation Control F.

Food G.

k'ater

{

i H.

Milk I.

Other 13.

RE!tARKS / ADD I T I ON AL I NFOR.*iAT I ON :

l 14.

THIS IS IS NOT A DRILL / EXERCISE (CIIECK ONE) u t

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i 5 i Proc No El-3 4tt.ach.w nt 2 Revicten 6 l' r.;e i 1: :

D HOS;PI,TAL NOTIFICATibN FORM 1.

Comununica to r A.

Name:

B.

Title:

C.

Telephone Number:

2.

Location: Palisades Plant 3.

Number of victims:

r 4.

Nethod of transport:

Estimated time of ir, rival:

5.

Extent of injuries:

t;- :.

Q.

f-;.

y ':. ~: "

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6.

First aid and/or decontamination procedures initiated:

7

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Contamination levels:

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Offsite Monitoring D

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A*.B. A*.B.

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Control Room E

4 p.

A - Dedicated telephones l

B = Cor...cre tal telephone i

C = Intraplant telephones D = Radio E = Tacc-to-face F = Intercom C = Sound powered telep! Cs H = PA System oiC583-00lle-93-154

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E.T.RGENCY Calf I.IST Medical Memorial llospital St Joseph 983-83do Mercy Hospital, Benton Harbor 927-5242 cr 927-52.I South flaven Community Hospital 637-271 Dale K Morgan, MD, South Haven 637-3609 David B Witte, MD, South Haven 637-3528

~

Local Response City of South Haven 637-5211 (day)

Board of Public 11tilities 637-5151 (night)

State Response Michigan State ' olice 517-373-0617 P

Emergency Services Division, Lansing

$17-337-6100 517-332-2521

~

Michigan State Water Toll Free 800-292-4706 Resources Commission 517-373-7660

. a i

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Indissa CiviltDefense 317-232-3830 (day)

-- /

r Indiana State Police 317-232-8250 (night) 7,,

FederalRespoejs Department of Energy 312-972-4800 (day)

Radiological Assistance Program 312-972-5731 (night) fasurers American Nuclear Insurers 203-677-7305 (day) 203-677-7715 (night)

Nuclear Nutual Limited 809-295-3278 l

Insurers l

l Techeical Support i

l Institute of Nuclear 404-953-0904 l

Power Operations (emergency response) 404-953-3600

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(normal use)

RENs Radiation Emergency Management 505-2.43-0236 Services - Nedteal Consultant 505-848-6024 (.i ge r )

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Revision 1 D.a t e pal.!SADES NUCLEAR PLANT 9fERGENCY,1.1PLE.1ENTAT10N PROCEUl'*tE Revision anil Approva! Surn.iry TIT LE:

OFFS!TE L35E CALCULATION AND RECO.1E?.DArloNS FOR PROTECTIVE ACTIONS 1.

Prepared 2.

QA Concurrence a a D.%

s -xs-n N.A.

Date Originato #

Date E

j, 30 d Approval /Q-List No 4.

PRC Reviewed f f' ]INI Y bi 53 2//4%eA

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' / K G ;'3./ A Date ppnt Head

'Date f

4 5.

Approved 6.

ATMS Incorporated I 27 &3 J #f f3 Plant rianager Date Date 7.

Biennial Review Date

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D ciO383-0027el54-gg 1

l

W P me No F.1-0.0 PAMSADES NL'CLEp_ PLANT EMERGENCY !".PLC'tENTATION PROCEDURE Revision 1 Page i TITLE:

OFFSITE DO5E CALCULATICN AND REC 0",MLNDATICNS FOR PHOTEC1*VE ACTIONS f

f Table of Contents 1

I k

1.0 PERSONNEL RESPONSIBILITY.

E I

A 2.0 PURPOSE E

1 3.0 INITIAL CONDI*' IONS AhD/OR REQUIREME.rS.

Y h;

I 4.0 PROCEDURE 1

3 4.1 DVERVIEW.

I l) 4.2 RELEASE RATE.

9-2

,tl 4.3 AVERAGE GAMMA ENERGY (E) n 2

):

4.4 METEOROLOGICAL DATA s.

2 E

4.5 CALCULATIONAL METHODS fl 3

4.6 OETSITE 190NITORING........................

q P'

3 W:

A.7 OETSITE PROTECTIVE ACTIONS.

.. a 3

4.8 COMPLETION OF REQUIRED CALCULATIONS

7..

3

' S.0 ATTACHMENTS p

P-ATTM'.XIENTS 41 w

a1, "Offsite Dose Worksheet" p

C a::Wn,

g#.'

t.c6r.

E.

t.

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lI PALISADES NL' CLEAR Pl. ANT E ' " ' I I '

• h ", ','. * *; " "t. s I

EMERGENCY IMPLEMENTATION PROCEDURE pe I

flTLE.

oH SITL DOSE CALCULATICN AND RECCW A ' H '

I"h PROTECTI\\T. ACTIONS 1.0 PERSONNEL RESPONSIBILITY The Chemsstry/ Health Physics Support Group Leader shall tepicment this procedure.

In the absence of a Chemtstry/ Health Phystes Support Group Lea de r, the Site Emergency Director shall delegate this function.

2.0 PURPOSE To determine the appropriate steps required to calculate otfsite dose and recommend offsite protective actions.

3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS This procedure shall be implemented when there is a potential for, or an actual sinnificant release of radioactive materials from the Plant site, per El-2.1..

4.0 PROCEDURE 4.1 OVERVIEW All procedures in Emergency Implementation Procedures, Sec-a.

tion El-6 are for calculation of offsite dose and making recommendations for offsite protective actions. Not all procedures in this section are applicable to all release ca tegories. The following paragraphs will direct the user to the appropriate procedures to complete this task.

i b.

Use Attachment 1 of this procedure, (Offsite Dose Worksheet), when j

completing this procedure. Mark the blank in the left margin of I

the worksheet to designate which procedures should be performed, l

per the following paragraphs.

j l

4.2 RELEASE RATE

(

This section selects the appropriate procedure to determine a release

[

l

[]

rate (CL/sec) for input into the Offsite Dose calculation.

1.

4.2.1 If the release is occuring through the Plant stack, the release rate I

should be determined in EI-6.1.

Mark Section 1.1 on the worksheet if l

this paragraph applies to the release.

d

!l l

l 4.2.2 If the release is occuring through the steam dump, the release rate should be determined in EI-6.2.

Mark Section I.2 on the worksheet if this paragraph applies to the release.

,i il l

l 4.2.3 If the release is occuring through the stack or steam dump and th.a stack monitors or main steam line gamma monitors respecttwely, are not functional, the retcase rate should lie' determined in El-6.3.

Mark e

Section 1.3 on the worksheet af this paragraph appites to the release.

I ei0383-0027al54-69 b e

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the. osst a n eo ent t.. a t d.,+

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Po t e t.L i d l for rele4=c or en 4.tua el a.c tenenx pa4.c. i rir

,,s.-,

sate should be alculated an L1-8, *, u.ang ( i.e te n sh r e se r...n t..a,,. i ma,nitors.

Mark sectson 1.4 un the

.o r k a s.c e t at t h i s p e r g i ai.h

..s p.

1 t o t he (potent 3al) release.

4. 2. 's If the results from Post-Accadent Laplisex (El-11 are v

aule.

constra4t'en of potent:41 or actual re t c.e se rates from the. unt. a s-es t butidkag er the Primary Coolant Systete may be determanca su El-t, Tham procedura may serve es A bac kup for El-b. 3 in the case of a contalasneat hwalding re!asse, as tame permats.

I mp l eme n t. t s.,n.. : t s. a s procedure should not delay completton of off=nte Dome Caltui.ts.nn.

Mark Sectles !.5 of the worksheet af the above cc.n.1 a t s on=. e si.e t t.a the use of Post-Acesdent Sampians input.

4,3 AVENAGE GAF,,14 ENEA4Y (E)

E!*6,6 sh411 be used to determine the average games 4 energy per disintegratios 44 be used for Of f sate Dose calculations.

Set t iosa 11.1 is already marked on the work 4heet, 4,4 METEOR 01.06! CAL DATA This secties selects the primary and backup methods of obt4aninic meteorelesical dets, includios wind speed, wtad direct. ton nd g

stability stess, 4,4,1 If the site meteorological station is functioning, current scather emeditions should be datessiend in Ele 6.7.

Mark section 111.1 on the workshatt 4( erisite meteorolostcal data is available.

4,4,2 Backup meteore!.sical dets and weather forecasts 4re obt.saned in 25 6,$,

The batkup systes should be used when the ousate ty.tes

=

set SWeilable, Weather ferocests may be used to antlesp4Le chunging s

conditione, forecasts shogl4 be made only if staffing and time Permits, Mark Section !!!,2 on the worksheet if b4ckup a.eteorology is

used, 4,$

CA!.CULATIOWAL PtETHOD5 This sect &on describes the method (s) whtch should be use.1 to teliu! te offaite dose, 4,5.1 The str41sht-line Gausst aa method described in El-c. 's should be used LO determane ofisste done, Thss methol reguares a p re p e o g r.saeu.i l

dewistt-Parkerd 48 hv cateu!4 tor Inormally stose8 *tth f et hn a. 41 Support Center emergency equapsent).

This aetho.8 16 e n. p r ee ce.t w a r.

the Late metho.1 and thould be the primary one.1.,ntal t he. le t.44 41 l

tupport Center 6.

stalled. tie r k 3eatsun l'.'.I us the t.o s k = f.c e i s at

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PALISADES NUCLEAR PLANT Froc No El-o.o EMERCENCY IMPLEMENTATION PROCEDURE Revtaton 1 1.ine 3 et !

TITLE: OFFSITE DOSE CALCUL\\ TION AND Recon 1sDATloNS FOR PROTFCTI\\T. ACTIONS 4.5.2 If a pre-progransned Hewlett-Packard 41 CV is not available, r:1-6.10 should be used to determine offsite dose.

The methodology and results are essent. ally identical to those in EI-6.9, but no calculator is requtred.

Mark Section IV.2 on the worksheet it the backup method is used.

4.5.3 Segmented Caussian Method. EI-6.ll - to be developed.

4.6 0FFSITE 210NITORING EI-6.12 compares offsite monitoring results (EI-9), to Offstte Dose calculatiocs eade in this section. This comparison should be made as data becomes available and time permits. Mark section V.1 on the l

worksheet if the above conditions are met, 4.7 OITSITE PROTECTIVE ACTIONS EI-6.13 shall be used to determine. recommendations for offsite l

protective actions.Section VI.1 is already marked on the worksheet.

j i

' ' EA COMPLETION OF REQUIRED CALCULATIONS 1

Initiate the.first procedure as identified on th6 worksheet.

Proceed p

to the next procedure identified on the worksheet upon completion of r

the firrt. Omit unmarked sections of the worksheet.

1 5.0 ATTACHMENTS

?, "Offsite Dose Worksheet" 6.

h P

i b

(:.-

fi:

r C.

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'1 i

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ciO383-00274154-89 e

Pr. '..

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QQ.51,TE DOSF. WORK.c!!EET h

I Release Rate from Stack t.as 4 nitors

( ) Section 1.1, Reference EI-6.1. Release Rate Determinat ion

=

cpm (A)

• S.tIA-2113 ( )

1.

Current stack gas monitor reading (circle units) mR/hr "RIA-2319 ( l l

• • R I A-2 3 26 ( )

• • RIA-2327 ( )

cpm (B) 2.

Stack monitor background reading

=

(circle uutts) mR/hr cpm (C)

=

3.

Net stack reading (circle units) mR/hr 3/ min (D)

=

(t 4.

Stack gas flow rate i

5. ~ Stack saa flow rate

'3 ***

3 m /sec (E) 3

=

(D) ft / min x 4.7{E-4 Ita/ain o

i i

Ci/m3 t

Caaversion factor =

(F)

(circle units) 3 C m mR/br i

7.

QN, Noble gas release rate =

Ci/sec (G)

(C) x (E) x (F)

=

Ci/sec (H) 3.

QT, Iodine release rate = (G) x (1.0E-3)

=

Date:

Time:

Completed By:

l et0383-0027bl54-89

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hev:

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.c ot ti CFFSITE DOSE WORXFl[EET f

i Sec t t on 1. 2, Re f e r ence El-6. 2, Re le,sse l<a te C-te rmin.it s-

te' Monitors.

