Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 1004.31 Re Airborne Radioactivity Sampling & Analysis & 1004.29 Re Activation of Operations Support Ctr
	ML20039B019
Person / Time
Site:	Three Mile Island
Issue date:	11/13/1981
From:	Nelson M, Ross M; METROPOLITAN EDISON CO.
To:	;
Shared Package
ML20039B015	List: ML20039B017; ML20039B019;
References
	PROC-811113-01, NUDOCS 8112220189
	Download: ML20039B019 (175)
	v • d • e

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FOR USE IN UNIT I ONLY

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1004.1 Revision 5 11/13/81 IWORTANT TO SAFETY NON-ENVIRONENTAL IMPACT RELATED CONTROLLED COPY FOR THREE MILE ISLAND NUCLEAR STATION USE IN UNIT I ONLY UNIT NO.1 EMERGENCY PLAN IMPLEENTING PROCEDURE 1004.1 UNUSUAL EVENT Table of Effective Pages

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Page Revision Page Revision Page Revision Page Revision 1.0 4 21.0 5 2.0 5 22.0 4 3.0 5 23.0 4 4.0 4 24.0 4 5.0 4 25.0 4 6.0 5 26.0 5 7.0 5 27.0 5 80 5 28.0 5 9.0 4 29.0 5 10.0 4 11.0 4 12.0 4 13.0 4 14.0 4 15.0 4 16.0 4

{VT 17.0 5 18.0 5 19.0 4 20.0 4 Unit 1 Staff Recommends Approval

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Approval /V Date j Cognizant Dept. Head Unit 1 PORC Recommends Approval

() { fi/ f?& Date // 2 /

Chairman of PORC l

Man ger TMI I Approval M

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Date // /b l QA Modifications / Operations Mgr k Date DOCUENT ID: 0023W F( ' ' "1 i sJ UNIT ! ONLY paA:288arabasiB9 p PDR

FOR USE IN UNIT I ONLY 1004.1 Revision 4 THREE MILE ISLAND NUCLEAR STATION

(] UNIT 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.1 UNUSUAL EVENT 1.0 PURPOSE The purpose of this procedure is to define the conditions that shall be regarded as an Unusual Event for Three Mile Island Nuclear Station (Unit 1) and to:

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

b. Ensure necessary actions are taken to notify GPU-Muclear management and offsite emergency response organizations.

c. Mobilize the appropriate portions of the emergency response organization to initiate appropriate emergency actions.

The Emergency Director is responsible for implementing this procedure.

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(i~ ! NOTE: Emergency Director responsibilities that may NOT be !

! delegated include: ;

a. Decision to notify offsite emergency management agencies.

b. Making protective action recommendations as necessary to offsite emergency management agencies.

c. Classification of Emergency Event.

d. Determining the necessity for onsite evacuation based upon potential exposure to non-essential personnel.

e. Authorization for emergency workers to exceed 10 CFR 20 radiation exposure limits.

2.0 ATTACHMENTS 2.1 Attachment I, Unusual Event Notifications

( i 2.2 Attachment II, Emergency Status Report.

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1 FOR USE IN UNIT I ONLY 1004.1 Revision 5 2.3 Attachment III, Checklist for Notification of Significant Events Made in Accordance with 10 CFR 50.72.

3.0 EERGENCY ACTION LEVELS INITIATING CONDITION INDICATION 3.1 Reactor trip follcwed by an Reactor trip alarm (F-1-1) unplanned automatic ECCS followed by HP Injection Flow initiation. alarm (E-2-6 and/or E-3-6).

3.2 Radiological effluent technical As indicated by a valid Alert specification limits being alarm on RM-AS, RM-A8, RM-A9, approached. or RM-L7.

