Text

Public Version of Revised Emergency Plan Implementing Procedures 1004.3 Re Site emergency,1004.4 Re General Emergency & 1004.12 Re Environ Monitoring
	ML20090G868
Person / Time
Site:	Three Mile Island
Issue date:	10/06/1983
From:	Stange S; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20090G861	List: ML20090G868;
References
	PROC-831006-01, NUDOCS 8310270125
	Download: ML20090G868 (74)
	v • d • e

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1004.3 a3 Revision 12 -F. .

r 10/06/83

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IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.3 SITE EMERGENCY ,

Table of Effective Pages ,

Page Revision Pflge Revision Page Revision Page FWision 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 7.0 9 8.0 9 9.0 9 tp 10.0 9 11.0 12 12.0 12 13.0 12' 14.0 9 15.0 9 16.0 9 .

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Signaturg Date Signature

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Document ID: 0025H b

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1004.3 Revisidn 9 - !

THREE MILE ISLAND NUCLEAR STATION

, 3 UNIT NO.1 EERGENCY PLAN IWLEMENTING PROCEDURE 1004.3 SITE EMERGENCY 1.0 . PURPOSE -

The purpose of this procedure is to-define the conditions that shall be

!- regarded as a Site Emergency for Three Mile Island Nuclear S n (Unit 1) and to: '

! a. Ensure necessary actions are taken to protect t.e e h and safety of the public.

b. . Ensure necessary are taken to no f Nuclear management and offsite response organi t)o .

c. Mobilize th ncy response o iza ons to initiate appro.

j priate ency actions.

The Emergency D tor is respo r implementing is procedure, r /

I i

NOTE: The Emer rector is veste h e tain :

authori '

sponsibility a ot be :

dele subordinate. are: :

a. ification of an rg event. :

b ing and directi tal notification to :

e agencies. .

: oving and dire ing i formation releases to :

he media. :

Approving and, if pos ble, personally conveying :

-appropriate Protective Action Recommendations :

to the Bureau of Radiation Protection. :

e. Directing 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 :

established operating procedures, emergency :

operating procedures, normal equipment operating

limits or technical specifications during :

attempts to control the emergency. (Note: It is :

imperative that the Emergency Director consult :

i : to the fullest extent practicable with the :

! : Parsippany Technical Functions Center in arriv. :

l

ing at a decision to deviate from prescribed :

t,

- : procedures.) :

( ....____.._________...._____..______..___________.......__..__________

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1004.3, ,

Revision 9

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When the designated Emergency Support Director (ESD) arrives at the site and declares himself to be ready to assume that role, he will assume overall responsibility.._for management of the response to the accident and recovery operations. With activation of the ESD function, the ESD specifically will assume decision authority for Items C an owever, decision authority for Items A, B, E, F, and G will be TEtaa e_ by the Emergency Director (ED). Decisions on all of the lis a t ons nomally will result from close and continuous consultati betwy n the ESD and the ED and it is the r ility of the ED to e re the ESD is provided with the a information to a at timely and appro-priate decisi .

e special case b e classification, the ESD shall retain pr gative to over ED if, in the judgment of the ESD, uncert ty or other ons exist to th extent warrant-ing classification of a highsfi of emergency tha classified by the ED.

2.0 ATTACHMENTS 2.1 Attachment , i ergency Noti a s.

2.2 Attachme I, ergency Status Rep 2.3 Attachment I , Checklist for Notification of Significant Events Made in Accordance with 10 CFR 50.72.

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1004.3. . .

Revision 9 1 3.0 EMERGENCY ACTION LEVELS 3.1 Radiological Control and Containment Integrity Initiating Condition pdication -

3.1.1 Actual or projected dose rates at As indicated by:

the Exclusion Area boundary that if a. Valid coun te of > 1.0 released for one hour would result x 105 cpm gas channel in doses greater than 1/20 of the of RM-A8.

lower limit EPA Protective Action b. Vali e of > 3.0 Guidelines but less than the lower x 10 the gas channel limit EPA Protective Action Guide- of !

lines using actual containment c. unt rate increase of pressure. .0 104 cpm / min on the ine channel of RM-A8.*

d. A lid count rate increase f >3.0 x 104 cpm / min. on D -

he iodine channel of RM-A9.*

@ e A valid dose rate of >2.8 x 104 mR/hr on RM-G8. ~

Offsite radiological monitor-ing reports or dose projec-tions >50 mR/hr (gamma) but <1 eiii/hr (gamma) or air e ose equivalent t- I11o 50 mR/hr (> 1.6 x l

< /cc{to<5R7hr 10- uCi/cc).

i 3.1.2 Major damage fuel in C y either:

containment o e andling object, weighing more than building. the Technical Specification l

Limiting Conditions for

Operation 3.11.6 limits, .

impacting on spent fuel.

b. The water level in the reactor vessel or spent fuel pool drops below the top of the spent fuel.

3.1.3 Reactor Building pressure >30 psig. As indicated by Reactor Building Spray initiation and on Reactor l Building Pressure Indicator.

3.1.4 Reactor coolant total activity As indicated by either:

> 18,300 uCf /mi and/or Dose a. Reactor coolant activity as Equivalent Iodine-131 >1430 determined by sample and uCi/ml indicating possTble loss analysis.

l of coolable geometry. b. RM-L1 Low (Off Scale High)

c. RM-L1 High (Off Scale High)

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- 1004.3~ !

' Revision 9 3.2 Security t

3.2.1 Security _ of- the plant (Vital Area) Shift Supervisor's judgement based is threatened by unauthorized on the infonnation from the Duty (forcible) entry of the facility Security Sergeant. -

(Protected Area).

3.3 General Plant Status 3.3.1 Other plant conditions are in Whenever plan co di ons warrant progress or have occurred which it, as judg e Shift Super- .

may involve actual or likely major visor /Eme i ector, failures of plant functions needed NOTE: In ing the judgement for protection of the public. as to t for declaring a Site .e '

y, any uncertainty

, co n e status of plant fu t needed for protection of ub c, the length of time the inty exists, the prospects early resolution of ambigui-

@ t s, and the potential degrada-ion of the plant functions needed for protection of the public should be considered; i.e., sig-nificant u rtainty as to the reliabil plant functions for protecti public extending beyon re.sonable time period is as f 1 basis for declaring a S r ncy.

3.4 Pressure, Te a and Inventory t 3.4.1 Known loss nt accident A indicated by automatic ECCS greater up capacity itiation due to both high leading to sible RCS saturation. containment pressure (4.0 psig) and low reactor coolant pressure (1600 psig) or reactor coolant system pressure / temperature curves or subcooling monitor

indicate saturation conditions.

3.4.2 Primary to Secondary leak As indicated by:

a. Known primary to secondary a. Automatic ECCS initiation due leak rate and the Reactor to low Reactor Coolant System Coolant System approaching Pressure (1600 PSIG) or saturation. saturated conditions being approached as indicated on the Reactor Coolant System pressure / temperature curves or the subcooling monitoring indicating <25 .

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1004.3. .

Revision 9

b. Total primary to secondary leak b. Valid high alarm on the steam rate >50 GM AND loss of offsite line monitor (RMG26 or RMG27) power! and makeup tank level de-creasing at >2 inches / minute in conjuncti3'n with an indicated failure of offsite

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power (zero volts on SS-1 for the 4 bus A 8 bus).

c. Total primary to secondary leak c. Makeup ta 1 decreasing rate >50 GPM AND a steam line at >2 in e te in breakT conTu *th a rapid unan decrease in stqa re or actuation oQ am Line Rupture Pet on System (SLRDS) or sua indication.

d. Total prim o condary d. =

up tank level decreasing leak rate > ~~

AND a loss at >2 inches / minute with a of cond t? alid high alarm on the steam line monitor (RMG26 or RMG27) in conjunction with condensor vacuum <23 inches or <2 circulating water pumps operat ng.

e. Total primary to se dr ak e. Makeu nk level decreasing rate >50 GPM WITH in te at es/ minute with fuel 3'amage e val alarms on RML1 Low following: or ML1 High (Reactor

1. Loss of wer Co Letdown Monitors)

2. Steam 1

3. Loss o ensor Vacuum Indicated failure of offsite power (zero volts on SS-1 for the 4 bus and C2. 8 bus) OR Rapid unanticipated decrease in steam pres-sure or actuation of the Steam Line Rupture Detection System (SLRDS) or visual indication of a steam line break OR

3. Condensor vacuum 773 inchas or <2 circulating water pumps operating.

3.4.3 High incore thermocouple readings Any two incore thermocouple following a. reactor trip. readings > 700*F following a reactor trip.*

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1004.3_

Revision 9 3.4.4 Complete loss of any function As indicated by a complete loss of 'i g ..

needed for plant hot shutdown. any of the following

a. All means to feed and remove heat from OTSGs.

b. All means to control R.eactor Coolant Pressure

c. Makeup pumps or makeup flow control.

3.5 Electrical Power ;

3.5.1 Loss of all offsite power coin- Continuat o ondition in Alert +

cident with a loss of both Diesel EAL 3.5. e than 15 minutes Generators for more than 15 minutes. ;

3.5.2 Loss of all vital te'DC Co tion of condition in Alert power for more nutes. EAL 3. for more than 15 minutes.

3.6 Instrumenta tuation Systems 9 3.6.1 Most or 1 ators lost and s judged by the Shift Supervisor.

plant nitiated or i progre ch may involve actu or likel for failures o nt functions needed for pro of the public.

i 3.6.2 Failure of any actua rgency Shift er sor judges that ECCS Core Cooling Syst es HPI, set n exceeded but ECCS has LPI and Core F1 rt and ia ed.

run following ic system initiation su the number of compone le is below the minim m for accident ,

analysi s.

3.7 Natural and an-made Phenomena i l 3.7.1 Severe natural phenomena being Plant is not in cold shutdown and experienced or projected with any of the following phenomena

! plant not in cold shutdown. are experienced or projected:

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a. An earthquake of magnitude

> 0.12g horizontal and/or

' > 0.08g vertical acceleration TSafe Shutdown Earthquake).

b. River Stage >307 feet at the River Water Tntake Structure.

c. Actual river state <271 feet at the River Water Tntake Structure.

d. Sustained Hurricane winds or

. tornados >75 mph as indicated I

l on the Wiiid Speed Recorder.

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,mm e9 --g-4-r---w+ - - + --m- - - w--w*, - '-v----w--- -- _

1004.3 ;

Revision 9 3.7.2 Other hazards being experienced Plant is not in cold shutdown and or projected with the plant not any of the following phenomenon are in cold shutdown. experienced or projected:

a. Aircraft crash which, in the Judgment of the_ Shift. Super-visor affects vital struc-tures by impact or fire.

b. Explosion issile damage i which, i dgment of the i Shift Su , causes sever to safe shut-down ment.

c. E %qu xic or flammable vital areas which n judgment of the Shift

. ervisor, affects operation afe shutdown equipment.

3.7.3 Fire compro ' functions 9 ged by the Shift Supervisor.

of any saf s em.

3.7.4 Evacu o e Control Roo ontrol Room is evacuated and where 01 of the shutdown control of all of the following systems ot establishe systems or within 15 inutes. establishe( quipment ithin 15 minutes:is not

a. Em Feedwater System I b. Turbine pass Valves or ti. spheric Steam Dump Valves.

c. a Pumps.

I e p Flow Control Valve.

p down Flow Control.

Refer to Alert EAL 3.7.4) 3.8 3.8.1 Complete 1 Reactivi of a function needed for p ant hot shutdown.

O As indicated by a complete loss of Control Rods.

These indications may be detemined via instrumentation that will be in-stalled or expanded as required by NUREG 0578 prior to restart.

4.0 EMERGENCY ACTIONS 4.1 Upon recognition that any of the above action levels have been reached or exceeded, the Shift Supervisor / Duty Section Super-intendent shall assume the duties of the Emergency Director.

(The event should be assessed and declared within 10 minutes g of the occurrence).

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- Revision 9 4.2 Announce to Control Room personnel that has

' (name) assumed the duties of Emergency Director. The Emergency Director s, hall periodically (approximately every hour) consult ,

with the lead personnel of each area involved in the emer-gency, and discuss:

a. . Status of each area

b. Immediate actions to be taken by each 1 d rson

c. Problem areas

, d. Recomm on course of ac io 4.3 Announc announced, the 6? ng message over the publ c system (merge :

NOTE: Turn on Whelen n tch. :

ATTENTION ALL PE L, TTENTION ALL PER : A SITE EMERGENCY HAS B LARED IN UNIT I N-ESSENTIAL PERSONNEL IN PORT TO UNIT I . ALL NON-l ESSENTIAL P N THE UNIT II RT TO THE UNIT II WAREHOUSE. PERSONNEL IN H.P. ED AREAS PROCEED TO l

THE H.P. CONTROL POINTS BERS OF THE EMERGENCY ORGAN ORT TO YOUR S . THERE WILL BE NO SMOK N ING OR EATING L L THER NOTICE. (Repeat mes ly).

4.4 If emergency is radiation-oriented, direct that the Radiation Emergency Alarm be sounded.

l I : NOTE: Turn off Whelen siren after alarm has been sounded. :

4.5 Assign a Communicator to make notifications to persons and/or agencies per Attachment.I,Section I.

l 4.6 Assign a Communications Assistant and direct him to perform all applicable steps of 1004.8.

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1004.3. . ,

Revision 9 3- 4.7 Direct the Emergency Assembly Area Coordinator to implement the Warehouse Muster Procedure EPIP 1004.36.

4.8 Contact the. Duty Section' Superintendent and discuss Plant Status and inform him that the onsite and offsite Duty Section personnel are being calle'd.

4.9 Depending on the emergency action level whi ched or exceeded, ensure that the appropriate Em '

perating Procedures have been implemented.

4.10 If local s fre, ambulan pol ) are required, direct icator to notif in County Emergency Op t nter and reques t a propriate assistance.

N security (N/S Ga e gin preparations to expedite

, i of responding personnel (Poli e/ Fire /

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( Ambulance) . Se s uld be advised to im . nt EPIP

) 1004.19, Eme e urity/Dosimet a ssuance.

NOTE: I rgency Respon r el are required to :

outside the P Area affected by a :

tive plume, th ncy Director or his :

i : nee will direct t uance of TLD's from the :

rth or South Gate. :

4.11 If the emergency involves radiological problems, direct the Radiological Assessment Coordinator to implement Radiological Controls During Emergencies procedure (1004.9).

4.12 If changes in onsite or offsite radiation levels are expected, direct. the Radiological. Assessment Coordinator to:

a. Dispatch offsite and/or onsite radiation monitoring teams in accordance with EPIP 1004.10 and send a monitor to the Emergency Assembly Areas.

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1004.S- :

Revision 9-

. b. Implement Onsite/0ffsite Dose Projection procedure (1004.7).

4.13 If personnel / vehicles are, or are suspected to be contamin -

ated, have the RAC initiate the Personnel / Vehicle Monitoring and Decontamination procedure (1004.20).

4.14 Activate the Technical Support Center (1004 !. the Operations Support Center (1004.29).

4.15 If additional sources or notificat s arVrequired, refer to Additio tance and Not catio procedure (1004.6).

4.16 Assign i dual to complete hcmentII,SectionIand giv i e Radiological A ment Coordinator to transmit to Bureau of Radia ection.

4.17 Direct the Radiolog a ssment Coordin to complete L

Attachment II, to transmit he B eau of Radia-tion Protec n adioactive rel occurred or is occurrin 4.18 Stop 1 d and gaseous is es that are in progress unti assessment of their im ct is performed and specific approval is given to continue the release by the Emergency 1- Director.

4.19 Verify that communications and documentation are maintained per procedure Communications and Recordkeeping (1004.5).

4.20 If applicable, direct the Operations Coordinator to dispatch Emergency Repair / Operations personnel to investigate the identified problem area (s) in accordance with Emergency Repair / Operations procedure 1004.21.

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1004.3

. Revision 12 4.21 Af ter 30 minutes from initial contact with PEMA, confirm that BRP verification has been made. If no verification, instruct the^communica. tor to proceed to Attachment I, Section 1 t 2.e.

4.22 Instruct the Radiological Assessment Coordinator to provide ongoing dose estimates for actual releases to th au of Radiation Protection.

4.23 If a report of initial accountability iden . i names of missing individuals has not been rece d in 30 minutes from the ti ordered, contac t ecurity Coordinator at 8038 40 for a status .

4.24 If p r e re still unacco n d or 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from the onset o untability, direct rations Support Center Coord ator to initi , ency Plan Imp'e nting Procedure (EPIP) 1004.18, Se7N1 Rescue.

4.25 If person (s) r d or ill and adiologically controlled or are potentiall o nated, or if per-son (s) ceived radiatto t on exposure greater tha r , direct the RAC t ement EPIP 1004.16, Contam-inated I juries / Radiation Overexposure.

131 4.26 If person (s) have been exposed to I sufficient to cause a thyroid dose of greater than or equal to 25 RAD direct the RAC to implement the Thyroid Blocking Procedure, Emergency Plan Implementing Procedure 1004.35.

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1004.3 Revision 12 .

4.27 Upon completion of a muster at the warehouse, an orderly evacuation by private vehicle shall be ordered by the follow-ing~ message over the public address system (merged): ,

___ _________- - - - _ - ===- =-

NOTE: Turn on Whelen siren switch. .

- . -- --- ==-- _________ _ - --- =-

ATTENTION ALL PERSONNEL; ATTENTION ALL PERS . L NON-ESSENTIAL PERSONNEL IN UNITS I AND II THE (MIDDLETOWN SUBSTATION /500 KV SUBSTATION) E NORTH / SOUTH GATE. (DEPENDING ON PLUME UPON ARRIVAL, ALL SUPERVISORS WILL ASSEMBLC N IN THEIR PERSONNEL AN VIDE FURTHER INSTR ' i NS. (Repeat message slowly).

_-n _ _ _ _ _ _ - - = _ _ -____-__.

____I 2I__ b _[-- *" Y_*" N' = =

_ - = = _ _ _ _ _ _ _ _ = - - -

4.28 E e dose projections timates and, if necessary, reco end protective to the BRP con tent with the guidelines in At en ,Section IV.

4.29 Based upon as e of plant condi e Emergency Director s ither close out t mergency, escalate to a mergency or do to a lower class as foi

a. If Recovery Phase criteria have been met (see Recovery Procedure 1004.24), but long term recovery operations are not necessary, close out the Site Emergency by performing the notifications in Attach _

ment I,Section III.

b_ . If Recovery P.hase. criteria have not been met, but Site Emergency action levels are no longer exceeded, de-escalate to a lower emergency class by notifying 12.0 _

1004.3

, . Revision 12 :

BRP on the Radiological Line and performing the remaining notifications in accordance with the

. applicable emergency procedure as specified in Step 5.2.

c. If emergency action levels exceed tho a Site Emergency, escalate to a Generai , notify BRP on the Radiological Line a he remaining notifications in accordanc th General Emer-edure (1004.4).

4.30 If nece to potential co atton of normally non n ed sumps and/or a s, or the need to closely r liquid releases i e procedure 1004.14, Monitor-ing/ Controlling Liq rges.

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5.0 FINAL CONDITIONS 5.1 A higher cla gency has bee by the Emergency Director n e General Emergency .ure (1004.4) is being Imple , r 5.2 A lo ss of emergency has n declared by the Emergency l

Director and one of the following procedures is being l

l implemented:

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a. Unusual Event (1004.1) l b. Alert (1004.2) l f 5.3 The Site Emergency has been closed out with the concurrence of l the Emergency Support Director, since no recovery operations are required, or 5.4 The Site Emergency can be shifted to a recovery mode by j implementing procedure 1004.24.

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1004 4- ;

. Revision 9

, a . 5.5 At the close out of the Emergency, ensure that all logs, checklists, procedures and other documentation generated in

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j the Control Room, asociated with the event, are gathered and .

sent to the Emergency Preparedness Department for review and filing.

A '

Date Signature f X As'UM Responsible for Impi ntiit9/ Procedure-1 0

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1004.3 Revisidn 9 ' !

ATTACHMENT I SECTION I INITIAL CONTACT

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INITIALS _ _ ,

The Conmunicator shall notify the following agencies and personnel and update the Attachment I,Section II checklist after each notification.

1. Dauphin County Emergency Operation Center (If this is a reclassification notification, fids n fy BRP on the radiological line or 9-787-3720 then g 3, unaffected Control Room).

a. Telepho . 9 1 or 9-236-7976 Q

1. I ntact, activate a hi County radio system.

b. T at the Three Mile (name/ )M Island Nuclear Stati I calling. W declared a Site Emergency at h pon Emergency Director j W t, deliver one of h hours. Yed owing statements):

1. W v had a radioa elease OR

2. had a radioactiv aso, but do not expect this l

si ation to result in in detectable changes in offsite radiation levels, OR

3. We have had a radioactive release, but do not know if there will be a detectable change in offsite radiation l

l levels. We will be keeping the Bureau of Radiation Protection infonned of the results of our investigation, OR i

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,__,.v., .-_.,,___r ,____,x . , _ , , - . _ . , _ . , - - - _ - . . _ . , _ _ . _ _ , . . , , , _ _ - - _ . . - . - _ _ . , . _ _ , _ , - , _ ,

1004.3 Revisidn 9 ?

ATTACHMENT I SECTION I INITIAL CONTACT INITIAL -

4. We have had a radioactive release and expect to be able to detect changes in offsite radiation level it they will be less than the levels calling *fo al Emergency.

We will be keeping the Bureau o itadi n Protection info 1

(Gi t non-technical tion of the emergency a xtent of radio t e elease including poten-ally affected popu t and areas.

A A M %

2. Pennsylvania Emergen gement Agency @E!K) v A (If this is a r ification notific i to Item 3, unaf.

fected Cont .

NOTE: n protective actions are to be recomended, the :

rgency Director should refer to the contents of :

Attachment I,Section IV. :

a. Telephone: PEMA dedicated line (Use only during NORMAL work hours 0800 1600 Hrs. Monday - Friday) or 9 783 8150 (Use when the dedicated line is out of service or after nomal work hours.. A diverter forwards this after nomal work hours call to the PEMA Duty Officer).

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I..... ..... .. ... . $.$ .$ '.. $$$$ . . $ *. *.............

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1004.3' Revisio'n 9 g

ATTACHMENT I SECTION I INITIAL CONTACT

^

INITIAL _.

b. MESSAGE:

This is at the Three sland (name/ title) .

Nuclear Station linit I calling. We have a me ncy. Give me the Operations Duty Officer. (When D 'cer answers):

This is C Three Mile Island

' $ytitle)

Nuclear oAAJnit I calling. e declarad a Site Eme e h s. We request that you contact (time) the au of Radiati t ion. Bureau Radiation Protection call back Id be made on th d logical Line or 948-8069, 94 r 944-0839. (8 o Emergency Director's , deliver one fo lowing statements).

1. We had a radioac r se, OR

2. e .iad a radioacti e se, but do not expect this s tion to result in detectable changes in offsite radiation levels, OR

3. We have had a radioactive release, but do not know if there will be detectable changes in offsite radiation levels. We will be keeping the Bureau of Radiation Protection infonned of the results of our investigation, OR t

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1004.3. ,

Revision 9 ATTACHMENT I SECTION I

], g INITIAL CONTACT INITIAL. . .

4. We have had a radioactive release and expect to be able to detect changes f ri offsite radiation lev t they

.will be less than the levels calling'f al Emergency. We will be f;eeping the Radiation Protectior, infor1ned.

c. Give a sho -

hnical descri tion the emergency and, if appl , fter release, sta E direction of the pro c pathway and t tially affected populations. ,

b

, i d. If PEMA wa o be contacte Dauphin County; c em that PEMA contacted and di to not'fy PEMA, , Lancaster, York, on nd Cumberland .

e. e verification:

i Expect Bureau of Radiation Protection (BRP) contact after PEMA notification. If no BRP confir1 nation is received within 30 minutes, notify PEMA of the situation. If i

unable to contact PEMA (line busy), call Dauphin County I

and notify them that BRP has not verified initial contact. Request Dauphin County to contact PEMA and BRP.

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l 1 004.3 ^

i Revision 11 ATTACHMENT I SECTION I I

INITIAL CONTACT

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INITIAL __.

3. Unaffected Control Room

a. Telephone: 8066, 8067, 8068 or inter Control Ro ine.

b. MESSAGE: Emergency organization staffing is but implementation of the Unit 2 Emergency Pla n required.

(Give a brief description of plant sta t e Shift Supervisor /F .

4. Institute of NgfC a4 wer Operations D (Do not no i is is a reclass f at on notification),

a. Te e: 1-404-953-0904 tact the TMI Site operator for assistance by dia

b. MESSAGE:

This is m v at Island Nuclear ametti t1e }

Station U ling. We hav a Site Emergency at ,

hou e a brief description of t%6 )

the emergTncy).

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1004.3 '

Revisf o'n 9 ATTACHMENT I SECTION I

(

INITIAL CONTACT INITIAL

5. American NuclearInsurers 1-203-677-7305 or 9-1-800-243-3172/3173 (after normal working hours)

MESSAGE:

This is at Three ! e and Nuclear (name/ title Station Unit I calling. We have declared a gency at n hours. (Give a f ription of the (time) emergency) . Q b

0" &

m A mT N We (have/ha k

noC had a radio t v

ease.

6. If the Site involves radia n eases, notify the follow-ing agenci -

a. Radi ianagement Corporation Emergencies (0800-1700) 73-1-215-243-2990 (1700-0800) 73-1-215-841-5141 l

Office (0800-1700) 73-1-215-243-2950 l

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- 1004.3.. .

- Revisfor. 9 r

i ATTACiffENT I SECTION I INITIAL CONTACT'

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INITIAL ...

MESSAGE:

This is at the Three Mil Nuclear (name/ title) .

Station Unit I calling. We have declared a Sit ncy at hours. (Give a b i iption of the (time) emergency) .

m NU hv M

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cW 6

(

We have had r ive release.

We m r sistance at this time.

7e not)

(De i e assistance req f any).

7. If police ohdedical assistance is required, notify the following l agencies:

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

Notification to be perfomed per procedure 1004.16

b. Pennsylvania State Police 234-4051 f

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1004.3 Revision 12 .

ATTACHMENT I SECTION I INITIAL CONTACT INITIAL - -

MESSAGE:

This is at the Three Island (name/ title) '

Nuclear Station Unit I calling. He have de a Site Emergency at hours. W (time) (have/have not) had a radioa please. He requ e istance as follows:

, (State a s ante required). ty

8. NuclearRegdklor Commission (NR Be esda, MD v continuously maintained (Commi ons with the NRC w I following ntact).

a. Telephone: NRC E e Notification Sys S) (RED PHONE) (If ENS e inoperative, e ktf>EPIP1004.6,

" Additional stance and Notifi ti r alternate methods.)

. b. MESSAG -

NOTE: plete this form (adapted from NUREG-0845) before :

c ntacting the NRC (if this can be done without ex_ :

ceeding the one (1) hour notification time require- :

ment) obtain the information from the Shift Super- :

: visor / Emergency Director. :

j Request to speak to the Outy Officer Duty Officer's Name Time of Contact This is / at Three Mlle Name Title 22.0 .,

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1004.3 Revision 12 ATTACHMENT I SECTION I INITIAL CONTACT Island Nuclear Station. Unit 1. He have declared a(n) (select as appropriate).

50.72 (NON EMERGENCY)

GENERAL EM NCY (1004.4)

UNUSUAL EVENT (l004.1) TRANSP ALERT (1004.2) PHY I L CURITY; SAFEGAURDS X SITE AREA EMERGENCY (1004.3) A TEGORY at . ours on .

te v Tim Piovid ment selecte by hlft Supervisor /Emer-

[

gen D r to the NRC t' icer.

He have not a loactive release, OR

2. We have ha active releas t do not expect this to result in ect bl changes in o atton levels v

3. e had a radioac 'e e ase, but do not know here will be a tec able change in offsite radiation levels. He w 11 be keeping the Bureau of Radiation Protection informed of the results of our investigation.

4 He have had a radioactive release and expect to be able to detect changes in offsite radiation levels, but they wl!1 be less than the levels calling for a General Emergency. We expect the levels to be < 1 Rem per hour (gamma) and < 5 Rem per hour child 23.0 ,

1004.3 Revisjon 12 ;

ATTACHMENT I SECTION I INITIAL CONTACT thyroid dose commitment. He will be keeping the Bureau of Radiation Protection informed.

c. Give a short non-technical description of the eme cy and the extent of the radioactive release, inclu ected populations and areas. .

/>

AL 6% ~

EVENT TIME: Q CAUSE: _ b a> v cap 4 S t ". n POWER PRIOR TO EVENT: A POWER NON: A

_ V ANv ANY SAFETY INJECTION OF EC \c2 COOLING MODE: Ab ANY CONTAMINATION? ): _

ANY RELEASES: (QUANTIFY):

24.0 ,

1004.3 Revisi.o.n 12 ATTACHMENT I SECTION I INITIAL CONTACT CONTAINMENT STATUS (IF APPLICABLE): .

ANY OTHER PROBLEMS: b 1@

(tT PLANS: A Et A

D DATE TIME O MP TION - PL ED BY

NOTE: If the NRC Du er directs you uspend con- :

tinuous c 1 t ons inform the a call :

back wil' ttated if any si ifican changes :

occur. with Duty Off e , time and :

date t ergency Direct 's o :

NOTE: f nitial NRC noti cat is complete per :

A hment I, Section a e; Refer to the NRC :

t'.fication Checklist, A tachment III. This :

ecklist contains information desired by the NRC :

and may be helpful in providing follow-up :

Information. :

25.0 -

1004.3 Revisidn 9 i ATTACHMENT I SECTION III g

SECONDARY CONTACT INITIAL , , , , ,

The Communicator shall notify the following agencies and personnel and update the Attachment I,Section II checklist after each notification.

1. Announce or have announced the following message plant page after turning on whelen sirens " ATTENTION L P ONNEL, ATTENTION ALL PERSONNEL. The Site Emergen een terminated.

(Give a brief d of the work re r ons, if any)".

Repeat messa n off whelen si ID

2. Bureau of. n Protection v

a. T one: Radiological n 9-787-3720

b. MES :

. This is A at the ifle Island

'a itle Nuclear Sta I calling. W c% sed out the Site Emergen t hours i ted recovery operations.

[ time)

Ple n y PEMA, Dauphin, ter, York, Lebanon and Cumberl nd counties.

3. Unaffected Control Room

a. Telephone: 8066, 8067 8068

b. MESSAGE:

Notify Shift Supervisor / Foreman of close-out of the Site Emergency. ,

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1004.3. .

Revision 9

, ATTACHMENT I SECTION III SECONDARY CONTACT INITIAL _,.

4. If applicable, notify the following persons and/or agencies of close out of the Site Emergency:

a. Hershey Medical Center:

9-534-8333 (Ask for Duty Nurse)

b. Pennsylvania State Police: 9-234-4051

c. Radia ement Corp.:

ergencies (0800- 73-1-215-243-2990 O Office

( 0 0 0)

-1700) 73-1-215-841-5141 73-1-215-243-2950

d. rican Nucle s: 74 203-677-7305

e. Others - a or.

by the Emergky D eate A A y C. ,ieted e, 9.C.,,etee r

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1004.3. .

Revision 9

, ATTACHMENT I SECTION IV PROTECTIVE ACTION RECOMENDATION GUIDELINES

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THESE RECOMMENDATIONS MAY BE DELIVERED ONLY BY THE EMERGENCY DIRECTOR

1. Consideration shall be given to sheltering if:

a. Release time is expected to be short (Puff relea urs).

(AND)

b. Evacuation could n be well underway pri -

cted plume arrival due to ing time, high wind eeds, and/or foul weather. D

2. Consideration a iven to evacuat :

a. A rele s expected to occ rojected doses approaching or exceeding:

' 1 Rem Whole Body 5 Rem Child v (AND)

b. Release ti e ected to be lo hours)

(AND)

c. Evacuation can be well underway prior to plume arrival for above i

release, based uoon wind speed and travel conditions.

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28.0

1004.3 Revisio'n 9 ATTACHMENT II SECTION I EMERGENCY STATUS REPORT

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1. Description of Emergency:

M

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oW

2. Has the Reactor tripp Yes / No

3. Did the Emergency s Systems actuat O Yes / No If so, which o

a. High re Injection Yes / No

b. Low Pressure Injection es / No i c. Core Flood v / No

d. 4 psig Reactor Bu %61ation es / No

e. Reactor Buildin ay Actuated Yes / No

4. What is the stat plant

a. At power

b. Hot Standby

c. Hot Shutdown

d. Cooling down

e. Reactor Pressure psig

f. Reactor Temperature *F

5. Is offsite pow'er .available Yes / No

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29.0

1004.3 ,

Revision 9 ATTACHMENT II SECTION I EMERGENCY STATUS REPORT

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 Ye o

1. What are the approximate radiation and and/o contamination levels mR/hr 2

A 00 cm

8. Are there excessiv n levels and/or nation level s. Yes / No

a. If so, below:

1. Radiation levels (Wh b

2. Contamination le DPM/10 m Location:

W f,

Y Date mM Time O Completed By i

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30.0

. 1004.3. .

~

Revision 9 ATTACHMENT II SECTION II EMERGENCY STATUS REPOP.T Fill out if a release has (is) occurring. Provide BRP all available infoma-tion for verification call.

1.- What is the approximate radio:ctive source tem disc ate from the plant (As determined by the Projected Dos'e on Procedure (1004.7).

a. Noble gases Ci/sec

b. Iodine A Ci/sec

2. What is the e meteorology D

a. Win s m

b. W irection _

v

c. Stability Class-Stab 1/ Unstable 8

3. What is the projected y dose rate a d iodi concentration at the nearest off i wind point

a. . R/hr

b. Ci/cc Iodine

c. b (Location) l M

4. Estimated duration of the release l

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a. If the release is teminated:

Start Time Stop Time l Duration

b. If the release is still in progress:

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

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1004<3- :

Revision 9

. ATTACHMENT II SECTION II EMERGENCY STATUS REPORT

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5. a. Based on projected dose rates, iodine concentration and duration or estimated duration (if still in progress) of the release,'will the lower limits of the EPA Prot 'e tion Guides be exceeded (i.e.,1 Rem Whole Body -

ild Thyroid)/

Yes/No V

b. If yes, es i me to exceedi PAG:

hours ted whole body do 2 Rem and ch' d dose W

Rem.

Date Time Comp teg Aih Co s By l % 0 i

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32.0 i

1004.3_ . .

Revision 9

(

ATTACHMENT III CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS

, ~'MADE..IN.ACCORDANCE WITH 10 CFR 50.72 .

A. Identification:

Date Time Name'of Person Making Report Licensee Facility Affected G Applicable Part of 10 CFR 50.72 x B.

Description:

Date of Event A me _

Description of Wh N C. Consequences o E (Complete depen n v

n type of event) 4 Injuries Fatal i M V A Contamination (personnel) A (propertyi \

t. Overexposures (known/possi m

Safety Hazard (describe potential) A\

n Offsite Radiatio __

h IntegratedDosek Loca v

Meterology (wind speed) From (direction)

Weather Conditions (rain, clear, overcast, temperature)

Equipment / Property Damage D. Cause of Event:

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1004.3. .

Revision 9 ATTACHMENT III CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS

' MADE.IN ACCORDANCE WITH 10 CFR 50.72 -

E. Licensee Actions:

Taken Planned &

Emergency Plan Activitated (Yes/No) Classifica ergencyl-o Resident Inspector No s/No) Stat fied (Yes/No)

Press Release Plan e o) News N nterest (Yes/No)

L 1 National F. Current Stat . (Complete dependin e of event)

1. Reactor Systems Status A b

! Power Level Before Ev6 Af er Pressure n emp. (thot) b - tcold)

RCS Flow (Yes/ Pumps On M

Heat Sink: e er S m . Dump Other b Sample Taken (Yes/ Activity Level M

ECCS Operating (Yes/No) ECCS Operable (Yes/No)

ESF Actuation (Yes/No)

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

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S/G Levels Feedwater Source / Flow I'

Containment Pressure Safety Relief Valve Actuation (Yes/No)

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

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1004.3 - .

. Revision 9

, ATTACHMENT III

-CHECKLIST FOR NOTIFICATION OF SIGNIFTCANT EVENTS

~ MADE IN.ACCORDANCE WITH 10 CFR 50.72 -

Containment Water Level Indication Equipment Failures O Nomal Offsite Power Availabe (Yes/No) m Major Busses / Loads lost A

+

Safeguards Buss ource .

D/G Running o to Yes/No)

2. Radioactfyi ase

. Liquid _ ocation/ Source

Release Rate A Duration b l I Stopped (Yes/No) .O Release o (Yes/No)

Amount of Releasen ( Tech c. its Radiation Lev 1 Plant Are uated

3. Security /S ar 2 Bomb Th earch Conducted (Ye Search Results Site Evacuated (Yes/No)

Intrusion: Insider Outsider Point of Intrusion Extend of Intrusion Apparent Purpose Strike / Demonstrations: Size of Group Purpose 2 See 10 CFR 73.71(c), effective April 6,1981.

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35.0

[ 1004.3. ,

Revision 9 ATTACHMENT III CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS

~ MADE IN ACCORDANCE WITH 10 CFR 50.72 .

-Sabatoge: Radiological (Yes/No) Arson (Yes/No)

Equipment / Property

~ '

, Extortion: Source (phone, letter, etc.) &

Location of Letter .

Demands //

General: Firea ed (Yes/No) lence (Yes/No)

Control of mpromised or Thr N d (Yes/No)

Stolen /M s rial

'Agenci tified (FBI, S ocal Police, etc.)

Media Interest (pres pated)

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1004.4- ;

- Revision 9-

09/26/83

-IW ORTANT TO SAFETY NON-ENVIRONMENTAL IWACT RELATED THREE MILE ISLAND NUCLEAR STATION UNIT NO. l'EERGENCY PLANNING IWLEMENTING PROCEDURE 1004.4 _

GENERAL EMERGENCY Table of Effective Pages Page Revision Page Revision Page Revision , e sion 1.0 8 2.0 8 3.0 8 4.0 8 5.0 8 6.0 8 7.0 8 8.0 8 9 9.0 8 10.0 8 11.0 9 12.0 8 13.0. 9 14.0- 9 15.0 9 16.0 9 1.

19.0 9 20.0 9 21.0 9 22.0 9 23.0 9 l 24.0 9 i

25.0 9 26.0 9 27.0 9 i

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$ c c~n 9/MNK3 Date

/ / (/Si~gnature O

/ s Signature ' Date Document ID: 0029W r

1004._4 .

Revision 8

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-s THREE MILE ISLAND NUCLEAR STATION UNIT.NO.1 EMERGENCY PLANNING IMPLEMENTING PROCEDURE 1004.4 GENERAL EMERGENCY-1.0 PURPOSE The purpose of this procedure is to define the conditions that shall be regarded as a General Emergency for Three Mile Island Nuc1 a ation (Unit 1) and to:

a. Ensure necessary actions are taken to protect th th and safety of the public.

b.- Ensure necessa are taken to notk U. Nuclear management and offsite e response organi gpi .

c. Mobilize t ency response o iz ions to initiate appro_

priat ency actions.

The Plant Opera ons Group wil e actions neces ry to implement 1 this procedure upon identif to f one or more o ergency Action Levels listed in Sectio , o his procedure rgency Director l- shall then assume re bility for the con n implementation of i

this procedure.

l ': NOTE: e Emergency Director is vested with certain :

uthority and responsibility that may not be :

delegated to a subordinate. Included are: :

a. Classification of an emergency event. :

b. Approving and directing official notifications to :

offsite agencies. .

c. Approving and directing infomation releases to :

the media. :

d. Approving and, if possible, persc;ially conveying :

appropriate Protective Action Recommendations :

to the Bureau of Radiation Protection. :

e. Directing 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. :

1.0 _

I I _ _ - _ . ._ _ - . _ - _ _ _ _ . _ _ . _ . -

1004.4- :

Revision 8 4 : g. Approving and directing deviation from : !

established operating procedures, emergency : ,i

operating procedures, nonnal equipment operating : >

limits or technical ~ specifications during : !,

. attempts to control the emergency. (Note: .It is.:

imperative that the Emergency Director consult :

l

to the fullest extent practicable with the :

'Parsippany Technical Functions Center arriv- :

ing at a decision to deviate from pr d :

procedures.) . :

L ___________________________________________________ __ _ _________

When the designated Emergency Support Director (ESD e at the site and declares himself to be ready to assume that e, will assume -

l overall responsibilit 'gragement of the respo to the accident and recovery operation t activationofthe58 unction, the ESD specifically w 1 decision autho t for Items C and D. However, decision aut y for I'tems A, B,1E, d-G will be retained by the l Emergency Direc r (ED). Deci 1 of the list actions normally

[ t will result. from close and u s consultation betwe he ESD and the ED and it is the re ty of the ED n that ESD is provided with the n information to ar s timely and appro.

priate decisions t special case @ classification, the ESD shall retain the gative to overrule D if, in the judgment of v

the ESD, uncertainty or other considerations exist to the extent warrant.

ing classification of a higher level of emergency than that classified by the ED.

INITIALS 2.0 ATTACHMENTS i

l 2.1 Attachment I, General Emergency Notifications 2.2 Attachment II, Emergency Status Report a

2.0 -

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-,--,-,--r -a . , - - . . . . . , - - - . - . - , , , - ~ ..,,-,-.,--..-,.,,...-.n,- - . - , . _ , - - . _ _ . - - - - . - . . . - - - . . - - - - - - -

1 004.4 Revision 8 - !

2.3 Attachment III, Checklist for Notification of Significant Events i

Made In Accordance with 10 CFR 50.72.

3.0 EMERGENCY ACTION LEVELS ,

3.1 Radiological' Control and Containment Integrity ',

l - Initiating Condition Indicatio. I 3.1.1 Actual or projected dose rates at As determi -

the Exclusion Area boundary that a. A pro; e calculation

if released for one hour would of >1' (gamma) whole

, . result in doses in excess of the bo Exclusion area lower limit EPA Protective Action using actual meteor-Guidelines using 1 containnent o gy Reactor Building

, pressures, ate based on actual con inment pressure (includes ty aste Gas Tank Rupture containing the high limit content of 8800 C1).

A projected child thyroid dose calculation of >5 Rem /hr at the Exclusion area boundary _

using ual meteorology and Reac bilding leakrate base gi, tual containment P r

c. adiological monitor-rts of >l Rem /hr a) or airborne dose u valent r .

3.2x10g131>5 Remat/hr uC17'cc) any

- oTfsite location.

3.1.2 Significa v is of radiation s indicated by either:

in the reactw containment a. DogerateonRM-G8>2.8x building and potential loss of 10 mR/hr and a Reactor containment integrity. Building pressure >30 psig.*

b. DogerateonRM-G8>2.8x 10 mR/hr and a Reactor Building hydrogen concentra-tion >3 percent by volume.

3.2 Security 3.2.1 Loss of physical security control Shift Supervisor's judgment, based of the plant (Vital Area). on advice of the Duty Security Sergeant.

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.. _ - - _ .u. _-. _ .. _ .. a ,. ,.. - ___ _ , _ _ ___._ .. _ _ _ _ _ _ -___ ..___ _ _ _. _ _. _ _ _ ____

i 1004.4_ .

~

Revision 8 3.3 General Plant Status 3.3.1 Other plant conditions are in Whenever plant conditions warrant

. progress or have occurred which it, as judged by the Shift Super _

may involve actual or inaninent visor / Emergency Director.

substantial core degradation or NOTE: In exercising tlle judgement melting, with potential for loss as to the need for declaring a of containment integrity, or may General Emergene any uncertainty make release of ,significant amounts concerning the tial for large of radioactivity in a short time releases of r 10 e material, possible. the length the uncertainty exists, a r spects for the

! early res of ambiguities should dered, i .e. ,

signific uncertainty as to the po al r large releases of ra o 've material extending nd reasonable time period is O cient basis for declaring a G eral Emergency.

These indicat s e determined umentation that will be installed or expanded s uired by NUREG 057 to restart.

4.0 EMERGENCY ACTION INITIALS 4

4.1 Upon recognit o any of the abo g a levels have been reached or ded, the Shift Su r NN / Duty Section Super _

intend 1 assume the du e Emergency Director.

(Th ve hould be assessed eclared within 10 minutes l

l of the currence.)

4.2 Announce, or have announced, the following message over the public address system (merged):

NOTE: Turn on Whelen siren switch. :

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4.0 -

1 1004.4 , ,

Revision 8

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., ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: A GENERAL EERGENCY HAS BEEN DECLARED IN UNIT 1. ALL NON-ESSENTIAL

, PERSONNEL IN. UNITS 1 AND 2 PROCEED T0 (500 XV SUBSTATION /

MIDDLETOWN SUBSTATION) (Depending on plume pathway). UPON ARRIVAL, ALL SUPERVISORS WILL ASSEMBLE and LOG ERSON-NEL. PERSONNEL IN H.P. CONTROLLED AREAS R'EP CESS CONTROL POINTS. ALL MEMBERS OF THE EMER E ANIZFION REPORT TO YOUR STATIONS. THERE WILL H i KING, DRINKING, OR EATING U THER NOTICE.

(Repeat lowly) D 4.3 Anno n ntrol Room Per n 1 hat (name) has umed the dutie Em ency Director The Emergency Direct a periodically ox. every hour) consult with th personnel of eac nvolved in the emergency, d s:

a. Sta ch area.

b. Iu- ".t. action to be each lead person.

c. lem areas.

l d. Recommendations on course of action.

l 4.4 Direct the sounding of the Radiation Emergency Alarm.

l. .......... --.............--.....-- ............... -----..----.......

! : NOTE: Turn off Whelen siren switch after alarm has been :

sounded. :

4.5 Assign a Comunicator to, make notifications to persons and/or agencies per Attachment 1, Section 1.

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1004.4. .

Revision 8 4.6 Assign a Connunications Assistant and direct him to perform i

all applicable steps of Procedure 1004.8.

4.7 Contact the Duty Section Superintendent, and discuss plant status and inform him that the on site and off_ site duty section personnel are being called.

4.8 Depending on the emergency action level wh'i s ched or exceeded, ensure that the appropriate Em r perating Procedures have been implemented.

4.9 If local s fire, ambulance, po ) are required, direct icator to notif in County Emergency Oper t ter and reques a ropriate assistance. Notify s ty (N/S Gate) to beg parations to expedite entry of responding emergency 1 (Police / Fire / bulance).

( Security should i to implemen roce 1004.19 (Emergency S u simetry Badge u .

l

NOTE: I rgency Respo r el are required to :

outside the p area affected by a :

tive plume, th ncy Director or his :

nee will direct t uance of TLD's from the :

rth or South gate. :

i i

4.10 If the emergency involves Radiological problems, direct the Radiological Assessment Coordinator to implement Procedure 1004.9 (Radiological Controls during Emergencies).

l 4.11 Direct the Radiological Assessment Coordinator to:

l

a. Dispatch off_ site and/or on site radiation monitoring teams in accordance with Procedure 1004.10 (Onsite and Offsite Radiation Monitoring).

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6.0 -

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1004.4- .

Revision 8

b. Implement Procedure 1004.7 (Onsite/Offsite Dose Projec-tions).

4.12 If personnelfvehicles are, or are suspected to be, con .

taminated, have the RAC initiate Procedure 1004.20 (Personnel /

Vehicle Monitoring an'd Decontamination).

4.13 Activate the Technical Support Center (Pro'c .28) and the Operations Support Center (Procedure .

4.14 If additional resources or notificati a required, refer to (Additi tance and Notificat ) Procedure 1004.6.

4.15 Assign ual to complete ment II,Section I and giv i Radiological s sment Coordinator to transmit t Bureau of Radiation etion.

. 4.16 Direct the Radiologi sment Coordinat to complete

Attachment II, to transmit t the eau of Radia-tion Protecti 4.17 Stop all 1 and gaseous discha t are in progress until s sment of their a is performed and specific app 1 given to continue elease by the Emergency Director.

4.18 Verify that communications and documentation are maintained in accordance with Procedure 1004.5 (Communications and Record-keeping).

4.19 If applicable, direct the Operations Coordinator to dispatch l Emergency Repair / Operations Personnel to investigate the identified problem areas (s) in an accordance with Procedure l 1004.21 (Emergency Repair / Operation:).

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1004.4_.

Reviston 8 :

4.20 After 30 minutes from initial contact with PEMA, confirm that i

BRP verification has been made. If no verification, instruct the-Communicator to proceed to Attachment I, Section 1-2.e.

4.21 Instruct the Radiological Assessment Coordinator to provide ongoing dose estimates for actual releases to the eau of Radiation Protection.

4.22 If a report of Accountability has not been ed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from the time it was ordered, co e Shift Sergeant /Se ordinator at 80 , 9, 8040 for a status report. Q 4.23 If pe n are injured or 1 an are in a radiologically c lied area or are po n y contaminated, or if per-son (s have receive on exposure gre r than 25 REM; direct the RAC t 1 t Procedure 1 . ontaminated Injuries /Radt rexposure).

j 4.24 If person ( e been exposed to ficient to cause a thyro greater than il o 25 RAD, direct the I

RAC nt Procedure 1 . (Thyroid Blocking).

4.25 If pers nel are unaccounted for, direct the Operations Support Center Coordinator to initiate Procedure 1004.18

, (Search and Rescue).

4.26 Evaluate dose projections and estimates and, if necessary,

, recanunend protective actions to the BRP, consistent with the i

guidelines in Attachment I,Section IV.

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. , . - - - , . - . - . - - - , . , - - . - . ~ . , . ,,,,e... .,,,,,,.m. ________n,,,,,,w._

1 1004.4._ .

Revision 8

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4.27 Based upon assessment of plant conditions, the Emergency

.1 Director shall either close out the General Emergency and

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enter 'the _ Recovery Phase or downgrade to a lower class.as follows:

a. If Recovery Phase criteria have been met ( cedure 1 004.24) and long term recovery opera't not necessary, close out the General E directing the Communicator to perform the i tions in Attach-i ment III.

b. If Phase criteria Q t been met, but General E Action levels r no longer being exceeded, e-escalate to a lowe gency class by notifying BRP on the Radiolo and perform t remaining

( notificatio a rdance with t e app able emergency procedur ified in Step ..

4.27 If necessa , e to potential co "--x on of normally non-c ed sumps and/o or the need to closely mon id releases, init rocedure 1004.14

(

(Monitor ng/ Controlling Liquid Discharges).

5.0 FINAL CONDITIONS

'5.1 A lower class of emergency has been declared by the Emergency Director and one of the following procedures is being implemented:

a. Site Emergency (1004.3)

b. Alert (1004.2)

c. Unusual Event (1004.1)

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1004.4- :

Revision 8 5.2 The General Emergency has been closed out with the concurrence of the Emergency Support Director, since no recovery opera-tions' are required. - .

5.3 The General Emergency has been shifted to a recovery mode by implementing the Procedure 1004.24 (Recovery 0 i s).

5.4 At the close of the Emergency, ensure that check-lists, procedures and other documentati d in the Control Room associated with the eve are hered and sent to the Emer paredness Departmen or review and filing.

Date 4 y fNrture of Person espons1 Die for ementing Proce e

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1004.4 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 after e notification.

INITIALS

1. Dauphin County Emergency Operation Center

^ - - -

NOTE: If s a reclassific i otify BRP on the :

cal line or dial -3720 and proceed to :

, Unaffected Cc ol om. :

a. one: 9-911 or 9-23 V

(1) If no contact, the Dauphin Co ty Radio System.

b. MESSAGE:

This is n V at the Island Nuclear eftttle)

Station t alling. He hav d a General Emergency at ours. (Based up gency Director judgement, l

use one of the following statements):

1. We have not had a radioactive release, however we have the potential for a significant radioactive release OR 11.0 _

1004.4 Revis36n 8 :

INITIALS t

2. We have had a radioactive release and offsite radiation

-levels are expected to be > 1 REM per hour (gamma) or a child thyroid dose commitment of > 5 REM / hour. We will keep the Bureau of Radiological Protection ed.

(Give a short non-technical descripti6n t mer_ -

gency, the exust of the radioactive e, and potentially affected populations d s:)

^

M Gd

2. Pennsylvan i encyManagementknc (PEMA) v y

NOTE: If this is a r ss cation notific tion, go to :

Item 3, Unaf ntrol Room. :

(

NOTE: Where protective ac n a to be recom. :

men rgency Dire o d refer to the :

b______________ _ .. . ". _* . __ _ _________________

a. Telep n- MAdedicatedih( only during NORMAL work hour 0 _1600 Hrs. Monday - ay) or 9.783_8150 (Use when the dedicated line is out of service or after normal work hours. A diverter forwards this after normal work hours call to the PEMA Duty Officer).

NOTE: If no contact, proceed to Step 2.d. :

12.0 -

1004.4

?

- Revisfoh 9 INITIALS

b. MESSAGE: ASK FOR THE DUTY OFFICER This-is at the Three Mile Island Nuclear ~

'(name/titl e)

Station Unit I calling. We have declared an Emerg cy.

Give me the Operations Duty Officer. (When, Dut 0 answers): This is at the Thre s and (name/titl e)

Nuclear Station Unit 1 calling. We ha red a General Emergency a hours. We requ t t you contact the D

Bureau ation Protectio B au of Radiation Pro-tec n back should b the Radiological Line or 946- , 948-8071, 94 9. Based on Eme ency Direc-tor's judgement, deli of the follow tatements):

1. We have no a radioactive rele h wever, we have the pot ia significant 'o t e release.

2. J ad a radioactiv e and offsite radiation s are expected to be > 1 REM / hour (gama) or a child thyroid dose comitment of > 5 REH/ hour. We will keep the Bureau of Radiation Protection infomed.

13.0 ._

l

1004.4 Revision 9 ?

~'

INITIALS

3. Give a. short, non-technical description of the emer-

-gency and the extent of the radioactive release, and ,

potentially affected populations and areas:

b hY (tT M

c. If PEMA was o be contacted, t Dauphin County; advise t t PEMA cannot be Q d and request them to not , BRP, and Lan s r, ork, Lebanon and C and counties.

d. Messa verification Expect Bureau of a Protection (B ct after PEMA notificati no BRP confi t received within 30 s, notify PEMA of 1 n. If unable to contac 11 Dauphin Co d otify them that BRP has fied initial cant t. nstruct Dauphin County l to contNt PEMA and/or BRP.

3. Unaffected Control Room

a. Telephone: Use 8066, 8067 or 8068 or inter-control Room Ho t-Line.

I 14.0 ._

l

r 1004.4

?

Revisl6n 9

' INITIALS

b. MESSAGE: Emergency organization staffing is requestea but implementation of the Unit 2 Emergency Plan is not required.

(bive a brief description of plant status to the Shift Supervisor / Foreman).

m k

A

4. Parent and Four b Counties

a. Telephon ty separately ng, iver the message

1. Du i 911 or S-236-7 2 rk i-643-5111

3. ncaster 3

4. Lebanon . Af ho or Weekends 73- u

- 02b or Daytime 73 1 272 2

5. Cumber _ 9-238-9076

b. MESSAG -

Thi a Three flile Island 14uclear (name/titl e)

Station Unit 1 calling. We have ceclared a General Emergency l

l at hours. (Give a brief description of the l (time) l emergency. )

l i

i __ ._________...........______ ._.________..____.__.__________ ..__...

Each county must be notified independently and the

NOTE: :

l

message transmitted. :

I ._

15.0 l

l L f

1004.4

, .Revis~ ion 9 ?

INITIALS

5. . Institute of Nuclear Power Operations (Do not notify if this is a reclassific& tion notification).

a. Telephone : 1-(404)-953-0904 or contact the TM1 Site Operator for assistance

, b. MESSAGE: -

This is at the Three Mile 1 uclear (name/ti tl e) -

Station Unit lling. We have dec da neral Emergency at . (Give a brief crip ion (tim Q of th f emergency. ) b

% Et" n r M A\

BV (C9 A~ V

6. Pennsylvania 5t(t(t/ Police 9-234-4051 ,

MESSAGE:

This is A at the Th 11e Island Nuclear g/ title)

Station Unit 1 calling. We have declared a beneral Emergency at hours. We thave/have not) had a radioactive (time) release. We require imediate traffic control assistance in the vicinity of the (North / South) gate.

(

) 16.0 ._

1004.4

. Revis10'n 8 INITIALS

7. Radiation Management Corporation Emergencies (0800-1700) 73-1-215-243-2990 (1700-0800) 73-1-215-841-514_1 Offfce (0800-1700) 73-1-215-243-2950 MESSAGE:

-This is at the Three Mile I ear (name/ title)

Station Unit I We declared a Gene Emergency at 9 time hours. G @ief description o th emergency.)

We had a radioac elease. We (have/ e not) /do not) require assistance a ' tide. (Describe the as tance required if any.)

8. American Nuclea urers 74-1-203-673 MESSAGE: -

This is A at the Mile Island Nuclear

( / title) i- Station Unit 1 calling. We have declared a General Emergency at hours. (Give a brief description of the (time) emergency.) We had a radioactive release.

(have/have not) l I I l 17.0

? -_ . . .-- .-_- _ .. _ _ . _ _ - . , _ - - _ . - _ _ .

1004.4 Revis_lon 9 7 INITIALS

9. If medical assistance is required, notify the following agency:

Hershey Medical Center 9-534-8333 (ask for Outy Nurse)

Notification to be performed in accordance with procedure 1004.16.

10. Nuclear Regulatory Commission (NRC) - Bethesda, MD (Communications with NRC will be continuously tha following contact.)

a. Telephone: NRC Emergency Notificati S (ENS) (RED PHONE)

(If the EN n s inoperative, r fe Procedure 1004.6, "Additi A stance and Notif "

, for alternate not fi methods).

b. E:

-__-_- ---__ - __ __-_______---- ^ ----

NOTE: Complete this adapted from 0845) before :

contactin RRE (if this can be do ithout :

exceedi ne (1) hour noti at n time :

requ tain the info t om the Shift :

i : Sup ergency Direc :

Reque ak to the Duty b

y ty Officer's Name Time of Contact j This is at Three Mlle Island l Name/Titla l

l Nuclear Station, Unit 1. He have declared a(n) (select as appropriate).

, 50.72 (NON EMERGENCY) X GENERAL EMERGENCY (1004.4)

UNUSUAL EVENT (1004.1) TRANSPORTATION l ALERT (1004.2) PHYSICAL SECURITY; SAFECUARDS SITE AREA EMERGENCY (1004.3) OTHER CATEGORY 18.0 _

~

i

1004.4 Revision.9- ;

At hours on .

time date Provide the statement selected by the Shift Supervisor /

Emerg'ency Dir_ector to the NRC Duty Officer. _

1. We have not had a radioactive release, however, we have the potential for Significant rad release.

OR

2. We have had a radioactive re s offsite ra evels are expected >l REM / hour or a child thyro e commitment of >5 f

our. We will b k p ng the Bureau of Radiation Prot formed.

c. Give a short non-tech cription of the .ergency and ,

the extent of the ve release, a e entially affected popul d areas. N nW M

ww v w

EVENT TIME:

CAUSE:

POWER PRIOR TO EVENT:

POWER NOW:'

ANY SAFETY INJECTION OR ECCS7 19.0

-yy ---ur ----e y w e. w,w-, mr -e.w-----w ,,-m,y -*-----y ---+y y----- --. --w-.-r- g yw - , ---,w-y-.,es,---e h

1004.4 Revisforr 9 :

COOLING MODE:

ANY CONTAMINATION?. (QUANTIFY):

b W

ANY RELEASES: (QUANTIFY):

ctT

/>

AL 6% ~

CONTAINMENT STATUS (IF A ANY OTHER PROBLEMS M a M %

PLANS: _

^

&> " &S DATE TIM _- TION n PLETED BY i _______.____ _ _ .________________ ____________ _____________

NOTE: the NRC Duty Officer directs you to suspend :

I,

c tinuous coramunications infom the Officer a call :

back will be initiated if any significant changes :

occur. Document with Duty Officer Name, Time and :

Date in the Emergency Directors Log. :

1 J

20.0 t

1004.4 R: vision 9 ATTACHMENT I SECTION II NOTIFICATION CHECKLIST

TIME OF INITIAL NOTIFICATION TIME OF :

OR ESCALATION DE-ESCALATION OR CLOSE OUT :

. :: a :

:: UNUSUAL: SITE : GENERAL .- SUAL: : SITE : GENERAL :

AGENCY :: EVENT : ALEd:. EMERGENCY : EMERGE .

ENT : ALERT : EMERGENCY : EMERGENCY :

7 1 b : : :

l

Dauphin County :: : /:ji j/> : ::

:: : : :: N) : : , :

PEMA :: : V.: [V/ _

(N : : :

Unit 2 Control Room VV .

(N

(/f)::

i F

INPO :: : : -

/) :: : : : :

NRC ,_g : : : :n : : : :

: : y f: f : : : :

Hershey Medical CenV~ 12:_ ,_ * : *n *:

Yf,l A :

: // ' ' Q-/

State Police ::

_ *: %- . *: :: V A : :

: C./ / I : ::

RMC :: *: *: //t 4:

v

:: Q4/.7:/ k:: :

:: : : :: Y //'V

ANI :: *: *: -

A :: : (/ :/> : :

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

</ V i lI

Optional i e

l 21.0

1004.4 Revisi6n 9 !

' ~

ATTACHNENT I SECTION Ill SELONDARY CONTACT

'^

INITIALS The Comraunicator shall notify the following agencies sonnel and update the Attachment I,Section II checklist h notification.

1. Announce or have announced the following me r the plant page after turning on irens " ATTENTION LL RSONNEL, ATTENTION ALL PERSONhEL e eral Euergency 1 -D n tenainated. (Live a brief descri f the work rest ic o , i f any)". Repeat message and tu whei 3.

2. Bureau of R diat' E

a. Telephone: Rou . e or 9-767-3720

b. MESSAGE:

at the Three nd Nuclear (his is (n tge)

Station i alling. We ha lo d out the General Emergency at ours and initiated recovery operations.

(time) '

Please notify PEMA, Dauphin, Lancaster, York, Lebanon and Cumberland counties.

3. Unaffected Control Room

a. Telephone: 8066, 8067, 8066 22.0 _

1004._4 ,

~

, Revision 9 INITIALS

b. Message:

Notify" Shift, Supervisor / Foreman of close out of the Generel Emergency.

4. Nuclear Regulatory Comission Office - Bethesda, Md.

a. Telephone: Emergency Notification Systera (Ei45 (RED PHONE)

b. MESSAGE:

This is A at the Three I il land Huclear (name el Station t alling. We hav clo -out the General Emergency at //. hours and ini . overy operations.

5. _ If applicable, notify 1 ing persons a d/or a cies of the close-out of the Ge rgency;

a. Hershey Medic nter: 9-b34-8333 s Outy Hurse)

b. Pennsylv Police: 9-2

c. Radiatk ement Lorporation ' )

l Office N (0800-1700) 73-1-%15-243-2950 l Emergencies (0800-1700) 73-1-215-243-2990 l

l (1700-0800) 73-1-215-841-5141

d. American Nuclear Insurers: 74-1-203-677-7305

e. Others: As directed by the Emergency Director DATE TIf4E LOhPLEILD C0ffLETED BY 23.0 _

1004.,4, ,

Revision 9 ATTACHMENT I SECTION IV PROTECTIVE ACTION RECOMME!4DATION GUIDELINES THESE RECOMlENDATIONS MAY BE DELIVERED ONLY BY

.THE Et<iERLEl4CY DIRELTbR

1. Consideration shall be given to sheltering if:

a. Release time is expected to be short (Puff r e <z hours)

b. Evacuation cou t well underway p D expected plume arrival du t warning time, 19 wi d speeds, ana/or foul weather.

2. Consideration shall be given t v ion if:

a. A release is expected t uNith projected oses roaching or exceeding:

1 Rem Whole B nd/or 5 Rem Ch y id (AND)

b. Release time is expected to be long (>2 hours)

( Al40)

c. Evacuation can be well underway prior to plume arrival for above release, based upon wind speed and travel conditions.

24.0 ._

1004._4, ,

Revision 9 ATTACHMENT 11 EMERGENCY STATUS REPORT

~

SECTION 1 , ,

1. Description of Emergency:

M D v A

2. Has the Reactor tripp Yes / No

3. Did the Emergency Systems actuate D / No If so, which o

a. High Pr Injection Yes / No

b. Low Pressure Injection Yes / N

c. Core Flood v Yet / i.o

d. 4 PSIG Reactor Buil ation das

e. Reactor Buildin - Actuated 14 o

4. What is the stat

a. 'At power t plant Ov

! b. Hot standby

j. c. Hot shutdown

d. Cooling down

e. Reactor Pressure psig

f. Reactor Temperature *F

> 5. Is offsite power available Yes / No

6. Are both diesel generators operable Yes / No

- 25.0 _

1004.4 Revisl6n 9 7

. 7. _ Have any personnel injuries occurred Yes'/ No If so, is the injured person (s) contaminated Yes / 140 What are the approximate radiation and/or contamination levels ,

mk/hr ,

DPM/100 cm2

8. Are there excessive radiation levels and/or contaminat Level s Yes / No If so, list below:

a. Radiation levels: ody)

b. Contamination s DPM/10 At locatio :

v b _

DATE MPLETED BY

% 0 -

l l

f l

26.0

~

I 1004.4- )

Revision 9 ATTACHMENT II ,

i EMERGENCY STATUS REPORT

~

, , _ . SECTION II -

Fill out if a release has (is) occurring. Provide BkP al i le infomation for verification call.

1. What is the approximate radioactive sourte tenn dis te from the plant ( As determined by the Projected Dos ate ~ 1culation procedure 1004.7).

a. Noble gases .O V Li/sec D

b. Iodine a Ci/sec

2. What is the xi e meteoral

a. Wind speed mph

b. Wind direction .O

c. Stability class - Stgb ral/ Unstable

3. What is the project d e dy dose rate an odine co'icentre-tion at the nea f te downwind po

a. b mR/hr M

b. uCi/cc Iodine

. c. (Location) 1 4.- Estimated dL ation of the release

a. If the release is tenainated:

Start time Stop time Duration 4

27.0 .-

--e - - , -

1004.12 Revisfoh 5 !

m 10/05/83 IW ORTANT TO SAFETY

-NON-ENVIRONMENTAL I WACT RELATED

. THREE MILE ISLAND NUCLEAR STATION UNIT NO.-1 EMERGENCY PLAN IWLEMENTING PP.0CEDURE 1004.12 -

- ENVIRONMENTAL MONITORItG Table of Effective Pages Page Revision Page Revision Page Revision Pag sfon 1.0 5 2.0 5 3.0 5 4.0 4 5.0 4 6.0 4 7.0 4 8.0 4 Q 9.0 4

-10.0 4 11.0 0 12.0 0 13.0 0

@ v l s O l

1 y

/

fdac_ Signatu '*

/cm 3 Date

! Signature Date Document ID: 0030W l

, y-+-... y-,- .m-e- -

-, yv,- - -,w --

1004.12. .

Revision 5 THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EERGENCY PLAN IPPLEMENTING PROCEDURE 1004.12 ENVIRONMENTAL MONITORIPG 1.0 PURPOSE ,,.

The purpose of this procedure is to provide the requirements and methods

-for environmental monitoring during or after a declared em at Three Mile Island. The Environmental Assessment Coor'di C) is responsible for implementing this procedure.

2.0 ATTACHMENTS l 2.1 Attachment I - Program l 2.2 Attachment I ogical Environme ampling Program 3.0 Et1ERGENCY ACTIQn[

3.1 This p re s to be initita on declaration of the following:

a. Site Emergency 1 . V !

f: b. ' General Eme .4.

c. As direct he Emergency Direc 4.0 EMERGENCY ACTION I

Initial 4.1 Obtain effluent monitoring data (type of release, release rate, flow rate, release pathways, wind speed and direction, etc.) from the Radiological Assessment coordinator to determine the appro-priate environmental sample locations.

4.2 Dispatch offsite monitoring teams and the mobile monitoring lab

. when the Environmental Assessment Command Center is activated per procedure 1004.30.

1.0 -

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

1004.12

~

?

Revision 5 4.3 ' Ensure communications are established between the monitoring teams and the Environmental Assessment Command Center.

4.4 Inform members of, the monitoring teams to notify the EAC or RAC when their individual exposures are approaching 300 mrem; these members should then be relieved, if possible. Relief d be conducted in a low radiation area. Also inform't s to notify -

the EAC or RAC before they enter an area that a re e

respiratory protection.

4.5 When mobile lab o designated locati ensure that additional m o al information f oiit s portable tower is obtained. .

field data from the e lab and the monitoring teams 4.6 Ensure l 1s relayed to the Control the Hear-site rgency Operations Facility.

4.7 Ensure that all ef 1 nitoring data o the l Environmental A ent computer.

4.8 Determine e ency for the ch ge of the thermoluminescent l dosimete L ' ) listed in Attac I.

4.9 Determine spe ific types of samples and sampling frequencies l required to determine offsite radiological conditions. Refer to Attachment II.

4.10 Ensure that all samples are returned to the EACC for further analysis and retention.

4.11 Ensure that all samples are 1.abelled in accordance with Environmental Controls Procedures 9420-REM 4620.2 through 4620.10.

2.0 -

1004.12 i

Revisfon 5 4.12 -Ensure that environmental monitoring is continued to completion in l all situations, even though the emergency status has terminated before sampling _is. complete. , ,

4.13 Ensure that required sampling records are completed and maintained in accordance with procedure 1004.5 (Communications ord-keeping). Attach log to procedure.

5 .0 FINAL CONDITIONS 5.1 All samples have been analyzed and the res rted and evaluated.

9 0

@@ v g 0 t

i 3.0 _

l _ .- _ _. -

- 1004.12 .

ist:n 4; .

ATTACHENT I ENVIRONMENTAL MONITORING TMINS TLD PROGRAM n

HEIGHT DISTANCE ASIMUTH LOCATION FEET MILES o DESCRIPTION TM-ID- Al-1 4 0.4 North Weather Station TMI TM-ID-B1-1 3 1/2 0.7 North Bridge TMI TM-ID-D1-1 3 1/2 V 71 Top of Dike TMI TM-ID-El-1 4 I 95 Top of Dike TMI TM-ID-H1-1 6 04 167 ole No.33-E-T-60, SSE TMI ,

TM-ID-J1-1 4 1/2 0.8 184 South TMI TM-I D-K1-2 6 0.4 V1 9 Pole No.E-33-T-28, South j Parking Lot TMI TM-ID-L1-1 4 1 Mechanical Draft Towers TMI TM-ID-N1-1 7 .4 l 270 Q Due West on Shelley's-j land TM-ID-P1-1 3 1/2 0.4 293 Sh y's Island t

TM-ID-Q1-1 6 1/2 0.5 317 , sland I

TM-I D-Rl-1 4 0.2 340 Nort b TMI l1 TM-ID-Cl-1 3 0.6 35 Route 441 Nj ,

TM-ID-DI-2 7 0.5 65 Laurel Road ;

TM-ID-El-2 3 0.4 90 Observation Center TM-I D-F1-1 6 0.5 117 Route 441 N. on Light Pole 4.0 i

W -12 -

sicn 4 ATTACHENT I (Cont'd) i HEIGHT DISTANCE ASIMUTH LOCATION FEET MILES 0 DESCRIPTION TM-ID-Gi-2 3 0.6 143 Route 441 S.

i TM-ID-L1-2 6 0.5 221 Beech Island

- TM-I D-R1-2 5 0.7 3 Hanry Island j TM-ID-K2-1 4 1.1 Shelley's Island 4

TM-ID-L2-1 6 II 227 Route 262 Pole No.E2890, j j BK722-306 .

TM-I D-M2-1 4 253 V 1 oldsboro Air Station TM-ID-N2-1 7 1.2 262 Goldsboro Marina on Light Pole l TM-ID-P2-1 7 1.4 j Still House Road on Tree TM-ID-Q2-1 5 .8 West Shore along River j TM-ID-A3-1 4 358 Middletown Substation 4

] TM-ID-H3-1 4 . II 159 mouth-Collins Substation i I TM-ID- AS-1 6 4.3 3 V S eet Exit From Route l No.E2481-10 TM-I D-BS-1 6 4.8 18 Scho Lane and Miller Road, pq 782-10 TM-ID-CS-1 6 4.5 42 Kennedy Lan' Pole No.74-E-97 l

TM-ID-D6-1 4 5.2 65 Beagle Road, Pole No. E1418 ;

5.0 l

l 1

,94,12 sien 4 ATTACHENT I (Cont'd)

HEIGHT DISTANCE ASIMUTH LOCATION FEET MILES o DESCRIPTION TM-ID-ES-1 6 4.6 81 N. Market Street (Route 230) -

and Zaeger Road, Pole No.PP and L 31084, 530386 TM-ID-FS-1 6 4.7 Amosite Road, Pole No.PP and L 31016, S29272 -

TM-ID-G5-1 6 4.8 Bainbridge Road (Route 241) and Risser Road, Pole No.ME825' TM-ID-HS-1 6 1/2 .I fl\ . 157 uard Shack at Brunner Island.

TM-ID-J 5-1 6 .9 182 ! anal' Road, Conewago Heights, i Pole No.E497EM, BK244122 TM-ID-KS-1 6 5.0 00 Conewago Creek Road, Strines-q town, Pole No.E924CE, BANK j 231 139 TM-ID-LS-1 6 .1 Stevens and Wilson Roads, Pole No. ME2521NB TM-I D-MS-1 6 4 249 4 ewisberry and Roxberry Roads, errytown, Pole No.E725NB

, TM-ID-NS-1 6 4.9 268 R od Drive, Pole

. 2 NB

^ Beinhower Road, TM-ID-PS-1 6 4.9 281 Rou Pole o.

}

TM-ID-QS-1 6 5.0 318 Lumber Strd , Highspire, Pole No.PP and L 26827, S31990 ,

TM-ID-B10-1 6 9.4 21 West Areba Ave., and Mill Street, Hershey, Pole No.PP and L 30383, S34608 6.0

10(, '

Revi. .~ 4 ATTACHENT I (Cont'd) l HEIGHT DISTANCE AZIMUTH j LOCATION FEET MILES o DESCRIPTION 2

TM-ID-E7-1 6 6.8 86 Hummelstown Street Eliza- l.

bethtown, Pole No.PP and L 32190, 530207 TM-ID-G10-1 4 .8 127 Drager Farm -

1 .6 Cumberland Street (Route TM-ID-C20-1 4 47 j l1 422) at 16th Street, Sub.-

j tion, Lebanon 6 TM-ID-D15-1 6 10.8 63 1S, 241, Lawr i

TM-ID-F25-1 6 21.1 3 Sleel Way and Loop Roads, Lancaster, Pole PP and L 21274, 39808, S36930 q

TM-ID-G15-1 5 1/2 14.4 '4 Columbia TM-ID-J15-1 4 180 North York Substation i TM-ID-P15-1 6 1. 300 4 Er d Road, Camp Hill, Pole j

(/[jlI No nd L 23347, enn Harris Hotel TM-ID-Q15-1 3 1/2 13.4 - West Substation TM-ID-Q15-2 6 11.5 310 Penn an Sts.,Hbg.,

Pole No. p 74, S35291 l

! TM-ID-RS-1 6 4.9 339 SpringGardend e and Route J 441 Pole No. PP and L 27716, '

i S232497 ,

7.0 1

4 10c '2 - -

Rev. '4 ATTACHENT I (Cont'd)

HEIGHT DISTANCE AZIMUTH LOCATION MILES o DESCRIPTION

_ FEET i TWID-C8-1 6 7.2 48 (Conewago School) Met-Ed 1039 CW 764/185 on School House Road Rd.1/8 mi. W of l; Schenk's Church

, T U ID-D9-1 6 1/2 5 72 (Bellaire) PP and L 32920 S l t 31503 1/4 mi. E. of Bellaire 1

I Crossroads on Mt. Gretna Rd.

II ,

TWID-F10-1 6 1/2 .i 112 megal Springs) PP and. L 33225 31/8 mi. W of Colebrook j d Donegal Springs Rd inter-j tion on Donegal Springs Rd.

I;i TWID-H8-1 6 1/2 7.4 (Starview) Met-Ed 193 EM 1/8

- , mi. N of Starview Methodist I

I Church in Starview on -

I Saginaw Road

]

TWID-H15-1 6 1/2 .2 157 (Wilshire Hills! ME793SE SW 1 orner of Orchard Rd and

! 4S d Rd., Wilshire Hills l fI i TWID-J7-1 6 1/2 6.5 1 177 i er) C53-LIM E240 MT l j ,

i Ma Street in Manchester j

acro gh Street at ,

corner t Drive l

i

^

TM-ID-K8-1 6 1/2 7.4 1% (Zion's CE SE corner of Co er Road and Rt. 295 In ection,

) TWID-K15-1 6 1/2 12.7 204 (Weiglestown) Alta Vista Road, i j .at Dover Township Fire House l <

8.0 1

i

- ,04.12

, 'si::a 4 ATTACHENT I (Cont'd)

HEIGHT DISTANCE AZIMUTH LOCATION FEET MILES o DESCRIPTION TM-ID-L8-1 6 1/2 8.0 225 (Andersontown) E611-D0-2017/

100 on Rohler's Church Rd.,1/8 mi SW of Orchard TM-ID-L15-1 6 1/2 11.7 2 (Mt. Royal) E30E3-D0 Bank l

! 321-232 W. Side of Rt. 74 at j

Mt. Royal Full Gospel Church TM-ID-M9-1 6 1/2 la 242 (Maytown) Pole No. SWP W281 SPPS 540 i

l on Alpine Rd.150 yds S of j ,

t.177 at Maytown l

! TM-ID-M15-1 6 1/2 11.9 237 i (Rossville) E 574 WR Bank l

474-100 W. Side of Rt 74-l 1/4 mi. from Rt.177 cross-l , roads by Earth Craft Barn l '

! TM-ID-Nu-1 6 1/2 7.8 ) (Lewisberry) PP and L 24599 j j S 29513 W side Rt 382 -1/2 1 mi. N of Lewisberry TM-ID-N15-2 6 1/2 .

I 274 4 Lisburn) PP and L E3149 S 30533 l s

II j j akcorner of Lisburn

t. of Lisburn Rd and (Rt 114) i TM-ID-N15-1 6 1/2 13.2 276 ) PP and L 21728 i , S Orchard Lane and i Her pe S of water '

tower I TM-ID-P8-1 6 1/2 8.0 292 (Reeser's signit) PP and L l

24757 S 31644 on Ever' green Rd ,

{

by Fairview Brethren in Christ 6 j Church Reeser's Summit' l

i j 9.0 i

9 i

04.12

'sion 4-ATTACHENT I (Cont'd)

HEIGHT DISTANCE AZIMUTH LOCATION FEET MILES o DESCRIPTION TM ID-Q9-1 6 1/2 8.5 308 (Steelton) PP and L 21570 -

l 5 32926 across from parking lot of Steelton Water Co.

TM-I D-R9-1 7 8.1 (Rutherford Heights) PP and L l 27280 S 34073 on Derry St. at .

66th -St. Rutherford Heights, I NE corner Ii TM-ID-R15_1 6 j 1. 330 (Colonial Park) Rt. 22 W. and

olonial Rd. on pole ~ adjacent to gas station 1

NOTE: Seventy _three (73) s s are exchanged :

quarterly, including ni wy} 19) quality control :

locations. Any thirty _ l ons are required :

per Environmental Technica; S i ications. :

f1 i

I lI i

t 4

0 10.0

9

100 R :.y . .

0' ENVIRONENTAL MONITORING ATTACHENT II RADIOLOGICAL ENVIRONENTAL SAPFLING PROGRAM The basic objective of radiological environmental analysis is the protection of people in the -

surrounding area from exposure to radiation in excess of the maximum permissible levels and guidelines, or fractions thereof.

The following table should be used in determining environmental samples (and quantity to be sampled):

TABLE I I

Quantity / Volume I j ,

Medium Sampled EacS Sample Anal sj s Preferre tion .

Vv Gross (/ P Air-particulate 7E4 cc (25 ft3) Beta, gamma Downwind from sii u

-Air-Iodine 7E4 cc (25 ft3) Beta, gamma ind from site A

Cshs l, Air-Noble Gases 7E4 cc (25 ft3) Bet a Dow M site

\J Gross V '

Water-River 2 liters Beta n I

10 downriv e (Note 1) Isotope f .2 upstream fr sit r control I /A ^

Nater-Tap 2 liters Gamma rom control -2 m

,(Note 2) Isotope ownwind from site Soil I kg. Gamma 2 from control ~25km from t Isotope 6 downwind from site I (Note 3) ,

i 4

11.0

'f

gg ,

R7,v . ., 'O TABLE I (Cont'd)

Quantity / Volume -

Medium Sampled Each 3 ample Analysis Preferred Sample Location Vegetation 1 kg. Gama 2 from control -25 km from site (Note 3 Isotope 6 downwind from site -

Milk 2 liters I 131 C 137 Sr90 4 fr trol ~25km from site (Note 4) I d from site Precipitation 2 liters Gam Onsite c vv vq ~

l 4

Ol 06, O. :

12.0 .

1004.12 Reviston 0 t ENVIRONMENTAL MONITORING ATTACHMENT II

(

RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM Note 1: Upstream samples should be a minimum of 10km up plant outfall.

Note 2: Control samples should come from least pr a wind direction from township 1) water supply.

Note 3: Control sa ld come from le alent wind direction at nea s te for sample nt 111ty. Downwind samples shou taken at/near TLD c ns for sample accountability.

ies in least

( Note 4: Milk samples should reated milk f prevalent wind dir for control pur o TO BE COLLECT N EMERGENCY CONDITIONS, NOT ALL SAMPLES ON TA HOWEVER, A REPRESEN MPLE SHOULD BE TA THOSE LISTED, AS TIME PERMITS.

C' This procedure may continue for a relatively long period of time after the i

emergency has been cancelled. As a minimum, this procedure should continue in effect until all required samples have been collected, prepared, and f

i analyzed. ,

1 13.0 -

, -- ,ge,.mn-m -mnnr-- .g-a- -

9.-.-v gy----y.- y,w,.e,am-,m-- rg,.- -e<n,, ,,.---r a4om,---.-m,,,,----,mm.,,ge., , .,

ML20090G868

Text

Description:

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