. Steam Dump Start Date (A)

Time (B)

Stsas Line Monitor Reading

=

net epm (C)

A S/C, **RIA-2324 Staae Line Monitor Reading

=

net epe (D) j B S/G, **RIA-2323 i

QN, noble gas release rate A S/G =

Ci/see (E)

A(C) x (1.7 x 3E-2)

=

QN, noble gas release rate B S/G =

B(D) x (17.3E-2)

Ci/see (F)

=

s l

1 l

=

i.QN, noble gas release rate

~ if release is from one S/G QN = (E) or (F) =

i

[ if release is from both S/G Ci/see (G)

QN = (E) + (F)

=

2 0

l N

s

$ QI, 1-131 dose equivalent release rate =

)

Ci/see (H)

(G) x (1.0E-3)

=

t I

O F

.t m Time:

Compteted By:

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Reviston i P a ct-1 of 15 0FFSITE DOSE kORKSifEE T O

CGNFIRMATION

( -)

Section !.2. Reference El-o.2, Release Rate Determination from Stearr Linc.'!3nstors.

1..

Lite:

Time:

~

2.

Steam Dump Start Date:

Time:

T 3.

T,,s 4.

PCP oa? Yes:

No:

S.

Secondary Pressure psia 6.

Fully open Dump Valve Saturated Steam Flow Rate cc/sec

.,. 7.

T,,,_ error n. _.

T 4.

Traction Valve Open N:gbc,

[ g,. Actus! Steam Flow Rate from one Dump Valve ec/see f

). S/G A dumps open? Yes:

No:

"; i.11.

• • RIA-2324 reading cpe

.a..

E: '712. S/G A Total Radionuclide Concentration

'pci/cc 7~ ~13.

S/G A Radionuclide Release Rate pCi/sec

14. S/G A Noble Gas Release Rate pCi/sec j.,,, }g, _

g/G A Radioiodine Release Rate pCi/sec

- 15'.

S/G B dumps open? Yes:

No:

}

16.

• • RIA-2323 reading eps 17.

S/G B Total Radionuclide Coccentration pCi/cc 18.

S/G B Radionuclide Release Rate pCi/see 19.

S/G B Noble Gas Release Rate pCi/sec 4

S/G 8 Radiciodine Release Rate pCi/sec 1

20.

Bypass Valve Open? Yes:

No:

O oiO383-0027bl$.'.-89 l

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re,

a, :.

Er,ts:

Pa re. -

<FFS!_TE DOSE _ WORKSIEET CONFIRMATION 21.

S/G A MSIVs open? Yes:

No:

i S/G B MSIVs open? Yes:

No:

~22.

Bypass Valve Noble Gas' Release Rate pCi/sec

~

..L' 5 / S"C 23.

QN =

Ct/sce gg a 24.

S/G A T F

old

• F S/G B T,,gg

25. S/G A Pressure psta S/G B Pressure psia p.26..FullyOpenDumpValveFlowRates:

1-S/G A cc/sec lg-1:-

1 5/G B cc/sec O

27. T error avs 28.

Traction Valve Open i

29.

S/G A Actual Steam Flow Rate ec/sec S/G B Actual Steam Flow Rate ce/sec Date:

Time:

Completed By:

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'h"....-

1.

High ran;;e ef fiti-nt monitor raadtng mh.'hr IA)

High range effluent monitor,

( ) stacii

( ) steam.tump

=

R/hr 18 2.

High range ef fluent raonttor reading = (A) x (I.0E-3) 3.

Response factor s

(C) 4.

Corrected monit:r reading.= (B) x (C) =

R/hr iD) r i; -5.

Elapsed L a ft h reactor shutdown to.

Ch ' -

monitor reading =

hours, days (E)

(circle one)

[.

Q:;iiti;. 2.

R/hr_

~~

Ci/see (F)

T '.-

Conversion factor g-from: Attachment 1()

$ ( )

'. ~ '. ~.' ( )

'c " ( )

e.

7.

QN, noble gas release rate = (D) + (F) =

Ci/sec (G) l 8.

QI, 1-131 dose equivalent release rate =

Ci/sec (H)

(G) x (1.0E-3)

=

t-1 Date:

Time:

Completed By:

OV ei0383-0027bl54-89

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h-H.in ge *:i'n a t airs.

Time p.a s. t shuteinwn =

hours (Ai 2.

Monitor niunber ( ) **RIA-2321 (3)

( ) 6 k!A-2322 3.

Monttor reading =

__ R/hr (C) pct /c_c 4.

Noble gas conversion factor =

R/hr 5.

Leak rate =

ce/sec (E)

', l6.

QW, noble gas release rate =

=

Ct/scs (F)

(C) x (D) x (E) x (1.0E-6) 1-1 7.

QI, I-131 dose equivalent release rate =

Ct/sec (G)

(T) x (1.0E-3)

=

.=

Date:

Time:

Completed By:

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G.im. i. 5 termi-.

(x)

!! 1, Reference El-6.6 1.

Decay time

_ hours (A) i F' 2.

Source of release ( ) Fuel Melt-or Fuel Failure

( ) Maan Steam or Oligas (Atr Ejet.to ) R e t. i :.. -

( ) Surge Tank Volume Control Tank.. inst D m itic: He le.. -

() Waste Gas Decay Tank Reic.ises

() Fuel Handling, Sapping anil L.ask Urop Rele.ises t

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Date:

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Completed By:

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,g t FFS UE DOSE. '-19KSMFE T O

!!! Meteoroluxital Data

()

111.1. Reference El-6.7. Plant Sate Meteorotosteal Systre i

~

l 1.

WS. Wind Speed =

apt. (A) () 10 se t e rs

( ) 60 meters, corrected

~

'., ; 2.

18. Wind Direction =

• froe (B) ( ) 10 meters

( ) 60 meters 3.

6010 DELT =

(C) preferred

~.

og i,,-c.

4.,..,

..r-i

}.

(() 10 4 SGMA =

(C) alternate z

c.

.~

?

m......( ) 60-M SGMA =

I _N3.,.

Ag i-1

.4.

Stability Class =

(D) i Time:

Completed By:

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Proc h El-o..-

A t t a c ts.. nt 1 j

Revision 1 J

P. ige-10 o f 15 OFJSITE DOSE koRKSitEET

( )

!!1.2, Reference El-6.8. Backup and Supplemental tieteorslogy.

I.

Wind direction s

• Frw (A) 2.

Wind speed 3 knots (B) r

{

t j

3.

Wind speed = (B) x (1.15) oph/ knot =

mph (C)

I 1

+ii g

! 4. _ Fasquill Stability Class =

(D) ni8 t time or cloudy = E default for stability class:

h

,. y,. a day time and clear

=D g..

t a.

e -:

O Dates

~

Time:

Completed By:

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OFFSITE D'6_Ejl!F1S!!EF'.'

O UFFS!;r, DOSE CALCiLA!!ic.

IV

()

IV.1, Reference El-6.9 Calculation of Offstte Dose - Straight Line Gaussias.

(Calculator Method) t i

Required Calculations Optional Calculatione i

Distance from Plant Site l

Boun-da ry l.

.5 mi 2 at 5 mt 10 mt F

1.

Child thyroid dose rate, meen/hr

=,

(A)

I t

3 (B) 2.

I-131 Dose equivalent cone, Ci/m

=

l }

• 3.

l Finite cloud whole body (C) e

.. dose rate, mees /hr

=

E.

~4.

Estimated release duration =

hrs (D)

Note:

default is two hours.

0-7:

~

Pt;-

5.

Child Thyroid dose, area =

['

-(A) x (D)

=

(E) r.g, u

b i.

6.

Finite Cloud Whole Body E

(F) h?

dose, area = (C) x (D)

=

f 7.

Above doses are based on actual / potential (circle one) releases.

(G)

Date:

Time:

Cempleted By:

~

e iO 353-0027ta l 54-69

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d'FF S!.F. D07 wrsKsifEET

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'i..

i

( )

IV. 2, Re f ea r cen e f. ! - ti. ; 0

• s ; t s s t e-D.. s e.

t.s t c u l.i t :

c. - s t.i..

Rer;u a red C s h u l.it t. ur-

";'t a. a. !

a:mita acen Site Boun-d ry

.5 m 2 ma 5 mi 10 mi

(\\-

Ca (mphl I")

1.

xp/Q 3 Ci/sec m

2.

x/Q (sec/m3) =

(C)

(B) + wind speed (mph)'

=

3.

Semi-infinite cloud wholt dose rate (ares /hr) =

(D)

(C) x (QN) x (E) x (9.0E+5)

=

fE) 4.

Finite cloud correction factor

=

. 5.

Finite cloud whole body dose rate (ares /hr =

(F)

(D) + (E)

=

(G)

'T 6$

Estimated release duration (hours) s O

7.

Finite Cloud Whole body dose commitment (ares) =

(H)

=

(F) x (G)

S.

1-131 dose equivalent concentration (1)

(C1/ms = (QI) x (C)

=

9.

Child thyroid dose rate (ares /hr) =

(J)

=

(1) x (1.85E9)

(area) =

10.lChildthyroiddosecommatment (J) x (G)

(K) i n

11.

Above doses based on actual /potentral seiscle one) releases. (L) t m_

l Date:

Time:

Completeil By:

O l

c 0'383-0027bl54-149

\\

of : S ! TF. DOSF bkKSHEE!

I

- t ' Rt.N C F. !. I - t, 11 s

(To be included later)

E t

'I i

I d

t1 P

k

• te l

L.

i k-i ke' i

Q 1-k<f.

l i

40383-0027bl54-89 t,j

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=_

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.-- _ _ _. mm -

.__.m,._

1 P r.. m t.:-3

• *a.

,ent t 5-vi,..i ;

P.i. i. !

c-OfTSITE Of'NI. ' ORVWEE' V Offstte Monitoring

()

V.1, Reference EI-6.12 Compartson of Of f site Monitoring with of f s, te Dose Calculations Site Distanc- =

boun-dary

.5 mi 2 m:

5m 10 mt 1.

Offsite Monitertag Data (A)

Whole Body dose rate (mres/hr)

=

(R) y I-131 dose equivalent conc (pCi/cc) =

t-

{.-

g,,2.

Flume direction a degrees to (C) y I-' ' 3. - Offsite Dose Calculations f.:r,.

l...

. Finite Cloud Whole Body (D) dose rate (ares /hrf

=

h-r a

0 I-131 dose equivalent g

[..,

come (pci/cc)

(E)

=

1-E.'

4.

Wind direction =

degrees from (F) j

Wlad direction =

degrees to (G) 5.

Data Comparison p.

(A) - (D)

_ (H)

=

(I)

(3) - (E)

=

If (R) or (I) > 0, circle in red.

I

}

(J)

(D) + (A)

=

(K) l (E) + (M)

=

I If (J) or (K) > 2.0, circle in red.

[(C) - (G)] =

degrees (L)

If (L) > 10*. circle in red.

D l

l Date:

Time:

Completeil By:

9 ciO383-0027bl54-89

~

1 PALISADES NUCLEAR PLANT Proc No EI-7.0 EMERGENCY IMPLEMENTING PROCEDURE Revision 0 Page i TITLE: EMERGENCY POST ACCIDENT SAMPLING Table of Contents Pase l '. 0 PERSONNEL RESPONSIBILITY,

1 2.0 PURPOSE I

t 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS.

1 J

4.0 EMERGENCY POST ACCIDENT SAMPLING.

1 5.0 ATTACHMENTS 1

k b

1 s

't r

1 g:

3

' \\

eiO683-0013bl54-89' f

'N 4

t '

,_,e 4 g

'd.-e 4

1. 4".

5m. f/-

• 41 --'

a

- r

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,c.

Pry No El-ti.0

.. qc.

'L y :' f r.' :....

E WGtKSHEET, ' ', -

C;;.

og/g.

. 'OFFSITE,,

4 i tusent I

{

R seen !

s VP~ Protective lActicas l' age l's of l'.

, g' (x) VI.1, Reference El-6.13, Protective' Action Recommendation for Offsite Population RECOHHENDE0' PROTECTIVE ACT1041$ TO REDUCE WOLE BODY AND T TO OITSITE POPUIAT1018 FROH EXPOSURE TO A GASEOUS PLliME 1-Basis Heroncnended ( A) Affected* for (C)

I' rot ca t ive Sectors Protective Projected Dose (Rem)

Recosciended Actions (a)

___ Comssen,t s,

A(Lion (B)

Actions to the Populataan

'Wo required protective actions (b) Previously res..reuen.tc.I W olebody.< 0.5 State esy issue an advisory protective astnon. o.ay f

be reconsidere.t...

to seek shelter and await Thyroid < 5 terminat d.

f further instructions.

I Monitor environmentat radiation levels.

If constraents exist, W olebody 0.5 to < 5 Seek shelter as a minimum.

Consider evacuation. Evacuate special iunssiteratson should bc xiven sur Thyroid 5 to < 25 unless constraints make it impractical. ifoni t or ev.acuation of tii l Iren environmental radiation

.ind pregn. int women.

levels. Cont rol access.

Wolebody 5 and above Conduct mandatory evacuation.

Seeking sheltes tout.1 be an alternatisc it Monitor environmental radia-tion levels and adjust area for evatuation scic n,. t

~~

' ~~._ [

Thyroid 25 and above immeliately po:.:. i ta l e.

mandatory evacu.ition based on these levels. Cont rol.n cess, iake Protective action decisions at the tinc of the i ni i.icn t m.c.

i.)'ihese.(-tcons are recommenfed for planning purposes.

casi:.t ineg condit ions into consideratioc, the tis 9e of the incident, state officials may ampicament low-impact protective actions in keeping witti th peen. spic of i

sh)Atmaint.sining radi. ti.m exposures as low as reasonably achievabic.

l r.stes are based on actual / potential (circle one) releases.

(D) l l

'these dose

oll.

Include the.irca within two miles of the plant (all sectors) in any recommended.srtions.

Date Time l

1 Comp l e t c.l lly :

Nevieweil ity :

Si t e,1:n.ci gency Di rec t or :,. _ _,,, _

i

PALISADES NUCLEAR PLANT Proc No EI-7.0 EMERGENCY IMPLEMENTING PROCEDURE Revis, ion 0 Page 1 of 1 TITLE: EMERGENCY POST ACCIDENT SAMPLING 1.0 PERSONNEL RESPONSIBILITY The Chemistry / Health Physics Group Leader shall implement this procedure. In the absence of a Chemistry / Health Physics Group Leader, the Site Emergency Director shall delegate this responsibility.

2.0 PURPOSE To provide the ability to take post accident samples of the Primary Coolant System, the containment atmosphere, and stack effluent.

3.0 INITIAL CONDITIONS AND/OR REQUIRElfENTS This procedure shall be implemented per EI-2.1, " Emergency Actions / Notifications / Responsibilities".

4.0 EMERGENCY POST ACCIDENT SAMPLING Upon determination that a radioactive release is taking place a.

through the stack that may warrant the activation of the Site Emergency Plan, (Refer to EI-1), the Chemistry / Health Physics Group Leader shall procede to EI-7.10, " Post Accident Sampling, Radioactive Gaseous Effluent Monitor" and perform post accident sampling per that procedure.

b.

Upon determination that a release of radioactivity may be taking place from the fuel into the Primary Coolant System that may warrant the activation of the Site Emergency Plan, (refer to EI-1), the Chemistry / Health Physics Group Leader shall procede to EI-7.1, " Post Accident Sampling", and perform post accident sampling per that procedure.

c.

Upon determination that a release of radioactivity to containment that warrants activation of the Site Emergency Plan, (refer to EI-1), may have occured, the Chemistry / Health Physics Group Leader shall procede to EI-7.1, Post Accident Sampling" and perform post accident sampling per that procedure.

5.0 ATTACHME.TS Y

None

+

eiO683-0013a154-89 w

w

+

6

'rt-w g

r.-

Proc No EI-2.1 0

Revision 10 Date 6/29/83 PALISADES NUCLEAR PIANT EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Sumnary TITLE: EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES 1.

Prepared 2.

QA Concurrence e a D.+

s-n-n MA.

Originato(/

Date Date 3.

Reconus proval /Q-List No 4.

PRC Reviewed A WL hin zand as pa tnWat Head Date

-4/2/d4 'd' 7 '/4 ' Dat'e 5.

Approved 6.

ATMS Incorporated W%

t. 2:1 h irs

/-19-28 Plant Manager Date Date t

7.

Biennial Review l

Date l

~..

u eio780-0006d154-89 4

e

• 6 '* %

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o o.

P r u.-

%, L 1 ' -

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pal.!SADES NTCt. EAR !>L\\NT r.MELSENCY :P.Pt.h"E,T I NG PRt. '.cl hl Revne. ton anti.\\pp re.s 1.* t..n. r.

TITLE:

EMERGENCY pus T ACCIDENT SAMP'.!NG e

Prepared 2.

QA onruerence 1.

I, fa A -1_

__s-2 5 -n N. A.

?. ' '.,

Origina W Date Date

?

J'.

?-

z i

,4

{

^.3, Recohend proval /Q-List es No

'4.

PRC Reviewed 4

p.,

3 L.

J.U '.""

• *~~

I

, f),

ml }

i o

. _ t c' b t.

... ' C ',

+

' ';lL fr eat Mead Date

• 'p y.*; ';'

.x Date

'g :

. i ';.,

r af:,.'-

c i

5 Approved 6.

ATMS Incorporated

.' i

_L 3lf3

). 2f.f q

.'" [>

Piant Manager Date Date 1

7.

Biennial Review t

Date s.

G eiO683-Onl3c 154-89

PALISADES NUCLEAR PLANT Pr c Na EI-2.1 EMERGENCY IMPLEMENTATION PROCEDURE Revision 10 Page 1 TITLE: EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES Table of Contents Pagg 1

1.0 PERSONAL RESPONSIBILITIES 1

2.0 PURPOSE 3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS.

1 4.0 EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES.

1 I

4.1 EMERGENCY ACTIONS / NOTIFICATIONS 4.2 SITE EMERGENCY DIRECTOR RESPONSIBILITIES.

2 4.3 DOCUMENTATION OF. NOTIFICATIONS.

3 5.0 ATTACHMENTS 3

Attachments, Emergency Actions / Notifications 1

ei0780-0006c154-89

-w

_ ~.

h.

PALISADES NUCLEAR PLANT Pr:c Na EI 2.1 EMERGENCY IMPLEMENTING PROCEDURE Revision 10 Page 1.of 3 TITLE: EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES 1.0 PERSONAL RESPONSIBILITIES The Site Emergency Director (SED) shall implement this procedure.

2.0 PURPOSE 2.1 To provide the SED with a prepared course of action for each emergency identified in EI-1, Activation of the Site Emergency Plan / Emergency Classification..

2.2 To define the SEDs responsibilities in an emergency.

3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS This procedure shall be Laplemented after completion of EI-1.

4.0 EMERGENCY ACTIONS"/ NOTIFICATIONS / RESPONSIBILITIES 4.1 EMERGENCY ACTIONS / NOTIFICATIONS The SED shall delegate the Actions / Notifications identified in a.

EI-1 and marked on Attachment 1.

Normally assi*gned personnel / groups are identified in fourth column.

t b.

The assignee should note the category of action as marked in column 1.

1.

Mandatory Actions (M) - Actions that should be performed within one hour.

NOTE:

Initial notification to State and Local government should be performed f

within 15 minutes.

2.

Subsequent Actions (S) - Actions that should be performed in an expeditious manner as conditions, time and personnel permit.

3.

If Needed Actions (I) - Actions that are not required in every case, but may be needed.

The assignee shall note the frequency the action should be c.

performed in Column 5.

d.

Appropriate actions / notifications should be turned over upon activation of the General Office Control Center or Emergency Operations Facility. Note the time of turnover on Attachment I and notify the SED.

NOTE:

A line through the box for time of turnover indicates this action / notification may not be appropriate for turned,over to the GOCC/ EOF.

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TITLE: E"1HGLNCY ACTIONa/NOTIFICM10NS/ nr.S $S6M!.IT L 4.2 SITE EMERGENCY DIRECTOR RESPONSIBILITIES a.

In addition to the responsibtiities listed in Attachment I, the SED shall also perform or delegate those actions and responsibilities listed below.

1.

Command and control of the Technical Sunport Center and Operational Support Center.

Refer to El-4.1 and EI-4.2.

• 2.

Approve recommendations to state'and local agencies regarding protective actions for the public.

Refer to EI-6.

• 3.

Approve decisions regarding Site evacuation.

Ref er to El-13.

4.

Maintain a log of events and actions during the emergency and subsequent recovery.

5.

Request Federal assistance as necessary.

I 6.

Have PA announcements regarding emergency conditions made at

~

,j" regular intervals or when significant changes occur.

~~

7.

Limic personnel access to the site.

8.

Ensure on site first aid is performed and accident victims are h

i transported to hospitals as necessary.

Refer to EI-14.

• 9.

Authorization to exceed the 10CTR20. dose limits for emergency workers. The following guidelines should be used to establish emergency dose limits:

F O

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Proc No EI 2.1 PALISADES NUCLEAR PLANT Revision 10 EMERGENCY IMPLEMENTING PROCEDURE Page 3 of 3

'l EMERGENCY ACTIONS / NOTIFICATIONS / RESPONSIBILITIES TITLE:

t 4

1 Projected Dose (Rem) to Comments Emergency Team Workers Category a

Whole Body 25 Control exposure of Although respirators emergency team members and stable iodine should i

Thyroid 125 to these levels except be used where effective for lifesaving missions. to control dose to emer-(Appropriate controls gency team workers, thy-for emergency workers, roid dose may not be a include time limita-limiting factor for tions, respirators, and lifesaving missions.

stable iodine.)

Whole body 75 Control exposure of

. emergency team members Thyroid

(**)

performing lifesaving missions to this level.

(Control of time of ex-posure will be most effective.)

Protective action t

These actions are recommended for planning purposes.

decisions at the time of the incident must take into consideration the impact of existing constraints.

• • No specific upper limit is given for thyroid exposure since complete loss might be an acceptable penalty for a life saved.

4.3 DOCUMENTATION OF NOTIFICATIONS Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of completion of Attachment 1, this form should be a.

forwarded to Plant Licensing to verify that required notifications have been made.

The form shall be forwarded to Palisades Document Control and b.

retained for 5 years.

5.0 ATTACHMENTS, Emergency Actions / Notifications l

l

• Indicates a responsibility that shall not be delegated.

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EMERGENCY / ACTIONS / NOTIFICATIONS t

Turnover to I'

Action Type Normally COCC/ EOF H, S, or i

'heference/ Telephone No Assigned To Frequency (Time)

(From El-1)

Action / Notification 3

Notification of Duty and Duty Call List SED /Come Initially at Unusual Call Superintendent Event 2.

Perform Emergency Staff Contact Property Protection SED /Come Initially at Unusual Augmentation Supervisor or Security Shift Leader - El-2.2 Event 3.

General Office Notification Dedicated phone or SED /Come Initially 517-788-0990 at Unusual Power Controller Event

)

upon activation transfer notification to Dedicated phone or 82-87001 Every 15 GOCC min above Upon' activation transfer notification to Dedicated phone or Unusual 7

Technical Support Center Event 4.

NHC Notification 1.

Dedicated phone or SED /Comm Initially 2.

202-951-0550 at Unusual Bethseda op Ctr or Event 3.

301-427-4056 Every 15 Silver Springs or min above s

4 Health Physics Network Unusual

• 22 (Louch tone)

Event

?

22 (dial phone) or 5.

301-492-7000 Bethseda Central Office i

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(Time)

Action / Notification

._ _F_. rom E_l 1. ).

(

Dedicated Phone or SED /Come Initially 5.

State Notification at Unusual 616-637-2125 or South Haven State Police Post Event Security Radio Every 15 min above Unusuai Event Dedicated Phone or SED /Comm, initially 6.

Local Notification at Unusual 616-657-3101 Van Buren County Sheriff Event Evcay 15 min.ituive (Inusu.i l Event 7.

Initiate Fire Protection Plan Fire Protection SED /SS Initially

_Inplementing Procedures 8.