3.3 Reactor coolant total activity As indicated by either:

> 50 pCi/ml but < 130 uCi/ml a. Reactor coolant specific indicating possible fuel defect. activity as determined by sample and analysis.*

b. RM-L1 Low > 6.35 x 104 cpm but < T.65 x 105 cqm.

c. RM-L1 High > 1.11 x 103 cpm but <2.7 x 103 cpm.

pd 3.4 Abnormal coolant temperature and/ Any condition whereby the or pressure or abnormal fuel tem- Technical Specification Safety peratures outside of technical Limits 2.1.1 and 2.1.2 are specification limits. excet.ded without a reactor trip and confirmed by an engineering analysis.

3.5 Exceeding primary system leak As indicated by either:

rate technical specification. a. Total reactor coolant leakage > 10 gpm as measured by daily leak rate test.

b. Unidentified reactor coolant leakage > 1 gpm as measured by daily leak rate test.

3.6 Failure of a safety or relief Failure of the following to valve in a safety releated system close:

to close following reduction of a. Pressurizer Safety applicable pressure. Valve (s), Power Operated I

Relief Valve (s) or OTSG safety valve (s) as indicated by the accous-tical valve monitoring or flow measuring equipment.*

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FOR USE IN UNIT I ONLY 1004.1 Revision 5 t b. OTSG Atmospheric Relief

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Valve (s) or Decay Heat ,

System relief valve.

3.7 A loss of On-site AC power As indicated by a loss of the resulting in a technical Specifi- ability to meet any of the cation shutdown. conditions of Technical Specification Limiting Condition for Operation 3.7.2.

3.8 A sustained loss of offsite power As indicated by a reactor trip resulting in a reactor trip. caused by loss of power.

3.9 Loss of containment integrity As indicated by a loss of the requiring shutdown by technical ability to meet any one of the specifications. conditions of Technical Specification Limiting Condition for Operation 3.6.

3.10 Loss of engineered safety As indicated by a loss of the features or fire protection ability to meet any one of the system function requiring shut- conditions requiring shutdown down by technical specifications of Technical Specification (e.g. because of malfunction, limiting Conditions of Opera-personnel error or procedural tion 3.3 or 3.18.

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inadequacy).

3.11 Fire in a permanent plant struc- Shif t Supervisors judgement, ture which cannot be controlled based on advice of the fire by the fire brigade within 10 brigade leader.

minutes of discovery.

3.12 Fire outside plant structures Shif t Supervisors judgement, requiring offsite firefighting based on request of the fire assistance. brigade leader for offsite firefighting assistance.

3.13 Indications or alarms on process As indicated by a loss of or effluent parameters not indications, assessment or functional in control room to an communications cability extent requiring plant shutdown requiring plant shutdown as or other significant loss of determined by the Shift Super-assessment or communicatin capa- visor.

bility (e.g., plant computer, Safety Parameter Display System, all meteorological instrumentation).

3.14 Security threat or attempted entry Shif t Supervisor's judgment, or attempted sabotage, based on advice of the Security Duty Sergeant.

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FOR USE IN UNIT l ONLY 1004.1 Revision 4 i 3.15 Natural phenomenon being exper- As indicated by any one of the

.V ienced or projected beyond usual following:

levels. a. A valid alarm on PRF-1-2 (>-

.019) "Theshold Seismic Condition" indicating an earthquake.

b. A projected river stage >

302 ft. at the River Water In-take Structure (50 year flood level).

c. High winds > 75 mph as indicated oli Wind Speed Recorder (NDS-501) or National Weather Service projection of tornado or hurricane force winds.

3.16 Other hazards being experienced As indicated by any one of the or projected. following as judged by the Shift Supervisor.

a. Onsite aircraft crash outside the protected area fence and not impacting permanent plant structures.

b. Train derailment within the Exclusion Area.

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c. Unanticipated explosion detected near or onsite.

d. Near or onsite toxig or flammable gas or liquid release which could affect the habitability required for nomal plant operability,

e. Turbine rotating compo-nent failure causing a Reactor trip.

3.17 Transporation of any contaminated As judged by the Shif t Super- l injured personnel from site to visor.

offsite medical facility.

3.18 Valid, unanticipated ALERT alarms Any two or more radiation on any two or more area and/or monitor ALERT alams are process radiation monitors at the received in the Control Room same time. simultaneously.

3.19 A reactor trip caused by As indicated by reactor trip either: caused by a validated low-flow

a. Any reactor coolant pump trip or by a total loss of failure. feedwater.

Q,m b. Total loss of ability to l feed 0TSG.

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FOR USE IN UNIT I ONLY 1004.1 Revision 4 3.20 Valid i'eactor Building Evacuation Receipt of a valid Reactor kq) Al a m. Building Evacuation Alarm.

3.21 Unanticipated positive reactivity As detemined by the Shift insertion potentially degrading Supervisor or as indicated by the level of safety of the plant. any one of the following:

a. An uncompensated opera-ting reactivity change resulting in a valid high i reactor coolant outlet temperature alam,

b. An unanticipated criti-cality.

c. An inadvertent rod '

withdrawal at power operations resulting in a reactor trip.

d. An inadvertent moderator dilution resulting in a valid high reactor coolant outlet temperature alam and/cr a Reactor trip.

3.22 Stuck-Out, Stuck-In or Dropped As indicated by a loss of the Control Rod requiring shutdown ability to meet any of the p by Technical Specifications. conditions of Technical Specifications Limiting 1

Conditions of Operation 3.5.2.2 for one control rod.

3.23 Other plant conditions exist Shift Supervisor judges that:

that warrant increased awareness a. Unit shutdown is other on the part of State and/or Local than a normal controlled offsite authorities. shutdown. For example, the cooldown rate exceeds Technical Specification Limits.

b. Unit is in other than a normal condition during operation and the abnormal condition is of such a nature as to warrant notification. For example, cracking is found in primary system piping during operation.

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c. Any other condition exists which has the potential for escalating into a higher level of emergency and, therefore, warrants notification.

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

4.0 EERGENCY ACTIONS Initial s 4.1 Upon recognition that any of the action levels above have been reached or exceeded, the Shift Supervisor shall assume the duties of Emergency Director. (Event should be assessed and declared within ten (10) minutes of the occurrence.)

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

NOTE: Turn on Whelen siren switch. :

" ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: AN UNUSUAL EVENT HAS BEEN DECLARED IN UNIT ONE. ALL ENERS OF THE ON-SHIFT EERGENCY ORGANIZATION REPORT TO YOUR STATIONS. ALL OTHER PERSONNEL SHOULD CONTINUE WITH THEIR NORMAL DUTIES l UNLESS FURTHER INSTRUCTION IS GIVEN. Give a brief description of the event and repeat the announcement.)

NOTE: Turn off Whelen siren switch. :

4.3 Announce to the Control Room personnel that Name has assumed the duties of Emergency Director.

) 4.4 Assign a Communicator to make notifications to persons and/or encies )er Attachment I,Section I.

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FOR USE IN UNIT I ONLY 1004.1 Revision 5 4.5 Contact the Duty Section Superintendent and discuss:

a. Plant status

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

4.6 Depending on the emergency action level which was reached or exceeded, ensure that the appropriate Emergency Operating Procedures have been implemented and/or the following Emergency Plan Implementing Procedures as required:

a. Contaminated Injuries and Radiation Overexposure (1004.16)

b. High winds - Tornado /High Winds (1004.22).

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

4.8 If local services (fire, ambulance, police) are required, ,

direct the Communicator 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 Ambulance). Security should be advised to Dosimetry Badge Issuance.

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NOTE: If the Emergency Response personnel are required to :

respond outside the protected area affected by a :

radioactive plume, the Emergency Director or his :

designee will direct the issuance of TLD's from the :

North or South gate. :

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

a. Dispatch offsite and/or onsite radiatico monitoring teams in accodance with EPIP 1004.10 and 1004.11.

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b. Implement Offsite Dose Projections procedure (1004.7).

4.10 If additicnl resources or notifications are required, refer j to additional Assistance and Notification Procedure (1004.6).

4.11 If the emergency involves in-plant radiological controls problems, direct the Radiological Assessment Coordinator to CN implement in plant Radiological Controls During Emergencies (1004.9).

4.12 Assign an individual to complete Attachment II,Section I and give to the Radiological Assessment Coordinator to transmit to the Bureau of Radiation Protection.

4.13 Direct the Radiological Assessment Coordinator to complete Attachment II,Section II to transmit to the Bureau of Radiation Protection if a radioactive release has occurred or is occurring.

4.14 Stop all liquid and gaseous discharges that are in progress until an assessment of their impact is performed and specific approval is given to continue the release by the Emergency Director.

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4.15 Verify that communications and documentation are maintained f

per procedure Communications and Recordkeeping (1004.5).

4.16 If applicable, direct the operations Coordinator to dispatch Emergency Repair / Operations personnel to investigate the identified problem area in accordance with procedure 1004.21.

4.17 Af ter 30 minutes, confirm that BRP verification has been made. If no verification, instruct the Communicator to proceed to Attachment I, Section 1.2.(d).

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FOR ~USE lN UNIT I ONLY 1004.1 Revision 4 4.18 Based upon assessment of plant conditions, either close out

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the Unusual Event or escalate to a higher class of emergency.

a. If Recovery Phase criteria have been met (see Recovery Procedure 1004.24), close out the Unusual Event by directing the Communicator to perfonn the notifications in Attachment I,Section II. l Implement the Recovery Procedure (1004.24).

b. If emergency action levels exceed those for an l Unusual Event, escalate to a higher class, notify BRP on Radiological Line and make remaining notifications in accordance with the appropriate emergency procedure as specified in Step 5.1.

4.19 If necessary, due to potential contamination of normally I non-contaminated sumps and/or tanks, or the need to closely monitor liquid releases, initiate procedure 1004.14, Monitoring / Controlling Liquid Discharges For Nonnally Uncontaminated Systems.

5.0 FINAL CONDITIONS 5.1 A higher class of emergency has been declared by the Emergency Director after meeting or exceeding an emergency action level of one of the higher classes and one of the following

. procedures is being implemented:

a. Alert (1004.2)

b. Site Emergency (1004.3)

c. General Emergency (1004.4)

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( 5.2 The Unusual Event has been closed out since no recovery operations are required.

5.3 The Unusual Event can be shifted to a recovery mode by implementing the procedure Rucovery Operations (1004.24).

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. .FOR.USE IN UNIT .I ONLY 1004.1 Revision 4 i ATTACHMENT I SECTION I-INITIAL CONTACT INITIAL The Communicator shall notify the following agencies and personnel, and update the Attachment I,Section II checklist for each notification.

1. DAUPHIN COUNTY EMERGENCY OPERATION CENTER (If this is a reclassification notification, go to Item 3, Unaffected Control Room).

a. Telephone: 9-911 or 9-236-7976

b. Message:

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

Nuclear Station Unit I calling. We have declared an

/ Unusual Event at hours, and (based upon (v] (time)

Emergency Director judgement, deliver one of the following statements):

1) We have not had a radioactive release OR

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, but do not know if there will be detectable changes in offsite radiation levels. We will be keeping the Bureau of Radiation Protection (bhp) informed of the results of q our investigation, OR U

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{f 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 levels but they are expected to be less than the levels calling for an alert. We will be keeping the Bureau of Radiation Protection infonned.

c. Give a short non-technical description of the emergency and any potentially affected population and areas.

D Op.

2. PENNSYLVANIA EMERGENCY MANAGEMENT AGENCY (PEMA)

(If this is a reclassification notification, go to Item 3, Unaffected Control Room)

a. Telephone: 9-783-8150. ( A diverter forwards this call to a PEMA duty officer after working hours.)

i NOTE: If no contact, proceed to step 2.d. !

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INITIAL CONTACT

b. Message:

This is Three Mile Island Nuclear Station Unit I calli ng. We have an emergency. Give me the Operations Duty Officer. (When Duty Officer answers:)

This is at the Three Mile Island

( name/titl e)

Nuclear Station Unit 1 calling. We have declared an Unusual Event at hours. We request you (time) contact Bureau of Radiation Protection. Bureau of Radiation Protection call back should be made on the Radiolgoical Line or 948-8069, 948-8071 or 944-0839.

(Based upon Emergency Director judgement, deliver one of the following statements):

1) We have not had a radioactive release, OR

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, but do not know if there will be detectable changes in offsite radiation levels. We will be keeping the Bureau of Radiation Protection informed of the results of our investigation, OR O~

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FOR USE-lN UNIT 1 ONLY 1004.1 Revision 4 ATTACHMENT I SECTION I INITIALCONTAE

4) We have had a radi sactive release and expect to be able to detect changes in offsite radiation levels, but they will be less than the levels calling for an Alert. We will be keeping the Bureau of Radiation Protection infonned.

c. Give a short non-technical description of the emergency, and any potentially affected populations and areas:

d. If PEMA was unable to be contacted, contact Dauphin County; advise them that PEMA cannot be contacted and direct them to notify PEMA, BRP, and Lancaster, York, Lebanon, and Cumberland counties.

e. Message verification:

Expect Bureau of Radiation Protection (BRP) contact after PEMA notification. If no BRP confirmation is received within 30 minutes, notify PEMA of the situation. If unable to contact PEMA (line busy), call Dauphin County and notify them that BRP has not verified initial contact. Request Dauphin County to contact PEMA and/or BRP.

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FOR USE IN UNIT I ONLY 1004.1 Revision 4 ATTACHMENT I SECTION I INITIAL CONTACT INITIAL

3. UNAFFECTED CONTROL ROOM

a. Telephone: 8066, 8067, 8068 or inter Control Room Hot-Line ,

b. MESSAGE:

Give a brief description of Plant Status to Shif t Supervisor.

4. INSTITUTE OF NUCLEAR POWER OPERATIONS (Do not notify if this is a reclassification notification.)

a. Telephone: 404-953-0904

b. MESSAGE:

This is at Three Mile Island (name/ title)

Nuclear Station Unit I calling. We have declared an Unusual Event at Lours. (Give a>brief

( time) description of the emergency.)

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INITIAL CONTACT INITIAL

5. Notify the following personnel / agencies if the emergency situation is such that notification is deemed appropriate:

a. Hershey Medical Center 9-534-8333 Notification to be" performed per procedure 1004.16.

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

This is at the Three Mile Island Nuclear

( name/ title)

Station Unit 1 calling. We have declared an Unusual Event at hours. We had a (time) (have/have not) radioactive release. We require assistance as follows:

(State any assistance required).

c. Radiation Management Corporation 73-1-215-243-2950 EMERGENCY NUMBER:

73-1-215-243-2990 l

l MESSAGE:

l This is at the Three Mile Island Nuclear

( name/ title)

Station Unit 1 calling. We have declared an Unusual Event

at hours. (Give a brief description of the

( time) emergency). We __ had a radioactive (have/have not) release. We require the following assistance: (State

( any assistance required.)

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FOR USE IN UNIT i ONLY 1004.1 Revision 5 ATTACHENT I SECTION I INITIAL CONTACT INITIAL

d. American Nuclear Insurers 74-1-203-677-7305 or 9-1-800-243-3172/3173 (after nonnal working hours)

ESSAGE:

This is at the Three Mile Island I name/ title)

Nuclear Station Unit 1 calling. We have declared an

., Unusual Event at hours. (Give a brief

( time) description of the emergency).

6. NUCLEAR REGULATORY COMMISSION OFFICE Bethesda, MD.

(Communications with the NRC will be continuously maintained following contact.)

a. Telephone: Emergency Notification System (ENS)

b. ESSAGE:

This is at Three Mile Island Nuclear (name/ title)

Station Unit I calling. We declared an Unusual Event at hours.

( time)

1) We have not had a radioactive release, OR O

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FOR USE IN UNIT 1 ONLY 1004.1 Revision 5 ATTACHENT I SECTION I INITIAL CONTACT i

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, but do not know if there will be detectable changes in offsite radiation levels. We will be keeping the Bureau of Radiation Protection informed of the results of our investigation, OR

4) We have had a radioactive release and expect to be

! able to detect changes in offsite radiation levels but they will be less than the levels calling for an

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Alert. We expect these levels to be less than 10 mrem /hr (gamma). We will be keeping the Bureau of Radiation Protection infonned.

c. Give a short non-technical description of emergency and l potentially affected populations and i

areas:

l l DATE TIE OF COWLETION COWLETED BY

NOTE: After initial NRC notification is complete per :

Attachment I,Section I above, refer to the NRC :

l : 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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.FOR USE IN i) NIT I ONLY 1004.1 Revision 4 ATTACHMENT I SECTION II SECONDARY CONTACT INITIAL The Communicator shall notify the following agencies and personnel and update the Attachment I,Section II checklist:

1. Bureau of Radiaton Protection

a. Telephone: Radiological Line

b. MESSAGE:

This is at the Three Mile Island Nuclear (name/ title)

Station Unit 1. We have closed-out the Unusual Event at hours.

(time)

Please notify PEMA, Dauphin, Lancaster, York Lebanon and

( Cumberland counties.

2. Unaffected Control Room

a. Telephone: 8066, 8067, 8068

b. MESSAGE:

Notify Shift Supervisor of close-out of the Unusual Event.

3. Nuclear Regulatory Commission Office - Bethesda, Md.

a. Telephone: Emergency Notification System (ENS)

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FOR USE IN UNIT-1 ONLY 1004.1 Revision 4 ATTACHMENT I SECTION II

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SECONDARY CONTACT INITIAL (RED PHONE)

b. MESSAGE:

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

. Nuclear Station Unit I. We have closed-out the Unusual L

Event at hours.

(time)

4. If applicable, notify the following persons and/or agencies of close-out of the Unusual Event:

a. Hershey Medical Center: 9-534-8333

( b. Pennsylvania State Police: 9-234-4051'

c. Radiation Management Corporation (RMC):

73-1-215-243-2950 or 73-1-215-243-2990

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

e. Others: As directed by the Emergency Director.

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1004.1 Revision 5 {V i ATTACHENT I

~Ti SECTION 11 g NOTIFICATION CHECKLIST 2

$$ TIE OF INITIAL NOTIFICATION TIE OF $ C OR ESCALATION DE-ESCALATION OR CLOSE OUT : (f)

ITI O: :: UNUSUAL: : SITE : GENERAL :: UNUSUAL: : SITE : GENERAL :

y: AGENCY :: EVENT : ALERT : EERGENCY :EERGENCY:: EVENT : ALERT : EERGENCY : EERGENCY :

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Dauphin County :: : : : :: : : : : -

- :: : : : :: : : : : L

'#3:: PEMA :: : : : :: : : : :

7 R: :: : : : :: : : : : 2

Unit 2 Control Room :: : : : :: : : :

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INPO :: : : : :: : : : :

r-I; : NRC O

f-: :: : : : :: : : : : Z

~~, : Hershey Medical Center :: *: *: *: * :: : : : : r--

9: :: : : : :: : : : :

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--- : State Police :: *: *: *: :: : : : :

C):: Rac :: *: *: *: * :: : - : : :

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ANI :: *: *: : :: : : :

-s : B and W :: N/A : N/A : : :: : : : :

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

Optional 21.0

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FOR USE IN UNIT 1 ONLY 1004.1 '

Revision 4 ATTACHMENT II EMERGENCY STATUS REPORT SECTION I

1. Description of Emergency:

2. Has the Reactor tripped Yes / No

3. Did the Emergency Safeguards Systems actuate Yes / No If so, which ones

a. High Pressure Injection Yes / No

b. Low Pressure Injection Yes / No

c. Core Flood Yes / No

d. Phase 2 Reactor Building Isolation Yes / No

4. What is the status of the plant

a. At power

b. Hot standby

c. Hot Shutdown

d. Cooling down

e. Reactor Pressure psig

f. