ML20078C478

Public Version of Rev 10 to Emergency Plan Implementing Procedure 1004.2, Alert

ML20078C478
Person / Time
Site:	Three Mile Island
Issue date:	08/09/1983
From:	Stange S GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20078C477	List: ML20078C478
References
0024W, 1004.2-01, 1004.2-1, 24W, NUDOCS 8309270618
Download: ML20078C478 (37)

Text

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1004.2 Revision 10 08/09/83 IWORTANT TO SAFETY <y NON-ENVIRONMENTAL IWACT RELATED 0"b g THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IWLEMENTING PROCEDURE 1004.2 i ALERT ,

Table of Effective Pages

Page Revision Page Revision Page Revision Page Revision 1.0 9 31.0 9 2.0 9 32.0 9 3.0 9 33.0 9 4.0 9 34.0 9 5.0 9 35.0 9 6.0 9 36.0 9 7.0 9 8.0 9 9.0 9 10.0 9 11.0 9 9

12.0 9 13.0 10 14.0 9 15.0 9 16.0 9 17.0 9 18.0 9 19.0 9 20.0 9 21.0 9 22.0 9 -

23.0 9 24.0 9 25.0 9 26.0 9 27.0 3 28.0 9 29.0 9 30.0 9 Y

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Th y Signatureg ' Date Signature

-h- Date 8309270618 830922 Document ID: 0024W e DRADOCK05000g 7 L' r o I

• , , .; 10 04.2 6 -

Revision 9 THREE MILE ISLAND NUCLEAR STATION .

UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.2 ALERT 1.0 PURPOSE The purpose of this procedure is to define the conditions that shall be ,

reganied as an Alert for Three Mile Island Nuclear Station (Unit I) and to:

a. Ensure necessary actions &m taken to protect the e and safety ,

c of the public.

b. Ensure necessary actions are taken to no i . clear management and offsite en y response omani .

c. Mobilize th' a nriate portions f mergency response organi-zation t ni te appropriate rg y actions.

The Emerg i or is respons implementing this procedure.

NOTE: The Emerge tor is vested w certain auth-  :

ority sibility that e delegated  :

to a . Included  :  :

A. C ation of an en '$ vent.  :

B. and directi 41 notifications  :

ite agencies.  :

. roving and direct omation releases to  :

media.  :

proving and, ble, personally conveying :

appropriate P Action Recommendations to :

the Bureau of Ra on Protection.  :

E. Dimeting onsite evacuation at the Alert or  :

< : lower level emergency classification based on  :

potential hazard to non-essential personnel.  :

F. Authorizing emergency workers to exceed 10 CFR 20 :

,: Radiation Exposure Limits.  :

G. Approving and directing deviation from estab.  :

lished operating procedures, ememency operating :

procedures, normal equipment operating limits or :

technical specifications during attempts to  :

control the emergency. (Note: It is imperative :

that the Emergency Director consult to the  :

fullest extent practicable with the Parsippany  :

Technical Functions Center in arriving at a  :

decision to deviate from prescribed procedures). :

h 1.0

~'.~ o 1004.2 Revision 9 When the designated Emergency Support Director (ESD) arrives at the site and declares himself to be ready to assume that role, he will assume l overall respons'ibility for management of the response to the accient and recovery operations. With activation of the ESD function, the ESD ,

specifically will assume decision authority for Items C and D. However, decision authority for Items, A, B, E, F and G will be rethd by the Emergency Director (ED). Decisions on all of the lis s nonna11y will result from close and continuous consultation t the ESD and the ED and it is the responsibility of the ED the ESD is

provided with the ne information to a t timely and appropriate deci ,

the special ca vent classification, the ESD shall retai e erogative to o b l he ED if, in the judgment of the ESD ty or other c ions exist to the extent warranting c ification of Ab evel of emergedgy than that classified by the ED.

2.0 ATTACHENTS 2.1 Attachment I, rt Notifications 2.2 Attachsen Emergency Status 2.3 Attach , Checklist for No tion of Significant Events Made In AcD6rdance with 10 CFR 50.72.

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1004.2 Revision 9 3.0 EERGENCY ACTION LEVELS i

, , 3.1 Radiological Controls and Containment Integrity l

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f Initiating Condition Indication 3.1.1 Radiological effluent activity As indicated by any of the .

exceed the Environmental technical following validated by sample I

specification instantaneous limits. and analysis:

a. RM-A8 (ga > 2.0 x 104 cpm (Hi ) but <

l 1.0 x 1

b. RM-A 5 x 104 cps ) but <3.0

c. .0 x 106 cpm.*

d , dine) increase >

.5 cpm / min but < --

x1 cpm / min.*

A9 (igdine) increase >

Q 2.5 x :.03 cpm / min but < --

0 .

1 x 100 cpe/ min.*

Offsite Radiological Monitoring Team reports >

10 mR/hr (gamma) but <50~

mR/h at any offsite locai n.

g. L Radiological i

Mo g Team reports quivalent I-131 gs at an offsite on of 5 mR/hr

.2 x 10N>Ci/cc) to d50 mR/hr (<1.6 x 10 7

@.pCi/cc). RM-L7 >1.0 x 103 ep, (high T1 arm).

1. RM-G8 1 6 0 x 103mR/hr.

3.1.2 Radiation levels or radioactive As indicated by eit'her:

contamination which indicate a a. Valid, unanticipated high severe degradation in the control alams on any two area of radioactive materials. and/or process radiation monitors (RMA, RM. or RMG monitors) at the same time.

l These indications may be determined via instrumentation that will be l installed or expanded as required by NUREG 0578 prior to restart.

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1004.2 l Revision 5 l

Initiating Condition Indication

b. Receipt of a validated

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report of airborne or waterborne contaminants

- as detemined by sample and analysis or general

• radiation readings as detennined by periodic survey to have increased by a fact f 1000 above normal.

3.1. 3 Fuel damage accident with release An acci s while of radioactivity to the contain- handlin uel during ment or fuel building. refue i hile moving ob the spent fuel wh causes any one of lowing:

a. alid High alarm on RM-A2.

i . A valid High alarm on RM-A4.

c. A valid High alam on RM-A8.

d. A valid High alarm on RM-A .

e. A va High alarm on R

f. vali igh alarm on i @ A id increase by a ctor of 100 of atmos-eric activity as determined by sample and 3.1.4 Reacto o nt pump failure at power leMing to fuel damage.

O analysis.

As indicated by both of the following:

Receipt of a valid RCP a.

Motor Overload alam and decreasing flow in the affected loop, and

b. Reactor Coolant specific activity as detemined by sample and analysis is

>50 uC1/ml but <3850 iici /ml.

(RML1 Lgw >6 x 104 CPM t Ut

<1 x 100 CPM and/or RML1 High >l x 103 CPM but >2 x 103 CPM).

4.0

1004.2  !

Revision 9 Initiating Condition Indication '

3.1.5 Reactor Building pressure Reactor trip and ECCS 140 psig, but <30 psig. initiated due to high Reactor

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Building pressure.

3.1.6 Reactor coolant total activity Asindicatedbyeither:

>3850 pCi/ml but <18,300 pCi/ml a. Reactor coolant activity -

and/or Dose Equivalent Iodine-131 as detemined by sample

>300 pCi/ml but <1430 pCi/ml and analysis.

Tndicating fuel cladding failure. b. RM-L1 Low ffScageHigh) i

c. RM-L1 Hi x 10 cpm but <1 .

3.1.7 Secondary system actisity As indii ample and

>1.0 pCi/ml (I-131 equivalent). analys1.

3.2 Security l

l 3.2.1 Security of ty (Protected i upervisor's judgement Area) is thr y unauthorize sed on infomation from the entry of Owner Controlle 4 Security Sergeant.

Area).

3. 3 Gen Status 3.3.1 Othe nt conditions n Whenever lant conditions progress or have occu h warrant as judged by the

! may involve an actual tial , Shift isor/ Emergency substantial degra Director.

l level of safety lant. NOT : I xercising the l

gement as to the eed for declaring an Alert, uncertainty concerning safety status of the plant,

@ the length of time the uncertainty exists, the prospects for early resolution of ambiguities, and the potential for substan-tial degradation of the level of safety of the plant should be j considered; i.e.,

l uncertainty as to the l existence of substan-l

' tial degradation of the level of safety of the plant extending beyond a reasonable time period is a sufficient basis fer declaring an Alert.

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. 1004.2 Revision 9 Initiating Condition Indication 3.4 Pressure, Temperature and Inventory Control 3.4.1 Primary coolant leak rate of As indicated by increased greater than 50 gpm. makeup flow in excess of

. letdown flow by 50 gpm Gr ,

makeup tank level decreasing at approximately 2 inches per i minute or greater.

3.4.2 Primary to Secondary leakage: As indicated  ;

a. Total primary to secondary a. Valid al on RM-A5 leak rate >50 gps. -

High conjunction with I tank level approximately minute or rea .

b. Total prima secondary k rate determined by leak rate d <50 gpm y leak rate test or AND loss ite power. keup tank level 9 decrease up to 2 inches / minutes with previous indication of tube leakage (RM-A5 Lcw Range in High Alam) in conju ion with an indi failure of off wer.

c. Total primary n ry leak c. tk ra determined by rate >l gym an pm AND ak rate test or a steam lin tank level ase up to 2 hes/ minute with a apid unanticipated decrease in steam pressure or activation of the Steam Line Rupture Detection System (SLRDS) or visual indication of a steam line break.

d. Total primary to secondary leak d. Leak rate detergined by rate >l gpa and <50 gym AND daily leak rate test or a losi of condensor, makeup tank level decrease up to 2 inches / minute with previous indication t

NOTE: 50 GPM = 1.67"/ min. : of tube leakage (RM-A5

on'the makeup tank  : Low Range in High Alarm)

because this is diff-: in conjunction with con-

cult to see the 2"/ : densor vacuum <23 inches

min. value is used. : Hg or less than 2 circu-

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lating water pumps oper-ating. .

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I 1004.2 Revision 9 Initiating Condition Indication 3.4.3 Reactor Coolant System hot leg As read on Reactor Coolant temperature is 16 20*F in either Outlet Temperature indication.

loop.

3.4.4 Non-isolable steam leak that As indicated by a Steam Line results in a rapid depressuri- Rupture System actuation -

zation of the steam system. (<600 psig) on the affected 0TSG.

3.5 Electrical Power -

3.5.1 Loss of all offsite power coin- As indic reactor cident with a loss of both Diesel trip ca loss of power Generators for less than 15 and res on both minutes, Die tors neither of l izes the ID or IE '

sses.

3.5.2 Loss of al DC power for attery Voltmeters read less tha s. and there is no light or ntr'oT power available.

3.6 Ins ta on and Actuati s s 3.6.1 Most o M 11 annunciato As judge y the Shift Super-which may involve an visor.

potential substanc a-tion of the level of

, the plant.

i 3.6.2 Failure of t c protection r trip setpoint system to and complete exceeded with no rod a trip ed. i mit lights.

3.6.3 Comp 1 of any function bindicatedbyatotalloss needed p ant cold shutdown of any of the following:

V a. Source and intennediate range nuclear instrument-4 tion.

b. A loss of forced reactor coolant system flow (include Decay Heat Removal Pumps, Reactor Coolant Pumps, etc.)

coincident with total loss of ability to feed OTSG's.

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1004.2 Revision 9

> Initiating Condition Indication 3.7 Natural or Man-Made Phenomena 3.7.1 Severe natural phenomenon being As indicated by any one of the experienced. following:

. a. Valid alarm on PRF 1-3, ,

" Operating Basis Earth-quake".

b. Actual river stage >302 feet but < eet at the River Wa ke Struc-e ture.

c. Proj r stage

<271 t the River e Structure.

d. o striking aci .

ricane winds >75 mph a ndicated on The Wind 9 peed Recorder.

3.7.2 Other ha ing experienced indicated by any one of the following:

a. Aircraft crash or other missile impact within the prot d area or onto an nent plant '

s

b. exp sion damage to t ure.

nent plant Re ase of toxic or able gasses into the lant which, in the C judgement Supervisor, affects ofthethe Shift safe operation of the plant. <

d. Turbine failure resulting in casing penetration.

e. Any fire in a permanent l plant structure which requires cffsite fireffghting capabilities.

3.7.3 Any fire jeopardizing the opera- As judged by the Shift Super-bility of any safety system.

visor.

3.7.4 Evacuation of control room anti- Shift Supervisor's judgement.

cipated or required with control of shutdown systems established from local stations within 15 ___ ._

minutes. -

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1004.2

. . Revision 9 Initiating Condition Indication -

3.8 Reactivity Control l l 3.8.1 More tha'n one control rod Stuck- As indicated by a loss of the l Out, Stuck-In or Dropped requiring ability to meet any of the l shutdown by Technical Specifica- conditions of Technical Spec- i tions. ification Limiting Condition

• for Operation 3.5.2.2 for more than one control rod.

i 3.8.2 Control Rod Ejection. As indicated actor Trip due to tron flux

in coinc th loss of

coolant ns.

J l 4.0 EMERGENCY ACTIONS Initials 4.1 Upon recogni any of the a et on levels have been 9

reached ed, the Shift pe sor/ Duty Section Su assume the d the Emergency Director. (The even uld be assesse ared within 1, minutes of its i

occurrence.)

4.2 Announce to Contr personnel that AA has assumed the d rgency Dir mergency Director shall peri (approx. every sult with the lead personn 1 area involved emergency, and discuss:

a. Stat f each area

b. Ilumediate actions to be taken by each lead person

c. -Problem areas

d. Recommendations on course of action.

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1004.2 Revision 9 4.3 Announce, or have announced, the following message over the public address system (merged):

' NOTE: Turn on Whclen siren switch.  :

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" ATTENTION ALL PERSONNEL; ATTEKTION ALL PERSONNEL: AN ALERT HAS i

BEEN DECLARED IN UNIT 1. ALL MEMBERS OF THE ONSIT ENCY ORGANIZATION REPORT TO YOUR STATIONS. ALL OTHE L AWAIT i

FURTHER INSTRUCTIONS." (If emergency is radia n. ented add:

"There will be No Smoking, Drinking, or E n til further notice.") (Giv (h kipf description o h ent and repeat the i <

Q announcemen .

4.4 If emer e i diation. orient d. i ct that the Radiation Energ larm be sounded.

NOTE: Turn off Whe n switch afte has been  :

sour.ded.  :

4.5 Assign a Commun o make notifica to ersons and/or agencies pe nt I, Section 4.6 Assign a. tions Assistan nd rect him to perform all applicabl eps of 1004.8.

l 4.7 Contact the Duty Section Superintendent and discuss:

a. Plant status

b. Which members of the Duty Section are required to augment the Onsite/Offsite Emergency Organization.

4.8 Depending on the emergency action level which was reached or exceeded, ensure that the appropriate Emergency Operating- -

Procedures have been implemented.

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• 1004.2 Revision 9 4.9 If local services (fire, ambulance, police) are required, direct the Coinnunicator to notify Dauphin County Emergency Operations Center and request the appropriate assistance. Notify Security (N/S Gate) to begin preparations to expedite entry of responding .

emergency personnel (Police / Fire / Ambalance). Security should be advised to implement procedure 1004.19 Emergency Se / Dosimetry Badge Issuance.

NOTE: If the Emergency Response pers required to  :

respond outside the protect ffected by a  :

rad ;ive plume the Ese Di tor or his  :

d ill direct the i of TLD's from the  :

uth gate.  :

9 ___________........___...

4.10 If the involves radio a problems, direct trie Radi al Assessment Coo n to implement Radiological Control uring Emerge .9).

4.11 If changes in onsit o te radiation leve expected, direct the Radio sessment Coo o:

a. Di spatch te and/or onsite d monitoring teams in acc e th EPIP's 1004 .

b. Onsite Offsite Dos jections procedure (1004.7).

4.12 If personne / vehicles are, or are suspected to be contaminated, have the RAC initiate the Personnel / Vehicle Monitoring and Decontamination procedure (1004.20).

4.13 Activate the Technical Support Center, procedure (1004.28), and the

. Operations Support Center, procedure (1004.29).

4.14 If additional resources or notifications are required, refer to Additional Assistance and Notifications procedure (2004.6).

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• 1004.2 Revision 9 4.15 Assign an individual to complete Attachment II,Section I and gin it to the Radiological Assessment Coordinator to transmit to the '

Bureau of Radiation Protection.

4.16 Direct the Radiological Assessment Coordinator to complete .

Attachment II,Section II to transmit to the Bureau of Radia- tion Protection if a radioactive release has occurred or urring.

4.17 Stop all liquid and gaseous discharges that are ss until an assessment of their impact is perfonned an ec ic approval is given to continue the release by the Emer n rector.

4.18 Verify that c tions and documen re maintained per

! procedure C fons and Recordk (1004.5).

4.19 If applic rect the Operat Chdrdinator to dispatch Emer e r/ Operations rs to investigate the identified problem M a(s) in accor t Emergency Re ir/ Operations procedure 1004.21.

4.20 After 30 minutes f fal contact wi onfinn that BRP verification h n made. If no ve at n, instruct the comununicat eed to Attac tion 1.2 (d).

4.21 Instruc fological Asses edinator to provide ongoing dose estima s for actual releases to the Bureau of Radiation Protection.

4.22 Evaluate dose projections and estimates and if necessary, recommend protective actions to the BRP consistent with the guidelines in

, Attachment I,Section IV.

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1004.2 Revision 10 4.23 If personnel are injured or ill and are in a radiologically  !

controlled area or are potentially contaminated, or if person (s) have received radiation exposure greater than 25 REM; direct the RAC t'o implement Emergency Plan Implementing Procedure 1004.16, i Contaminated Injuries / Radiation Over-exposure.

4.24 If person (s) have been exposed to 1 1 31 sufficient to ea thyroid dose of greater than or equal to 25 RAD the RAC to implement the Thyroid Blocking Procedure F.mers an Implementing Procedure 1004.35.

4.25 Based upon ass f plant conditio s, er close out the

! Alert, ese higher class of ncy or downgrade to a lower c s i a. covery Phase crite been met (see Recovery Procedure 1004.24) g tem recovery erations are not necessary, clo Alert by performi notifications in Attac ion III.

b. If Reco ase criteria have t met, but Alert ese a ion levels are er being exceeded, de- to an Unusual Eve y notifying BRP on the Radiological Line and perfom the remaining notifications in accordance with the Unusual Event procedure (1004.1).

c. If emergency action levels exceed those for an Alert, escalate to a higher class, notify BRP on the Radiologif.21 Line and make the remaining notifications in accordance with the appropriate emergency procedure as specified in Step 5.1.

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.. 4 1004.2 Revision 9 4.26 If necessary, due to potential contamination of normally non-contaminated sumps and/or tanks, or the need to closely monitor liquid reieases, initiate procedure (1004.14),

Monitoring / Controlling Liquid Discharges. .

5.0 FINAL CONDITIONS -

5.1 A higher class of emergency has been declared by the gency Director after meeting or axceeding an emergency evel of one of the higher classes and one of the follo ce- dures is being implemented.

a. Site Emerg .3)

b. General y (1004.4) p 5.2 A lower cl rgency has b e d ared by the Emergency Direc d' Unusual Event p e (1004.01) is being implemented.

5.3 The Alert as been close ce no recovery erations are required.

5.4 The Alert can be s o a recovery e lementing the procedure Reco perations (1004.2 .

S.5 At the clo hY Emergency, en all logs, check- lists, procedu a ther documentatio rated in the Control Room associated Mth the event are gathered and sent to the Emergency

Preparedness Department for review and filing.

s Date Signature of Person Responsible for Implementing Procedure j 14.0 l

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' ' 1004.2 Revision 9 ATTACHMENT I Section I _

Initial Contact The Communicator shall notify the following agencies and personnel and update ,

the Attachment I,Section II checklist for each notification.

Initial

1. Dauphin County Emergency Operations Center (If this is a reclassification notification vise BRP via Radiological line or 9-787-3720 then una c ontrol Room) go to Itan 3.

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a. Teleph 11 or 9-236-7976 9

1. n ontact, activat up n County radio system.

b. E:

Thi s A at the Thre ile Island (name )

Nuclear Stati I calling. We lared an Alert (t1 (Bas o mergency Direc ment, deliver one of the fo i statements):

1. W have not had a radioactive release OR

2. ' We have had a radioactive release, but do not expect this I

situation to result in datectable changes in offsite

, radiation levels, OR l

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' 1004.2 l Revision 9 ATTACHMENT I 4

Section I i

4 Initial Contact

! Initial .

3. We have had a radioactive release, but do not know if there will be a detectable change in offst adiation levels. We will be keeping the Burea ation Protection informed of the results nvestigation, 4.

We ha radioactive rel

% d expect to be able l t hanges in offs 1 egr ation levels, but they l ected to be les an he levels calling for a

{ Site Emergency. W keeping the Bureau of Radia-ion Protectio d.

l . c. Give a short no h 1 description o rgency and the extent of inactive rele e affected l populatio area.

Ab M M -

2. Pennsylva Emergency Management Agency (PEMA)

(If this is a recla,ssification notification, go to Item 3, Un-I affected Control Room.)

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. 1004.2 Revision 9 ATTACHElfr I Section I Initial Contact Initial -

a. Telephone: PEMA Dedicated Line (Use only during NORMAL work hours 08001600 hrs. Monday-Friday) or 9 783 81 Use when the dedicated line is out of service or aft work hours. A diverter forwards this after n 1 rk hours chil to the PEMA Duty Officer).

NOTE: If o contact, pr ed t step 2.d.  :

9._

b. ES  :

is hree Mile Isla r Station Unit I calling. We havv an emergency. the Operation uty Officer.

(When Duty Offt a rs:)

This is k(

' naggp1 tie)'

at e V

Mile Island Nuclear n Unit 1 callin ve declared an Alert at hours.

(My)

We re st you contact Bureau of Radiation Protection. Bureau of Radiation Protection callback should be made on the Radio _

logical Line.or 948 8069, 948 8071 or 944 0839. (Based upon Emergency Director judgment, deliver one of the following -

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statements):

1. We have not had a radioactive release, OR 17.0

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' ' 1004.2 Revision 9 ATTACHMENT I Section I Initial Contact

2. We have had a radioactive release, but do not expect this .

! situation to result in detectable changes in offsite radiation levels, OR

3. We have had a radioactive release ot know if there will be detectable chan site radiation level ill be keeping e au of Radiation P informed of the 1%s s of our investigation,

. We have had a radi release and expect to be' able to detect cha ffsite radiatio levels but they will be le e levels calling Site Emer-gency. be keeping t f Radiation Pro informed,

c. Give on-technical i n of the emergency, and a ally affected pop ons and areas:

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' 1004.2 Revision 9 ATTACHMENT I Section I Initial Contact Initial .

d. If PEE is unable to be contacted, contact Dauphin County; advise them that PEMA cannot be contacted and them to notify PEM, BRP, and Lancaster, York, Le Cumberland counties.

e. Message verification:

Expect Bu adiological Prot t (BRP) contact after PEM n on. If no BRP c tion is received within 3 notify PEm of si uation. If unable to ct PEM (line bus auphin County and notify them tha BRP has not v nitial contact. equest Dauphin County to cont nd/or BRP.

3. Unaffected Contrg,1 v

a. Tel :8066, Po67, 8068 Control Room Hot Line.

b.  : Give a brief t on of plant status to Supervisor.

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1004.2 Revision 9 l

ATTACHENT I Section I Initial Contact Initial ,

4. Institute of Nuclear Power Operations (Do not notify if this is a reclassificati notifica-tion.)

a. Telephone: 1-404-953-0904 or the TMI Site Operator for assistance

b. GE:

T \v 6 Vt Three Mile Island (name/ title)

. Station Unit 1 ing. We have declared an Alert at (Give a brief description of the emerg

. />

/4 " AV A% M

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5 the following p 1/ agencies if the emergency wtuation is such that notification is deemed appropriate.

a. Hershey Medical Center 9-534-8333 (ask for Duty Nurse)

Notification to be perfonned per procedure 1004.16.

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1004.2 Revision 9 ATTACHIENT I l Section I Initial Contact Initial ,

b. Pennsylvania State Police 9-234-4051 MESSAGE:

This is at e Mile (name/ title)

Island Nuclear Station Unit . We have 1

i declared an Alert at // ho . We

( (have/have not) a radioactive r e We require assistance as llows: (S istance required.)

c. Radiation Ma orporation (RMC)

Av Eme es h 0-1700) 73- -215-243-2990 (1700-0800) -

15-841-5141 e (0800-17 215-243-2950 is & at the Three Mile Island Nucle r Unit I calling. We have

declared an Alert at hours. (Give a brief (time) description of the emergency). We (have/have not) had a radioactive release.

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1004.2 Revision 9 ATTACHENT I Section I Initial Contact Initial ,

d. American Nuclear Insurers 74-1-203-677-7305 or 9-1-800-24 /3173 (after n ing hours)

Message

This is A Three Mile (name/ title)

, Nuclear Station calling. We have red an Alert atCN hours (Give a brief f el escription of th rgency).

We n had a radioactive release.

n- u

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1004.2 Revision 9 ATTACHENT I .

Section I Initial Contact Initial .

4. Nuclear Regulatory Comission (NRC) - Bethesda, MD.

(Continuous communications with the NRC will be mai ed follow-ing contact.)

a. Telephone: NRC Emergency Notification S NS) (RED PHONE)

(If ENS Phone 1.s inopertative, refer rgency Plan Imple-menting Pr 1004.6 "Additi sistance Notifica- -

tion"

• rnate methods). p

b. ES  :

is at the Three Mile Island (name/t1 y Nuclear Station Un ling. We have lared an Alert (time)

(Based u rgency Director d , use one of the fol nts):

1 ve not had a radi e release

2. We have had a radioactive release but do not expect this situation to result in detectable changes in offsite

. radiation levels.

OR 23.0

1004.2 Revision 9 ATTACHENT I Section I Initial Contact Initial ,

3. We have had a radioactive release but do not know if there will be a detectable change in offs radiation levels. We will be keeping the Burea o ation Protection informed of the results o investigation.

4. We have had a radioactive role e xpect to be a'le b

to d hanges in offst tion levels but they ess than the le $ ling for a Site Emer.

l n We expect th vel to be <50 mrem /hr (gam a) and I child thyroid dos c nt to be <250 MREM /hr.

We will be k Bureau of Ra tion Protection informed.

c. (Give a sho, on hnical descr t the emergency, the extent radioactive role e, f ny, and the potentially aff ations and a f ppropriate).

A N

DATE TIE OF COMPLETION C0W LETED BY P

NOTE: After initial NRC notificaion is complete per  :

Attachment I,Section I above; Refer to the NRC  :

Notification Checklist. Attachment III. This  :

Checklist contains information desired by the NRC  :

and may be helpful in providing follow up  :

__ _; information.  :

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I 1004.2 .

R:visien 9 ATTACHMENT I .

SECTION II NOTIFICATION CHECKLIST

, :I  : .

TIME OF INITIAL NOTIFICATION TIME OF .

OR ESCALATION DE-ESCALATION OR CLOSE OUT  :

A  :

::UNU5UAL:  : SITE :G  : UNUSUAL:  : SIIt.  : GENERAL :

AGENCY  :: EVENT :  %: EERGENCY :EME Y:;-EVENT : ALERT : EERGENCY : EERGENCY :

r:  : -

Dauphin County

y: /,t (f .

I .  :

IF V8}f/ e

PEMn V/m@ _ -l:  :  : $

/  :  :  :

Unit 2 Control Room  ::  : (  :  :: U  :  :  :

INP0 vg: (N

NRC (f:if

.y N)A :: ..

$HersheyMedicalCenter $ * :$ M1 *$ m: $ $ $ $ '

State Police

• y .

A *:

p::  :

RMC  :: *: * ,

I A* : * : :3'V f . -

::  :  : V // : A:  :  :

ANI  :: *: *: (/ h

y . //A  :  :

B and W

N/A : N/A :

: N J: p

/f

y (f(f'

::  :  : ";  : "Uf I

//l /) ::

5 Affected Counties  :: N/A : N/A : N/A  :  ::  :  :

i

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• Optional 25.0

1004.2 Revision 9 t ATTACHENT I Section III Secondary Contact Initial The Communicator shall notify the following agencies and personnel and update the Attachment I,Section II' checklist for each no ation.

1. Announce or have announced the following message lant page after turning on whelen sirens " ATTENTION ALL L. ATTENTION ALL PERSONNEL. The Alert has been termina e a brief de-scription of the strictions, if Repeat message and turn off whe s.

9

2. Bureau of a n Protection

a. T W

ne: Radiological -787-3720

b. MES .

This is m - he Three Mile I clear Station

', (name/t Unit 1. W c osed out the Al _t hours and v (time) init overy operations se notify PEMA, Dauphin, Lancas York, Lebanon and Cumberland counties.

3. Unaffected Control Room

a. Telephone:8066, 8067, 8068

b. Message: Notify Shift Supervisor / Foreman of CLose out of the Alert.

4. Nuclear Regulatory Commission Office - Bethesda, Md.

a. Telephone: Emergency Notification System (ENS)

(RED PHONE) 26.0 c_- - _ A

1004.2 Revision 9 ATTACHENT I Section III I Secondary Contact

. Initial . ,

1

b. ESSAGE:

,This is at the Three Mile I d Nuclear (name/ title)

Station Unit 1. We have closed out the hours (time) and initi very operations.

5. If applica ,n the following y and/or agencies of close t Alert:

Hershey Medical Ce e* -534-8333 (ask for Duty Nurse)

b. Pennsylvania ce: 9-234-40

c. Radiation)tene Corporation (

encies (0800-1 -215-243-2990 (170 3-1-215-841-5141 Office 7 ) 73-1-215-243-2950

d. can Nuclear Insu 4-1-203-677-7305

e. 'ers - as directed by the Emergency Director.

DATE TIME OF COMPLETION C0W LETED BY

.x

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1 I 1004.2 Revision 9 -

l ALERT f

f ATTACHENT I SECTION IV PROTECTIVE ACTION RECOMENDATION GUIDELINES l THESE RECOMENDATIONS MAY BE DELIVERED ONLY BY THE EMERGENCY DIRECTOR ,

i j 1. Consideration shall be given to sheltering if:

) a. Release time is expected to be short (Puff re a , <2 hours) and

b. Evacuation could not be well underw o expected plume i arrival du ort warning time wind speeds, and/or j foul .

9 l 2. Consideration s 1 given to evacu n .

1

! .. a. eas is expected ith projected doses approach-l i r exceeding:

j 1 Rem Whol o d/or

. 5 Rem Ch id i d l b. Rele. s expected to g >2 hours) i and l

l c. Evacu on can be well underway prior to plume arrival for I

above release, based upon wind speed and travel conditions.

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1004.2 Revision 9 ATTACHENT 17 EERGENCY STATUS REPORT Section I

1. Description of emergency: ,

A

2. Has the Reactor tripped Yes/No

3. Did the Emergency Safeguards Systems actuate le

/( M If so, which on

a. High Pr s Injection o

b. Low ss Injection /No

c. r FTKd Yes/No

d. 4 PUG Reactor Buil Is tion Yes/No

e. Reactor Buildin p ctuated Yes/No

, 4. What is the status of t

a. At power

b. Mt .

C. .

d. Cool Down

e. Reactor Pressure p ,,1 g

f. Reactor temperature *F 1

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1004.2 '

I Revision 9 ATTACHENT II EERGENCY STATUS REPORT Section I

5. Is offsite. power available Yes/No ,

6. Are both diesel generators operable Yes/No

7. Have any personnel injuries occurred Yes/No

a. If so, is the injured person (s) contaminated V

1. What are the approximate radiation d/ ontamination levels M mR/hr DPM/100 cm v D

8. Are these exce diation levels or ontamination Levels

Yes/ '

~

a. I , List below:

1. Radiation we ole Body)

. 2. Contami evels D

% x s O DATE TIE COWLETED BY

..--emm-30.0

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1004.2 Revision 9

. ATTACHMENT II EERGENCY STATUS REPORT Section II Fill out if a release has (is) ocurring. Provide BRP all available informa- ,

tion for verification call.

1. What is the approximate radioactive soun:e ters discharge e from the plant (As determined by the Projected Dose Calculat dure (1004.7).)

a. Noble gases Ci/sec

b. Iodine . k Ci/sec

2. What is the appr teorology

a. Wind spee ph v

b. Win tion -

c. Stabili Class-Stable / nstable

3. What is the projected who o se rate and to centration at the nearest offsite do int

a. /hr

b. \ 1/cc Iodine

c. (Location)

4. Estimated dura of the release

a. If the release is terminated:

Start time Stop time Duration

. b. If the release is still in progress:

Start Time Estimated duration (hrs / min /sec) i l -..

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l 1004.2

Revision 9 i

ATTACHENT II EERGENCY STATUS REPORT i

Section II l 5. a. Based on projected dose rates, fodine concentration and duration or ,

estimated duration (if still in progress) of the release, will the l

lower limits of the EPA Protective Action Guides be eded (i.e.,

l '1 Rem Whole Body, 5 Rem Child Thyroid.

Yes/No l

b. If yes, estimate time to exceeding PAG: m urs 1

~

Date 1me Complete

% Completed By m

~

% O e

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l 1004.2 Revision 9

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ATTACHENT III

CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS DEDE IN ACCORDANCE WITH 10 CFR 50.72 A. Identification

,

! Date Time Name of Person Making Report

Licensee Facility Affected A Applicable Part of 10 CFR 50.72

'V

B.

Description:

Date of Event Time .b Description of What

'V C. Consequences of E omplete dependi g pe of event)

Injuries Fataliti Contaminat nel) (property)

Overexposures nown/possible)M A Safety Hazard (describe - ntial)

. />

Offsite Radiation L \

Integrated Dose _ b v Lo Meterology ( d d)  ; direction)

Weather Conditi (rain, clear, overcast, temperature)

Equipment / Property Damage

! D. Cause of Event:

l ,

j.-e O

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7.. ,

1004.2 Revision 9 ATTACHENT III J CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 E. Licensee Actions: ,

Yaken Planned b Emergency Plan Activitated (Yes/No) Classificat encyl Resident Inspector Notified (Yes/No) Sta (Yes/No)

Press Release Planne ) News M terest (Yes/No)

F. Current Statu : ete depending t

~

1. Reac stems Status Power Le 1 Before Even Afte vent Pressure n . (thot I cold-- I RCS Flow (Yes/No Pumps On ( s v v Heat Sink: C er Ste up Other le Taken (Y Activity Level ECCS 0 Yes/No) Operable (Yes/No)

ESF Actuat n (Yes/No) _

l PZR or RX Level Possible Fuel Damage (Yes/No)

.S/G Levels Feedwater Soun:e/ Flow _

Containment Pressure Safety Relief Valve Actuation (Yes/No)

I see Emergency Action Levels, Appendix 1. NUREG-0654, Revision 1. Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

N m .

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1004.2 Revision 9 ATTACHENT III

, CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72

! Containment Water Level Indication .

l Equipment Failures b Nomal Offsite Power Availabe (Yes/No) m Major Busses / Loads Lost h Safeguards Busses Power Source />

D/G Running ( L Y s/No) __

i

! 2. Radioacti se Q Liquid b L cation / Source

! Re1 te Duration Stopped Yes/No) A Release tored (Yes/No)

Amount of Release A Tech Spec. Its Radiation Level t Ar ted l 3. Security /Saf s2 Bomb Th xh Conducte o) Search Results Site a (Yes/No)

Intrusion: Insider Outsider Point of Intrusion Extend of Intrusion i

Apparent Pu nose Strike / Demonstrations: Size of Group

. Purpose 2 See 10 CFR 73.71(c), effective April 6, 1981.

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- 1004.2 Revision 9 ATTACHENT III CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS l

' MADE IN ACCORDANCE WITH 10 CFR 50.72 batoge: Radiological (Yes/No) Arson (Yes/No) ,

Equipment / Property Extortion: Source (phone, letter, etc.) h Location of Le' ster _

j Demands ((

General: Fireams involved (Yes/No) x ce (Yes/No)

Control of Faci prosised or Th (Yes/No)

Stolen / Mis tal b i Agencies (FBI, State P e cal Police, etc.)

b 5 Media rest (present d)

@ v s O s

E 36.0

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