Covert Fire lept and Ambulance Service 616-764-1313 SED As Ni citeil

... _ ~ _..

9.

B.stkup Ambulance Service 925-2141 SED As Her le.1 HEDic I (St.luseph) 637-3305 Sout h II.sven Ambulance l

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Proc No

' 2.1 Revision 10 Page 3 of 6 EMERGENCY / ACTIONS / NOTIFICATIONS Turnover to Action Type Normally GOCC/ EOF N. S, or I (From El-1)

Action / Notification Reference / Telephone No Assigned To Frequency (Time) 10.

Hospitals:

Benton Harbor Mercy 616-927-5241 or SED

,616-927-5242 As Needed South Haven Community 616-637-5271 11.

Property Protection Supervisor Day: Call List SED Initially Night: At Site Area Emergency Only 616-468-6370 l

12.

Initiate Onsite Honitoring EI-8 Chem / IIP Contin-uously 13.

Initiate Offsite Monitoring EI-9 Chem / IIP Contin-uously I

f 14 Perform Offsite Dose Estimates, EI-i.0 Chem / IIP Per EI-6.0 Obtain Meteorological Data 15.

Perform Post-Accident Sampling El-7.0 Chem /HP As Needed a

f.

16.

Perform Environmental Assessment EI-10 Chem / lip As Needed I

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Turnover to Acticn Type Noranally G)CC/ Et er Action /Notificatiott Reference / Telephone No Assigned To Frequenry_.

(Tisa1 it. S,[ o r 1

{f,roen El-11 18.

Activate the Operational El-4.2-SED Initially at Alert Support Center (OSC) 19.

Activate the Emergency EI-4.3 SED Initially at Site Operations facility (EOF)

.. Area Emerg 20.

Activate the Joint Public Nuclear Plant Emergency Plant initially Information Center (JPIC)

Public Infonsation Policies Public and Procedures Aftairs Director SED Initially 21.

Dispatch liasons to local Emergency at Site Operatiosu Centers Area Emesg i

22.

Perform Personnel Accountability El-12 SED /

Initially Security,_ _ _.i t. A l i r t f

i 23.

Evacuate non-essential personnel E l - l '*

SED /

Initially Chem /HP/

.s t Site Security _,_ Arc.s Emer6 24.

Notif y I'l nt Public Aff airs Director Call List: (Days) 637-8769 or (night)

SED i n n t s.. I l y

.a t ilnus u.s i 82-80333 o}

Event

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' 2.1 Proc Nc Revision 10 Page 5 of 6 EMERGENCY / ACTIONS / NOTIFICATIONS a

' Turnover to Action Type Normally GOCC/ EOF H. S, or I Reference / Telephone No Assigned To Freque_ncy_

(Time)

(From EI-1)

' Action / Notification 25.

Perform Estimate Core Damage EI-il Tech As Needed T

26.

Backup Local Notification 616-983-7141 SED /Come As Needed Serrien Coyoty AND 616-673-5441 Allegan County 27 Michigan Dept of Public ifealth 517-373-1578 (Days)

Chem / IIP As Needed 517-373-0800 (Night)

SED /Come As Needed 28.

US Coast Guard Notification 616-983-1371 St Joseph 616-759-0951 i

Huskegon 29.

South Haven Water pept 616-637-5211 (Days)

SED /Come As Needed

+

616-637-5151 (Nights) i Notification i

30.

Palisades Park Mana8er Notification 616-764-8272 SED /Come As Needeel

/

31.

Van Buren State Park Manager 616-637-2788 SED /Come As Needed Notification 32.

Federal Aviation Administration 616-637-8075 SED /Come If light fails on South Bend, IN Het Tower

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4 EMERGENCY / ACTIONS / NOTIFICATIONS

'Ipin..ver to Artistn Type Norsially 8 G"tT / EOF H, 5, or I F cT2_ency

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(From El-1)

Artlon/ Notification Reference / Telephone No Ass _igned To L

33.

Initiate reentry / recovery EI-5 SED 34.

Initiate Event Report Admin Procedures SED Within 24 hrs at No 3.04 I

Unusual Event within 8 hrs above Unusu.il Event e

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Proc No EI-7.10 Revision 0 Date 6/28/83 PALISADES NUCLEAR PLWT EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Sununary TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING 1.

Prepared 2.

QA Concurrence f G hh 4-2'3-T3 h

Originad6r Date Date 3.

Recommend Approval /Q-List Yes No 4.

PRC Reviewed S/ /? M 6!EVh?

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Approved 6.

ATMS Incorporated he

1. LZ7 &3 J #3 Plant Manager Date Date 7.

Biennial Review Date j

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PALISADES NUCLEAR PLANT Proc No EI-7.10 TMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page i TITLE: POST ACCIDENT SAMPLING, RADI0 ACTIVE GASEOUS EFFLUENT MONITORING Table of Contents

{ age,

.1.0 PERSONNEL RESPONSIBILITY..

I 2.0 PURPOSE 1

3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS-.

1 3.1 IMPLEMENTATION..........................

1 3.2 DOSIMETRY REQUIREMENTS............

1 3.3 ANTI-CONTAMINATION CLOTHING REQUIREMENTS.

1 3.4 GENERAL RADIOLOGICAL PRECAUTIONS.

1 4.0 RGEM SAMPLING 2

4.1 ACCESS ROUTES 2

4.2 PRE-SAMPLING SURVEY 2

4.3 NORMAL RANGE IODINE / PARTICULATE FILTER CHANGE 0UT.

3 4.4 AUTOMATIC GRAB SAMPLE 3

1 4.5 HIGH RANGE IODINE FILTER CHANGE 0UT.....

3 4.6 SAMPLE COUNTING 4

4.7 RESULTS 4

l 5.0 ATTACHMENTS 4

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l PALISADES NUCLEAR PLANT Proc No EI-7.10 EMERGENCY IMPLEMENTATION PROCEDURE Revision 0 Page 1 of 4 TITLE: POST ACCIDENT SAMPLING, RADI0 ACTIVE GASEOUS EFFLUENT MONITORING 1.0 PERSONNEL RESPONSIBILITY The Chemistry / Health Physics Group Leader shall implement this procedure. In the absence of a Chemistry / Health Physics Group Leader the Site Emergency Director shall delegate this responsibility.

2.0 PURPOSE To provide the ability to take post accident samples of the stack effluent, using the Radioactive Gaseous Effluent Monitor (RGEM).

3.0 INITIAL CONDITIONS AND/OR REQUIREMENTS 3.1 IMPLEMENTATION a.

This procedure shall be implemented per EI-7.0, Emergency Post Accident Sampling.

b.

The normal range iodine and particulate filter should be sampled at high alarm, but may be sampled before this time at the direction of the Chemistry / Health Physics Group Leader. These filters isolate automatically at the RGEM hign alarm.

The automatic grab sample should be collected after the RGEM alert c.

alarm.

d.

The high range iodine filter should be sampled after the high alaria at the direction of the Chemistry / Health Physics Group Leader.

3.2 DOSIMETRY REQUIREMENTS Each individual that may handle a post accident sample shall as a minimum wear beta / gamma TLD's on their chest and on the inside of both wrists. Additionally, a ring TLD shall be worn on both index fingers with the TLD faced inward.

3.3 ANTI-CONTAMINATION CLOTHING REQUIRDfENTS Minimum clothing shall consist of full anti-C's, wetsuit with all seams taped, and a SCBA breathing unit. A lapel air sampler shoulr2 be worn by the sampling technician. Any persons who will handle samples shall wear lineman's gloves in addition to their other clothing.

3.4 GENERAL RADIOLOGICAL PRECAUTIONS a.

Two people should be used to gather samples. A qualified Radiation Safety Technician shall accompany a second technician.

The Radiation Safety Technician shall have as a nutnimum a teletector, an RO-2A, and a grab air sampler, or equivalent instruments. The Radiation Safety Technician shall monitor the l

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POST ACCIDENT SAMPLING RADIuACTIVE CASE 0t's EFFLL'ENT M"Nir S:C area during all samp1tng operat tons.

S. imp h s sha ll 1 e mon: to re.1 for beta radiation prior to any hand hand!tng.

b.

Sampling with general area radiation levels in excess.if 10 Rihr shall not be performed without the approval of the site Emergency Director.

c.

Stay times for technictans performing post accident sampling shall be based on the formula:

Stay Time = RQ x 0.8 DR Where:

"RQ" is the individuals remaining quarterly exposure and "DR" is the ares's general area doserate.

In cases where the doserates vary widely during sampling, the Radiation Safety I

Technician shall ensure that dosimeters are read f requently and ilo c

not exceed 80% of remaining quarterly exposure.

v Hand handling of samples shall be minimized. When simples must be l

j, ~

handled, a beta radiation doserate reduction of 90% can be assumed d.

(

p.e. <, '. -

for lineman's gloves. Dose to the extremities shall be 12mited to n,

7.5R as measured by the ring TLD pending a dose determination

^ r m

v. _

based on the beta / gamma TLDs.

h l

I When not being handled, samples shall be stored in a shtelded or i

e.

removed location.

.i RGEM control operations should be performed at the remote control l

f.

(

panel located behind the C-IIA panel'in the Control Room.

(

4.0 RCEM SAMPLING

.16.1 ACCESS ROUTES r

The primary access routes to the RGEM room is through the main P"'~ .

a.

it Control Room door, to the Turbine Building, and up the staircase'

• ^

to the RGEM room.

r

[

b.

In the case of high radiation levels along the above route. the back door of the Control Room should be used to access the Turbane Building.

4.2 PRE-SAMPLING SURVEY A pre-sampling survey may be performed in the RCEM room, but due to the short time required to sample, this precaution may be unnecessary.

The Chemistry /Nealth Physics Group Leader shall make this dete rmination.

O et0683-0012al54-89

PALISADES NUCLEAR PLANT Proc No EI-7.10 EMERGENCY IMPLEMENTATION PROCEDUFE Revision 0 Page 3 of 4 TITLE: POST ACCIDENT SAMPLING, RADIOACTIVE GASEOUS EFFLUENT MONITORING 4.3 NORMAL RANGE IODINE / PARTICULATE FILTER CHANGE 0UT Perform all control operations from the remote control panel in a.

the Control Room.

b.

Switch System Control Purge to the o_n position. This will divert purge air through the system during filter change.

c.

Proceed to the RGEM room per Paragraph 4.1.

d.

The normal range iodine / particulate sampler is located inside the lower cabinet on the right side of the RGEM system.

Open the cabinet and loosen the two wingnuts on the filter holder e.

assembly. Turn the handle clockwise and draw the filter holder from the sampler, f.

Unscrew the filter cap and remove the filters. Wrap the filters to prevent spread of contamination. Use forceps to handle the filters whenever possible. Samples should be marked with type, time and date.

g.

Inspect the 0-rings on the filter holder assembly and replace if damaged.

h.

Install new filters by following Steps 4.3.e and 4.3.f in reverse order.

i. Return to the Control Room and turn the System Control Purge to the off position. This will return the system to sampling mode.

4.4 AUTOMATIC GRAB SAMPLE A 30 second grab sample will be initiated when the Alert alarm is a.

given by the Normal Range Noble Gas Monitor (RIA-2326).

Proceed to:

b.

The RGEM room and close the two valves located on either side of the grap sampler.

-The grab sample can then be removed by releasing the two quick c.

release couplings found on both sides of the sampler. Sample should be marked with type, time and date.

d.

The grab sampler can then be removed for counting.

4.5 HIGH RANGE IODINE FILTER CHANGE 0UT A high alarm will switch the RGEM system to the IGgh Range sample a.

mode.

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E_.'.tRGE.NCY 1."Pt.U!ENTAT 10N f RpCEy!]E Mcvi ten e P.. g e '... ;

T I TI.E :

POST AC0! DENT S A."PLIN(..

RADIOTCTIVE CASEut's EFF l.LT..NT i S ! M' Nu b.

The Acendent Filter Control Operating Mode Swatch is kept in the sample position during normal operatton and emergency

.impling.

During emergency sampling, the system will.ilternate tietween

[

sampling and rurge every minute in a pre-set ratio.

1; To collect the high range iodine f alter, switch the Acrident i

c.

Filter Control Operating ?! ode to the Filter Change position.

In this mode purge air is continously diverted through the high r:inge iodine filter. This change should be made on the Control Hi,om RGEN remote control panel.

i f

d.

Proceed to the RGEM room, per Paragraph 4.1.

L Upon arrival at the high range iodine falter. loosen the two

[

e.

thumbscrews and two wingnuts on the top of the unit acid pull the y

retainer pin. located behind the lid.

f.

Draw the filter holder into the carrier by pulling the filter changer handle to its fully extended position.

Insert the small p

y-, ~., ' '

retainer pin on the top of the side bracket. The filter carrier M;

can be removed for counting. Mark the carrter with saniple type.

time and date. The filter changer may be unscrewed and removed to L.J W

facilitate transport.

[

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7

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J~ 4.6 SAMP!.E COUNTING i.

4 Samples should be counted initially with a PRM-6, (or equivalent),

{

~, _

a.

g, vc per El-8 or 9.

Samples containing.less than 25 mci may then be j

counted on the normal plant counting golpeent.

L b.

Iodine samples may be counted using a SAH-!!, per E!-8, as a backup method.

t E, " 7. i. 7

,4 ItESULTS f

V a.

Counting results shall be reported to the Chemistry /F alth Physics Group !.eader.

l b.

These results should be incorporated into Offsite Dose estimates (Refer to E!-6.0).

I i

5.0 ATTAC10 TENTS None

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Proc Na EI-1 J

Ravisien 8 Date 6/29/83 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE Revision and Approval Sunnary i

TITLE: ACTIVATION OF THE SITE EMERGENCY PLAN /

EMERGENCY CLASSIFICATION F

I I

2.

QA Concurrence 1.

Prepared e a D - n-s-n-rz

x. A.

Date OriginatcV Date 3.

Reco nd Approval /Q-List Yes No 4.

PRC Reviewed

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'Date era ent Head sDate 6.

ATMS Incorporated 5.

Approved

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Biennial Review Date

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PALISADES NUCLEAR PLANT Proc Na EI-1 EMERGENCY IMPLEMENTATION PROCEDURE Rsvioica 8 Page 1 TITLE: ACTIVATION OF THE SITE EMERGENCY PLAN /

EMERGENCY CLASSIFICATION Table of Contents P,,f!ge, I

1.0 PERSONNEL RESPONSIBILITIES.

1 2.0 PURPOSE 1

3.0 INITIAL CONDITIONS AND/OR REQUIREENTS.

4.0 ACTIVATION OF THE SITE EMERGENCY PLAN / EMERGENCY CLASSIFICATION.

1

..1 4.1 CLASSIFICATION / RECLASSIFICATION 3

4.2 DETERMINATION OF EMERGENCY ACTIONS / NOTIFICATIONS.

3 4.3 TURN OVER OF SED RESPONSIBILITIES 3

5.0 ATTACHMENTS ATTACHMENTS, " Site Emergency Plan Classification", " Emergency Class Description" l

i l

eio780-000Sd154-89 l

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PALISADES NUCLEAR PLANT Pr:c Na EI-1 EMERGENCY IMPLEMENTATION PROCEDURE Revision 8 Page 1 of 3 I

TITLE: ACTIVATION OF THE SITE EMERGENCY PLAN /

EMERGENCY CLASSIFICATION i

1.0 PERSONNEL RESPONSIBILITIES 1.1 The Shift Supervisor shall implement this procedure and assume the title and responsibilities of the Site Emergency Director (SED) until relieved by Plant management identified below.

1.2 The line of succession for the SED is:

Plant Manager (days), Duty and Call Superintendent (nights) a.

Operations and Maintenance Superintendent (1st alternate) b.

Operations Superintendent (2nd alternate) c.

d.

Technical Superintendent (3rd alternate)

Technical Engineer (4th alternate) e.

2.0 PURPOSE To classify those emergency conditions that necessitate the activation of the Site Emergency Plan. To identify actions that should be taken to mitigate the consequences of an emergency.

s 3.0 INITIAL CONDITIONS AND/OR REQUIREENTS This procedure shall be implemented any time an event occurs or conditions, exist which, in the opinion of the Shift Supervisor / SED, may require activation of the Site Emergency Plan (SEP).

QR, When events occur or conditions exist after the activation of the SEP that, in the opinion of the SED, may require reclassification, either upgrading or downgrading.

4.0 ACTIVATION OF THE SITE EMERGENCY PLAN / EMERGENCY CLASSIFICATION f

4.1 CLASSIFICATION / RECLASSIFICATION l

The Shift Supervisor / SED shall classify emergency condi-a.

tions/ events as follows:

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EMERCENCY IMPLEME.%TATION PROCEDUKE he v i.s : s.:

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TITLE: ACTIVATION OF fi!E SITE EMERGL.'.G PI E EMERGENCY CLASSil'IC/.T!ON 1.

Determine the estegory ' hat conditions / events best ist trom the list of keywords below:

Ala rms /Annuncia tors Communication Loss Containment lutegrity Engineered Safety Features b

[

Evacuation - Control Room i

Fire Fission, Product Barriers / Fuel Damage i.

Hazards - General 1

E~

Injury 2..

EL Meteorological Data Loss be ^ ?

t Miscellaneous g

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4 Natural Phenomenon E[ ^

Plant Power - Electrical

[

Primary Coolant System Integrity

(*'

t Primary Coolant System - Temperature or Pressure p

Radiation levels Releases Safety Injection System I

Secondary Side Security 2.

Use the keyword identified above and Attachment 1, Site Emergency Plan Classification to classtfy the condi-tions/ event.

NOTE:. Emergency Class Descript aon is provided for backgrousiil information and shoiald not be used f or classification.

O e10780-000Sa!54-89

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PALISADES NUCLEAR PLANT Pesc No EI-1 EMERGENCY IMPLEMENTATION PROCEDURE Revision 8 Page 3 of 3 TITLE: ACTIVATION OF THE SITE EMERGENCY PLAN /

4 EMERGENCY CLASSIFICATION 4.2 DETERMINATION OF EMERGENCY ACTIONS / NOTIFICATIONS a.

The numbers in the righthand column of Attachment 1 (Actions / Noti-fications) identifies actions that should be performed for each emergency. These numbers relate to the Actions / Notifications listed in EI-2.1, Attachment 1.

b.

The categories of actions are as follows:

1.

Mandatory Actions - Actions that shall be performed within one hour.

4 NOTE:

Initial notification to State and Local government should be performed within 15 minutes.

2.

Subsequent Actions - Action that should be performed in an expeditious manner as conditions, time, and personnel permit.

3.

If Needed Actions - Actions that are not required, but may be needed.

c.

After determination of the emergency actions / notifications mark the fef thand column of EI-2.1, Attachment I with an M, S or I for handatory, Subsequent or If Needed Action respectively, for each identified emergency action. Date EI-2.1, Attachment 1.

NOTE:

Emergency actions identified in this section are in addition to the SED responsibilities identified. in EI-1.1.

4.3 TURN OVER OF SED RESPONSIBILITIES a.

The Shift Supervisor shall turn over the responsibilities of SED to the personnel identified in Section 1.0 as soon as possible, above Unusual Event. Turn over may occur before this time at the option of the Shift Supervisor or potential SED.'

b.

Turn over should include verification of the emergency classification and pertinent information on Plant conditions.

c.

The turn over should be announced in the Technical Support Center (TSC) and Operational Support Center (OSC), if activated, to ensure continuity of command and control.

d.

Proceed to EI-2.1, " Emergency Actions / Notifications / Responsibilities" 5.0 ATTACHMENTS l

'5.1, " Site Emergency Plan Classification" l

5.1, " Emergency Class Description" e10780-000Sa154-89

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Revision 8 Page 1 of 32 ALAkMS/ ANNUNCIATORS CLASSIFICATION EMERGENCY ACTION I.EVEL HET110D OF DETECTION ACTIONS Alert Loss of most or all alarms Observation Handatory:

1,2,3,4,5, (annunciators) in Control Room.

6, 11, 12, 14, 17, 22 Subsequent:

18, 24, 33, 34 If Needed:

19, 25, 30 t

Site Area Loss of most or all alarms Observation Handatory:

1,2,3,4,5, Emergency (annunciators) for 15 minutes AND 6, 11, 12, 13, Shift Supervisors opinion that a 14, 17, 22 i

Plant transient has occurred or is Subsequent:

16, 18, 19, 21 in progress.

23, 24, 33, 34 If Needed:

19, 25, 26 4

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-Revision 8 Page 2 of 32 COMMUNICATIONS LOSS C E SIFICATION EMERGENCY ACTION LEVELS HETHOD OF DETECTION ACTIONS Unusual Significant loss of offsite Observation Handatory:

1,3,4,5,6 Event communication capability.

Subsequent:

24, 34 (eg, loss of all comunercial and If Needed:

2, 26, 33 dedicated phones) 4 i

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Proc No E. -1 Revision 8 Page 3 of 32 CONTAINHENT INTEGRITY CLASSIFICATION EMERGENCY ACTION LEVEL HETHOD OF DETECTION ACTIONS Unusual Loss of Containment integrity Leak Rate Test Results Handatory:

1,3,4,5,6 Event requiring shutdown due to OR Penetration Test Results Subsequent:

24, 34 Technical Specifications OR Observation If Needed:

2, 26, 33 e

NOTE:

For incidents involving loss of containment integrity AND loss of a second fission product barrier AND potential loss of the third fission product barrier, see FISSION PRODUCT BARRIER / FUEL DAMAGE.

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k Proc No Es-1 Attachacat 1 Revision 8 Page 4 of 32 ENGINEEHED SAFETY FEATURES CLASSIFICATION EMERCENCY ACTION LEVEL NETHOD OF DETECTION ACTIONS Unusual Ioss of engineered safety Observation Haadatory:

1,3,4,5,6 Event features requiring Plant shut-Subsequent:

24, 34 i

down due to Technical Speci-If Needed:

2, 26, 33 l

fications-3.2, 3.3, 3.4.

Loss of fire protection system Observation requi~ ring Plant. shutdown due to Technical Specifications.

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t Alert Failure of Reactor Protection Nuclear instrumentation Handatory:

1,2,3,4,5 system to initiate and complete AND Rod position indicator 6, 11, 12, 14 a trip AND the reactor is nat 17, 22 subcritical.

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Subsequent:

18, 24, 34

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If Needed:

19, 25, 26 I

Complete loss of any functions Observation needed for Plant cold shutdown ie, Loss of Auxiliary Feed System

1-s and Shutdown Cooling Systems.

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,i Site Area Complete loss of any function Annunciation Handatory:

1,2,3,4,5 t

Emergency needed for hot shutdown OR 6, 11, 12, 13, Observation 14, 17, 22 e

Subsequent:

16, 18, 19, 21, s

t-23, 24, 33, 34 If Needed:

15, 25, 26 Transient requiring operation Nuclear instrumentation of shutdown systems with failure AND Hod posillou indicator to trip (continued power 4

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generation, but no core damage immediately evident).

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Page 5 of 32 ENGINEERED SAFETY FEATURE _S CLASSIFICATION EMERGENCY ACTION LEVEL NETHOD OF DETECTION ACTIOhS General Transient requiring operation Nuclear instrumentation AND Mandatory:

1,2,3,4,5,6 Emergency-of shutdown system with Rad position indicator AND 11, 12, 13, 14, 17, 22 failure to trip which Reactor pressure greater results in core damage then safety valve setpoint Subsequent:

16, 18, 19, 21, or additional failure of OR Rapidly increasing 23, 24, 33, 34 i

core cooling and makeup Containment pressure systems (which could lead OR Rapidly. increasing If Needed:

15, 25, 26 to core melt).

Containment pressure OR Failed Fuel Monitor i**RIA-0202)off scale high confirmed by sample analysis Transient initiated by loss Observation - loss of of feedwater and feedwater condensate systems (principal AND heat removal system)

Observation - loss of followed by failure system of auxiliary feedwater ANp system for an extended Observation - failure of period. Core melting aux feedwater system possible in'several hours.

for greater than 30 minutes.

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Proc No E -I Revision 8 Page 6 of 32 EVACUATION, CONTROL ROOM CLASSIFICATION ENERGENCY ACTION LEVEL HETHOD OF DETECTION ACTIONS Alert Evacuation of Control Room Observation Handatory:

'1,2,3,4,5, anticipated or required with 6, 11, 12,.14, contral of shutdown system 17, 22 established at local stations, Subsequent:

18, 24, 3'l, 34 r

1 19, 25, 26 If Needed:

i Site Area Evacuation of Control Room and Observation Mandatory:

1,2,3,4,5 Emergency control of shutdown systems not 6, 11, 12, 13, established at local stations 14, 17, 22 within 15 minutes.

Subsequent:

16, 18, 19, 21 23, 24, 33, 34 If Needed:

15, 25, 26 i

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s Proc No Lt-1 Revision 8 Page 7 of 32 FIRE Cl.ASSIFICAT' ION EMERGENCY ACTION I.EVEL HETIlOD OF DETECTION ACTIONS Unusual Fire within the Plant last!cg

. Observation Handato ry:

1,3,4,5,6, Event more than 10 minutes.

OR 7, 11 Fire detection alarm con-Subsequent:

24, 34 firmed,by observation.

If Needed:

2, 8, 26, 33 Alert Fire potentially affects a safety Shift Supervisor's opinion Handatory:

1, 2, 3, 4, 5, systems.

6, 7, 11, 12, 14, 17, 22 Subsequent:

24, 34 If Needed:

2, 8, 26, 33 Site Area Fire compromising.the function of Observation Handatory:

1,2,3,4,5, Emergency safety systems.

6, 7, 11, 12, 13, 14, 17, 22 Subsequent:

16, 18, 19, 21, 23, 24, 33, 34 If Needed:

8, 15, 25, 26 I'

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Proc No Es-1 Revision 8 Page 8 of 32 FISSION PRODUCT BARRIERS / FUEL DAMAGE I CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS Unusual Primary Coolant Iodine-131 dose Failed Fuel Monitor Mandatory:

1,3,4,5,6 Event concentrstion equivalent

(**RIA-0202) Alarm confirmed Subsequent:

24, 34

> 1.Dpci/gm for more than 72 brs, by sample analysis.

If Needed:

2, 26, 33 i

> 0.1% increase in failed fuel Observation within 30 minutes.

• • RIA-0202 Alert Primary coolant Iodine-131 dose Failed Fuel Monitor Mandatory:

1,2,3,4,5 equivalent concentration

(**RIA-0202) off scale high 6, 11, 12, 14,

> 300pCi/gm confirmed by sample analysis.

17, 22 Subsequent:

18, 24, 33, 34 If Needed:

19, 25, 26

> 1% increase in failed fuel Observation within 30 minutes.

> 5% total failed fuel.

Failed Fuel Monitor

(* ARIA-0202)'off scale high confirmed by sample analysis OR Observation

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Fuel damage accident with release Radiation monitor alarm con-of radioactivity to Containment firmed after observation of

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accident OR Observation of accident confirmed by sample analysis OR Shift Supervisor / SED's opinion p/

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s Proc No Es-1 Revision 8 Page 9 of 32 FISSION PRODUCT BARRIERS / FUEL DAMAGE CLASSIFICATION ENERGENCY ACTION LEVEL HET110D OF DETECTION ACTIONS Alert Coolant pump seizure leading to Coolant pump trip AND Failed (cont'd) fuel fallure Fuel Monitor Alarm confirmed by sample analysis.

Site Area Major damage to spent fuel in Radiation monitor alarm con-Mandatory:

1,2,3,4,5 Eoergency Containment or Fuel llandling firmed af ter observation of 6, 11, 12, 13, Building.

(eg, large object accident OR 14, 17, 22 damages fuel or water loss belott Observation of accident Subsequent:

16, 18, 19, 21, i

fuel level) confirmed by sample analysis 23, 24, 33, 34 OR If Needed:

15, 25, 26 Shift Supervisor / SED's opinion Degraded core with possible loss High core temperature of coolable geometry.

OR Inadequate subcooling mar-gin OR Core uncovered AN, D,

_Temperature drop across the i

core increasing OR No

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core OR Shift Supervisor / SED's i,

opinion 1.

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Generpl Loss of 2 of 3 fission product Detection dependent upon Mandatory:

1,2,3,4,5, Emergency barriers with potential loss of which barriers fail and to 6, 11, 12, 13,

!;s third fission product barrier some extent, upon mechanism 14, 17, 22

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(eg, loss of Primary Coolant which causes failure.

Subsequent:

16, 18, 19, 21,

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15, 25 26 of Containment) o

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Proc No Ea-1 Revision 8 Page 12 of 32 IIAZARDS - CENERAL CLASSIFICATION ~

ENERCENCY ACTION LEVEL METil0D OF DETECTION ACTIONS Site Area Aircraft crash affecting vital Observation Handatory:

1,2,3,4,5, Emergency structures by. impact or fire AND 6, 11, 12,.13, Plant not in cold shutdown.

14, 17, 22 Subsequent:

16, 18, 19, 21, 23, 24, 33, 34 If Needed:

15, 2S, 26 Severe damage to equipment re-quired for safe shutdown from missile explosion - see ENGINEERED SAFETY FEATURES Entry of uncontrolled flammable Observation OR gas into vital areas OR Entry Detection with portable of uncontrolled toxic gas into instrumentation.

vital areas that constitutes a safety problem AND Plant not in Cold Shutdown.

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Revision 8 Page 13 of 32 INJURY CLASSIFICATION EMERGENCY ACTION LEVEL HETHOD OF DETECTION ACTIONS Unusual Transportation of injured contas--

Observation Handatory:

1,3,4,5,6,8, 5

Event inated individual from site to 10

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offsite hospital.

Subsequent:

24, 34 If Needed:

2, 9, 26

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Notify county to

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i Proc No El-1 Revision 8 Page 14 of 32 METEOROLOGICAL DATA LOSS CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DE'IECTION ACTIONS

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Unusual Loss of onsite meteorological data Observation Handatory:

1,3,4,5,6 Event MD Subsequent:

24, 34 Loss of all backup meteorological Observation If Needed:

2, 26 data 4

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• .. No EI-I Attachment IL Revision 8 Page 15 of 32 MISCELLANEOUS CIASSIFICATION ENERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS Unusual Plant conditions exist that war-Shift Supervisor / SED's opinion Mandatory:

1, 3, 4, 5, 6 Event rant increased awareness on the Subsequent:

24, 34 part of the Plant staff or State If Needed:

2,-26, 33 and/or local authorities OR require Plant' shutdown under Technical Specifications require-ments OR involve other than normallhutdown.

Alert Plant conditions exist that war-Shift Supervisor / SED's opinion Mandatory:

1,2,3,4,5,

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rant precautionary activation 6, 11, 12, 14 of Technical Support Center and 17, 22

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placing Emergency Operations' Subsequent:

18, 24, 33, 34 Facility and other emergency If Needed:

19, 25, 26 personnel on standby.

Site Area Plant conditions.warrent the Shift Supervisor / SED's opinion Mandatory:

1,2,3,4,5, Emergency activation of emergency centers.

6, 11, 12, 13, and monitoring teams or a precau-14, 17, 22 tionary notification to the Subsequent:

16, 18, 19, 21, public near the site.

23, 24, 33, 34 If Needed:

15, 25, 26 k'.

Genera l Conditions exist that make Shift Supervisor / SED's opinion Mandatory:

1,2,3,4,5,

'i Emergency.

release of large amounts of radio-6, 11, 12, 13, activity in a short time possible, 14, 17, 22 (eg,.any core melt situation)

Subsequent:

16, 18, 19, 21, 23, 24, 33, 34

-l If Needed:

15, 25, 26

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N Proc No Es-1 Revision 8 Page 16 of 32 MISCELLANEOUS CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS Ceneral Any major internal or external Shif t Supervisor /SEDs Emergency events (eg, fires, earthquakes, opinion (Cont'd) substantially beyond design basis) which could cause massive common damage to plant systems.

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Revision 8 Page 17 of 32 NATURAL PHENOMENON CLASSIFICATION ENERCENCY ACTION LEVEL NETHOD OF DETECTION ACTIONS Unusual Any earthquake felt in-Pi; Observation Handatory:

1,3,4,5,6 Event Flood, seiche - Obscrvation of t

Abnormal water levels including water approaching 590' level.

Subsequent:

24, 34 flood or low water or seiche.

Low water - Obst:rvation.

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Tornado onsite observation If Needed:

2, 26, 30, 31, 33 Alert Earthquake greater than OBE levels "To Be Added Later" Handatory:

1,2,3,4,5, surface acceleration greater 6, 11, 12, 14, than 0.lg 17, 22 Flood, seiche - Observation of i

Flood, low water, or seiche near water above 590' level.

Subsequent:

18, 24, 33, 34 design basis.

Low water - Observation, 9

Tornado striking facility Observation If Needed:

19, 25, 26, 30, 31 Site Area Earthquake greater than SSE levels "To Be Added Later" Handatory:

1,2,3,4,5, Emergency Surface acceleration greater 6, 11, 12, 13, than 0.2g 14, 17, 22 i

Flood, low water, or seiche Flood, seiche - Observation of Subsequent:

16, 18, 19, 21, greater than design levels water above 594' level.

23, 24, 33, 34 OR Failure of protection of Others - Observation If Needed:

15, 25, 26, 30 vital equipment at lower lev,els.

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Revision 8 Page 18 of 32 NATURAL PilENortENON CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS p Site Area Tornado in or sustained winds in Observation, notification by Emergency excess of design level.

offsite agencies; (Cont'd)

Peripheral tangential velccity

> 300 mph with tornado center i

traveling > 60 mph

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w Proc No El-1 Attachment I-Revision 8 Page 19 of 32 PLANT POWER - ELECTRICAL CLASSIFICATION EMERGENCY ACTION LEVEL HETilOD OF DETECTION ACTIONS Unusual Loss of offsite power Annunciation switchyard non-Handatory:

1,3,4,5,6 Event critical alarms OR startup trausformer trouble alarm OR Subsequent:

24, 34 Automatic start of Emergency piesel Generator.

If Needed:

2, 26, 32, 33 Loss of all onsite AC power Observation: both Emergency Diesel Generators inoperable

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Alert Loss of offsite power AND loss of Bus IC & ID low voltage Mandatory:

1,2,3,4,5,

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all onsite AC power for less than alarms 6, 11, 12, 14, 15 minutes.

17, 22 i-Subsequent:

18, 24, 33, 34 If Needed:

19, 25, 26, 32 7

Loss of all onsite DC power for DC Bus #1 and #2 low voltage i ~

less than 15 minutes alarms.

l-Site Area Loss of offsite power AND loss of Obse rva tion Handatory:

1, 2, 3, 4, 5,

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Emergency onsite AC for more than 6, 11, 12, 13, i

15 minutes.

14, 17, 22 i

Subsequent:

16, 18, 19, 21, 1,

23, 24, 33, 34

[p,i If Needed:

15, 25, 26, 32 f-(-

Loss of all vita} opsite DC power Observation 7 -}..[

for more than 15 minutes, AND

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Plant not in col 4 shutdown.

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Proc No El-1 Revision 8 Page 20 of 32 PLANT POWEH - ELECTRICAL CLASSIFICATION EMERGENCY ACTION LEVEL NETilOD OF DETECTION ACTIONS General Loss of offsite and Bus IC and ID low Mandatory:

1,2,3,4,5,6, Emergency onsite AC power AND voltage alarms 11, 12, 134 14, 17, 22 loss of auxiliary AND Subsequent:

16, 18. 19, 21, feedwater makeup Observation of failure 23, 24, 33, 34 capability for greater of aax feedwater If Needed:

15, 25, 26, 32 than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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Proc No El-1 Revision 8 Page 21 of 32 PRIMARY COOLANT SYSTEM INTEGRITY CLASSIFICATION EMERGENCY ACTION LEVEL HETil0D OF DETECTION ACTIONS Unusual Primary Coolant System leakage in PCS leak rate determination Handato ry:

1,3,4,5,6 Event excess of Technical Specifications (D/WO-1)

Subsequenti 24, 34 but < 50 GPH If Needed:

2, 26, 33 Steam Generator secondary water Chemical analysis activity > 0.lpCi/gm of dose equivalent I-131.

Primary to secondary leakage rate Offgas monitor (**RIA-0631) exceeds Technical Specifications alarm confirmed by chemical limits of 0.3 GPH steady state or analysis 0.6 CPM for transients, but

< 50 GPH.

Alert Rapid gross failure of one Steam Offgas monitor (**RIA-0631)

Handatory:

1,2,3,4,5 Generator tube with loss of alarm confirmed by sample 6, 11, 12, 14, offsite power, analysis AND Decreasing 17, 22 pressurizer level AND Obser-vation of loss of offsite j

power t

i Rapid failure of Steam Generator Offgas monitor (**RIA 0631).

Subsequent:

18, 24, 33, 34 tubes resulting in primary to alarm confirmed by sample k

secondary leak rate of several analysis OR Rapidly de-

/

hundred GPH.

creasing pressurizer low If Needed:

19, 25, 26 level (**LI-0103A)

[

r.

f, Steam line break with > 10 GPH Increased containment pressure b

primary to secondary' leak rate.

OR Increased Containment f ' t:

radiation levels; Decreasing kt pressurizer levels, OR Offgas p

h,p,g; Honitor (**RIA-0631) alarm gq tj confirmed by sample analysis g,,;.

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Proc No E. 1 Revision 8 Page 22 of 32 PRIMARY COOLANT SYSTEM INTEGRITY CLASSIFICATION EMERGENCY ACTION LEVEL HETHOD OF DETECTION ACTIONS Alert (cont'd)

Primary coolant System leak Containment sump high level

> 50 GPH but less than charging alarms AND mismatch between pump capacity.

charging flow and letdown flow Site Area Loss of coolant accident greater Low-low pressurizer level Handatory:

1, 2, 3, 4, 5, Emergency than charging pump capacity.

(**LIC-0101A) OR Safety 6, 11, 12, 13, lajection actuation alarm OR 14, 17, 22 Pressurizer low pressure alarm Subsequent:

16, 18, 19, 21, i

OR Containment high pressure 23, 24, 33, 34 alarm If Needed:

15, 25, 26 I

Rapid failure of Steam Generator Offgas monitor (**RIA-0631) tubes (several hundred GPM) with alarm confirmed by sample loss of offsite power.

analysis AND Pressurizer level decrease AND Observation of loss of offsite power.

Steam line break AND > 50 GPM lucreased Containment pressure l

primary to secondary leak rate OR Increased Containment i

AND indication of fuel radiation levels OR decreasing damage.

pressurizer levels _OR Steam i

Generator pressure instruments OR PCS leak rate determination k.

(D/WO-1) AND Offgas Monitor

(**RIA-0631) alarm confirmed i,

f by sample analysis AND Failed Fuel Monitor Alarm confirmed OR_ PCS sample analysis confirms fuel damage.

1 NOTE:

For incidents involving loss of Primary Coolant System Integrity AND loss of

(

a second fission product barrier AND potential loss of the third fission

[ gl, p product barrier, see FISSION PRODUCT BARRIER / FUEL DAMAGE.

4 '

eio780-0005bl54-89 i

3 i

Proc No EI-1 Attactunent 1 Revision 8 Page 23 of 32 PRIMARY COOLANT SYSTEM INTEGRITY TLASSIFICATION EMERGENCY ACTION LEVEL HETIIOD OF DETECTION ACTIONS Ceneral Small and large LOCAs Decreasing pressurizer level Mandatdry:

1,2,3,4,5,6, Emergency with failure of SIS OR pressurizer low-11, 12, 13, 14, 17, 22 leading to severe core pressure alarm OR Subsequent:

16, 18, 19, 21 degradation.

Salety Injection System 23, 24, 33, 34 actuation alarm AND If Needed:

15, 25, 26 Observation that SIS is not functioniug AND Failed Fuel Monitor '

(**RIA-0202) off scale high confirmed by

(

sample analysis I

Small or large I.0CA and Decreasing pressurizer level initially successful Safety OR Injection System, Subsequent Pressurizer low pressure

-l failure of containment.

alarm heat removal systems over AND several hours Safety Injection System actuation alarm ON].)

Observation - Failure of containment cooling for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> I

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Revision 8 Page 24 of 32 PRIMARY COOLANT SYSTEM - TEMPERATURE OR PRESSURE CLASSIFICATION EMERGENCY ACTION LEVEL NETHOD OF DETECTION ACTIONS Unusual Any challenge to over pressure Annunciation SV and/or PORV Event Protection System (OPPS).

open Mandatory:

1,3,4,5,6 Cratical operation at PCS temper-Temperature recorder (**TR-0121 ature < 525*F (except for physics or **TR-0111) tests).

Subsequent:

24, 34 Reactor high pressure trip.

Annunciator (RPS alarms)

(Initiating event)

Event recorder If Needed:

2, 26, 33 Pressurizer code safety operation. Acoustical monitors (**RI-1039

• • FI-1039, **FI-1041)

Quench Tank high level

(*ALIA-Oll6)

Quench Tank high pressure

(** PIA-Oll6)

Quench Tank high temperature

(*ATIA-Oll6) 3 l

Discharge temperature alarms (11TIA-0107,**TIA-0108, AATIA-0109)

Alerl PCS temperature < 50*F subcooled; Subcooling margin alarm Handatory:

1,2,3,4,5 sustained for more than 5 minutes 6, 11, 12, 14, or < 50*F subcooled, and 17, 22 I

subcooling margin decreasing.

Subsequent:

18, 24, 33, 34 i

Not applicable when Plant is in lf Needed:

19, 25, 26 cold shutdown or refueling shutdown condition.

e a[.[,' '.e10760-Qpp5bl54-89 f

i

Proc No El-1 Attaclament 1 Revision 8 Page 25 of 32 RADIATION LEVELS CLASSIFICATION EHERGENCY ACTION LEVEL HETil0D OF DETECTION ACTIONS Alert Radiation levels or airborne con-Radiation monitors increase Handatory:

1,2,3,4,5 tamination indicates a severe by a factor of 1000, confinned 6,11,12,14, degradation in concol of radio-DR 17,22 active materials.

Unexpected Plant area iodine Subsequent:

18,24,33,34 or particulate airbone concen-If Needed:

13,19,25,26 trations > 1000 HPC 27,28,39,30, (per 10CFH20, Appendix B 31 Table 1) 1 1

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Proc No El-1 Revision 8 Page 26 of 32 RELEASES

_ CLASSIFICATION ENERGENCY ACTION LEVEL HETHOD OF DETECTION ACTIONS Unusual Short term radiological effluent Stack monitor (**RIA-2326)

Handatory:

1,3,4,5,6 Event Technical Specifications exceeded.

reaches Alert Alarm setpoint Subsequent:

15, 24, 34-for greater than two hours.

If Needed:

2, 12, 13, 26

.h Confirmed by Lab sample 33 analysis.

Stack Monitor (**RIA2318) reaches high alarm setpoint for two or more hours.' Con-firmed by Lab sample analysis.

i Liquid waste discharge monitor

(**RIA-1049) reaches alarm

{

setpoint and automatic dis-charge trip function fails.

Confirmed by Lab sample analysis.

Significant solid or liquid waste Observation confirmed by spill outside restricted areas survey results.

with threatened offsite release.

Alert Radiological effluents > 10 times A valid stack monitor Handatory:

1, 2, 3, 4, 5, the Technical Specifications

(**RIA-2326) reading of 6, 11, 12, 14, limits (an instantaneous rate 2 3.0Et4 cpm above background 17, 22 which, if continued over two for longer than 15 minutes.

Subsequent:

15, 18, 24, 33, 34

'/

hours would result in a dose of A valid stack monitor If Needed:

13, 19, 25, 26, approximately 1 mR at the site

(**RIA-2318) reading of 27, 28, 39, 30, boundary under average meteor-2 4400 cpm above background 31 ological conditions).

for longer than 15 minutes.

OR Liquid Waste Discharge Honitor t

[

(**RIA-1049) reaches 10 times alarm setpoint and automatic discharge trip function fills.

v. " 5 Confirmed by Lab sample analysis.

ei0780-0005bl54-39 4

1-i

,n f-Proc No E.

a Revision 8 Page 27 of 32 RELEASES I

CLASSIFICATION EMERGENCY ACTION LEVEL HETHOD OF DETECTION

, ACTIONS

?

Site Area Effluent monitors detect levels Any of the following valid Handatory:

1,2,3,4,5, i

Emergency corresponding to > 50 mR/hr radiation monitor readings 6, 11, 12.,13, for 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or > 500 mR/hr whole for longer than 0.5 hour:

14, 17, 22 4

,I body for 2 minutes (or 5 times Stack monitor (**RIA-2326);

Subsequent:

15, 16, 18, 19, 21 these levels to the child thyroi4) reaches High Alarm setpoint; 23, 24, 33, 34 at the site boundary for adverse 2 2.5Et6 cpm above bkgd.

If Needed:

25, 26, 27, meteorological conditions. These Stack monitor (**RIA-2318);

28, 29, 30, 31 g

,F levels are projected based on 2 3.75Et5 cpm above bkgd.

other Plant parameters (eg, radi-Main Steam Honitors t

i ation level in containment with

(**RI A-2323 or **RIA-2324)

{

leak rate appropriate for exist-with a main steam release ing containment pressure) or occurring; are measured in the environs.

2 850 con above bkgd EPA Protective Action Guide-and confirmation of dose lines (see El-6.13) are pro-from procedure El-6.0 jected to be exceeded outside Containment high range moni-the site boundary.

Lors (**RIA-2321 or **RIA-2322) with no breach of contain-ment; 2 2.4Et4 R/hr above bkgd.

g 4

Any of the following valid f

radiation monitor readings fo'r longer than 2 minutes:

h Stack monitor (**RIA-2327) 2 20 mR/hr above bkgd.

Stack Honitor (**RIA-2318) is j.0 offscale and the High Range

,\\

Stack Honitor is 2 3.2E-3 R/hr above bkgd.

t,...,

hth. (

Hain Steam Honitors (**RIA-2323 Y

or **RIA-2324) with a main steam release occurring; kf-

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f' Proc No E. 1 Revision 8 Page 28 of 32 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL HETHOD OF DETECTION ACTIONS Site Area B 8500 cpm above bkgd and Emergency confirmation of dose (Cont'd) projection from procedure E{,-6.0 Containment High Range Moni-tors (**RI A-2321 or **RIA-2322) with no breach of contain-ment; c

2 2.4Et5 R/hr above bkgd.

r

?

QR Radiation monitoring teams at the site boundary measure whole body dose rates p

> 50 mrem /hr for 0.5 hr or i

h

> 500 mrem /hr for 2 min or thyroid dose rates i

> 250 mrem /hr (1.95E-7 pCi/cc I

dose equivalent 1-131) for i

0.5 hr or 2500 mrem /hr 3

(1.95E-6 pCi/c'c dose equivalent i

1-131) for 2 minutes.

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7-Proc No El-1 Attachment I-Revision 8 Page 29 of 32 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL NETHOD OF DETECTION ACTIONS General Effluent monitors detect levels Any of the following valid Handatory:

1, 2, 3, 4, 5, Emergency corresponding to I rem /hr whole radiation monitor readings may 6, 11, 12, 13, body or 5 rem /hr thyroid at the indicate a General Emergency 14, 17, 22 site boundary under actual meteor-Classification:

Subsequent:

15, 16, 18, 19, 21, ological conditions'. These levels Stack monitor (**RIA-2327) 23, 24, 33, 34 are projected based on other Plant reaches an Alert Alarm; If Needed:

25, 26, 27, parameters (eg, radiation levels 2 45 mR/hr above bkgd.

28, 29, 30, 31 in containment with leak rate Stack monitor (**RIA-2318) appropriate for existing contain-is offscale and the high ment pressure) or are measured range stack monitor is:

in the environs.

2 6.3E-3 R/hr above bkgd; Main Steam Honitors (**RIA-2323 or **RIA-2324) with a main steam release occuring is:

2 17,000 cpm above bkgd.

Containment liigh Range Mon-itors (**RIA-2321 or **RIA-2322) with no leakage greater t

than design _ leakage limit; f.

2 4.8Et5 R/hr above bkgd.

NOTE:

Consider evacuation only within A General Emergency is indica-about 2 miles of the site boundary ted if the dose projection from unless these site boundary levels procedure El-6.0 is 2 1 Rem /hr are exceeded by a factor of 10 or whole body or 2 5 Rem /hr

(

projected to continue for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> thyroid at the site boundary l

./

or EPA Protective Action Guide-for the existing meteorolo-i lines exposure levels (see gical conditions.

{.

EI-6.13) are predicted to be OR exceeded at longer distances.

Radiation monitoring teams at i,

the site boundary measure a whole body dose rate 2 1 Rem /hr or a thyroid dose rate j{j 2 5 Rem /hr (3.9E-6 pCi/cc t -fg dose, equivalent I-131)

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Revision 8 Page 30 of 32 SAFETY INJECTION SYSTEM CLASSIFICATION EMERGENCY ACTION LEVEL NETHOD OF DETECTION ACTIONS Unusual Safety Injection initiated and Annunciation flow verified Handatory:

1,3,4,5,6 Event discharged to vessel (Cktl, Ckt2)

Subsequent:

24, 34 If Needed:

2, 26, 33 i

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.m Proc No El-1 Revision 8 Page 31 of 32 SECONDARY SIDE i

Cl>.SSIFICATION EMERGENCY ACTION LEVEL HETii0D OF DETECTION ACTIONS f

Unusual Failure of. a safety or relief Annunciation AND Mandatory:

1,3,4,5,6 Event valve in a safety related system pressure indications, OR_

Subsequent:

24, 34 to close following reduction of Observation If Needed:

2, 26, 33 l

applicable pressure.

Rapid depressurization of Low Steam Generator pressure secondary side alarm

i. -[

For accidents involving primary to secondary leakage see "Pri-I mary Coolant System Integrity" I

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3 Proc No E. l Revision 8 Page 32 of 32 SECURITY f

Cl.ASSIFICATION EHERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS Unusual.

Security threat or Attempted entry Security alarms OR Mandatory:

1, 3, 4, 5, 6, Event or Attempted sabotage Observation AND Subsequent:

24, 34 Activation of Safeguards If Heeded:

2, 26, 33 Contingency Procedures.

t Alert Security threat exists that Security Alarms OR Mandatory:

1,2,3,4,5,

{

results in adversaries comman-Observation AND 6, 11, 12, 14, 1

deering an area of the Plant, but Activation of Safeguards 17, 22

.i pot control over shutdown capa-Contingency Procedures Subsequent:

18, 24, 33, 34 If Needed:

19, 25, 26

, bility or of any vital areas g

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!j Site Areai Physical attach?on the Plant Security alarms OR Han4Qory:

1,2,3,4,5,

}

Emergency) involving imminent occupancy of Observatioti AND 6, 11, 12, 13 j

the Control Room, auxiliary shut-Activation of Safeguards 14, 17, 22 1.

4 down panels, or other vital Contingency Procedures Subsequent:

16, 18, 19, 21, 23, 24, 33, 34 areas.

l If Needed:

15, 25, 26 I

/>

T General

Physical attack on the. Plant has,

SecArity alanes OR '

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1,2,3,4,5,

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6, 11, 12, 13,

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Emergency resulted in unauthokized personne), Activation of' S.ife; guards.

14, 17.-22 Observation Alus

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other vitallareas.

' Contingency Pro'cedures>,

Subsequent:

16, 18, 19, 21, 23, 24, 33, 34 h

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EMERGENCY CLASS DESCRIPTION Prce No EI-1 j

Revision 8 Page 1 of 7 t'

UNUSUAL EVENT State and/or Local Off-Site Class Licensee Actions Authority Actions UNUSUAL EVENT-

1. Promptly infoca

1. Provide fire State and/or local or security 4

Class Description off-site authori-assistance if ties of nature of requested.

Ic-Eventr, are :ba pro' ess or have unusual condition c

occurred which indicate a po-as soon as dis-

2. Escalate to a tential degradation of the level-

covered, more severe of safety of the plant.

No-class, if releases of radioactive material

2. Augment on-shift appropriate.

requiring off-site response or -

resources as needed.

monitoring are expected unless

3. Stand by un-further degradation of safety

3. Assess and respond.

til verbal systems occurs.

closecut.

4. Escalate to a more Purpose severe class, if appropriate,

^

Purpose of off-site notification is to (1) assure that the first or 4

step in any response later found to be necessary has been carried

5. Close out with ver-out, (2) bring the operating bal summary to off-

'4-staff to a state of readiness site authorities; and (3) provide systesacic followed by written s.

i handling of Unusual Events sumesry.

information and decision making.

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(.

Revisioi 8 Page 2 of 7 ALERT

/

State and/or Local Off-Site Class Licensee Actions Authority Actions ALERT

1. Fromptly inform

1. Provide fire State and/or local or security Class Description authorities of assistance if alert status and requested.

Events are in process ce have reason for alert as occurred which involve an soon as discovered.

2. Augment re-actual or potential substantial sources and degradation of the level of

2. Augment resources bring primary safety of the plant. Any and activate on-response can-releases expected to be site Technical Sup-ters and Emerg-limited to small fractions port Center and gency Broadcast of the EPA Protective Action on-site Operational System (EBS) to Guideline exposure levels.

Support Center.

standby status.

Bring Emergency Purpose Operations Facility

3. Alert to (EOF) and other key standby Purpose of off-site alert is emergency personnel status key to (1) assure that emergency to standby status, emergency personnel are regdily available personnel in-to respond if situation

3. Assess and respond, cluding moni-becomes more serious or to toring teams perform confirmatory radiation

4. Dispatch on-site and associ-monitoring if required, and monitoring teams ated communi-(2) provide off-site authorities and associated cations.

current status information.

communications.

4. Provide con-

5. Provide periodic firmatory plant status up-off-site ra-dates to off-site diation moni-authorities (at toring'and least every inj estion 15 minutes),

pathway dose projections

6. Provide periodic if actual re-meteorological as-leases sub sessments to off-stantially site authorities-exceed Tech and, if any nical Speci-releases are occur-fication ring, dose esti-limits.

mates for actual releases.

5. Escalate to a more severe class, if

7. Escalate to a more appropriate.

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. severe class, if appropriate.

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ALERT State and/or Local Off-Site Class Licensee Actions Authority Actions

6. Maintain Alert statua

8. Close out or rec-until verbal ommend reduction closeout or in emergency class reduction of by verbal summary emergency to off-site author-class.

ities followed by written summary.

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EMERGENCY CLASS DESCRIPTION Proc No II-l Revision 8 Page 4 of 7

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SITE AREA EMERGENCY State and/or Local Off-Site I

Class Licensee Actions Authority Actions SITE AREA

1. Promptly inform State

1. Provide any assistance EMERGENCY and/or local off-site requested.

authorities of Site Area Class Description Emergency statua and

2. If sheltering near the reason for emergency as site is desirable, acti-Events are in soon as discovered.

vate public notification process or have system within at least occurred which

2. Augment resources by ac-two miles of the plant.

involve actual or tivating on-site Tech-l likely major nical Support Center,

3. Provide public within at failures of plant on-site operational least about 10 miles 2

functions needed Support Center and near-periodic updates on for protection of

' site Emergency Opera-emergency status.

the public. Any ations Facility (EOF).

releases not ex-

4. Augment resources by pected to exceed

3. Assess and respond.

activating primary j

EPA Protective response centers.

. Action Guideline

4. Dispatch on-site and exposure levels off-site monitoring

5. Dispatch key emergency except near site teams and associated personnel including non-boundary.

communications.

itoring teams and asso-ciated. communications.

Purpose

5. Designate an individual for plant status updates

6. Alert to standby status Purpose of the to off-site authorities other emergency person-Site Area and periodic press nel (eg, those needed Emergency _

briefings (perhaps for evacuation) and declaration is to joint with off-site dispatch personnel to (1) assure that authorities),

near-site duty stations.

response centers are manned,

6. Make senior technical

7. Provide off-site moni-(2) assure that and management staff on toring results to li-monitoring teams site available for con-consee, DOE and others are dispatched, sultation with NRC and and jointly assess them.

(3) assure that State on a periodic personnel re-basis.

8. Continuously assess in-quired for

. formation from licensee evacuation of

7. Provide meteorological and off-site monitoring near-sita areas and dose estimates to with regard to changes are at duty sta-off-site authorities for.

to protective actions tions if situs-actual releases via a already initiated for tion becomes more designated individual or public and mobilizing serious, (4) pro-automated data trans-evacuation resources.

vide consultation.

mission.

,,.y with off-site

9. Recommend placing milk

. authorities and

8. Provide release and dose.

animals within two miles,

y, I'

(5) provide up-projections based on a-on stored feed and 9'3'9 :

s..

dates for the vailable plant condition assess need to extend

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EMERGENCY CLASS DESCRIPTION Proc Na EI-1 Attachsunt 2 Revision 8 Page 5 of 7 SITE AREA EMERGENCY State and/or Local Off-Site Class Licensee Actions Authority Actions public through information and fore-distance.

off-site seeable contingencies.

authorities.

10. Provide press briefings,

9. Escalate to General perhaps with licensee.

Emergency class, if app rop riate,

11. Escalate to General Emergency class, if og appropriate.

10. Close out or reconsend

12. Maintain Site Area reduction in emergency Emergency status until class by briefing of closecut or reduction siff-site authorities at of emergency class.

EOF and by phone fol-loved by written summary.

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EMERGENCY CLASS DESCRIPTION Proc No EI-1 Attachagnt 2 Revision 8 Page 6 of 7 GENERAL EMERGENCY State and/or Local Off-Site Class Licensee Actions Authority Actions GENERAL EMERGENCY

1. Framptly inform State

1. Provide any assistance and local off-site requested.

Class Description tuthorities of General Emergency status and

2. Activate immediate pub-Events are in reason for emergency as lic notification of process or have soon as discovered Emergency status and occurred which (parallel notification provide public periodic involve actual or of State / local).

updates.

imminent substan-tial core degra-

2. Augment resources by ac-

3. Recommend sheltering for dation or melting tivating on-site Tech-two-mile radius and five with potential nical Support Center, miles downwind and as-fer ?oss of con-on-site Operational sess need to extend tainment integ-Support Center and near-distances. Consider ad-rity. Releases site Emergency Opera-visability of evacuation can be reasonably ations Facility (EOF).

(projected time avail-expected to ex-able vs estimated evac-ceed EPA Protec-

3. Assess and respond, uation times).

tive Action Guideline expo-

4. Dispatch on-site and

4. Augment resources by s

sure levels off off-site monitoring activating primary site for more teams and associated response centers, than the imme-communicetions, diate site area.

5. Dispatch key emergency

5. Designate an individual personnel including' mon-Purpose for plant statua updates itoring teams and asso-to off-site authorities ciated communications.

Purpose of the and periodic press General Emergency briefings (perhaps

6. Dispatch other emergency declaration is to joint with off-site personnel to duty sta-(1) initiate pre-au thorities).

tions within five-mile determined pro-radius and alert all tective actions

6. Make senior technical others to standby for the public, and management staff on status.

(2) provide site available for con-continuous sultation with NRC and

7. Provide off-site moni-assessment of State on a periodic toring results to li-information from basis.

censee,' DOE and others licensee and off-and jointly assess them.

site organization

7. Provide meteorological measurements, and dose estimates to

8. Continuously assess in-(3) initiate ad-off-site authorities for formation from licensee ditional measures actual releases via a and off-site monitoring as indicated by designated individual or with regard to changes actual or poten-automated data trans-to protective actions tial releases,

mission, already initiated for (4) provide public and mobilizing consultation with

8. Provide release and dose evacuation resources.

eio780-0005c154-89 e

l EMERGENCY CLASS DESCRIPTION Prce No EI-1 Revisio'n 8' Page 7 of 7 GENERAL EMERGENCY State and/or Local Off-Site Class Licensee Actions Authority Actions off-site author-projections based on a-ities aod vailable plant condition

9. Recommend placing milk (5) provide up-information and fore-animals within 10 miles dates for the seeable contingencies.

on stored feed and public through assess need to extend off-site author-

9. Close out or recommend distance.

ities.

reduction in emergency class by briefing of

10. Provide press briefings off-site authorities at with licensee.

EOF and by phone fol-lowed by written summary.

11. Maintain General Emer-gency status until closeout or reduction of emergency class.

t eio780-0005c154-89 1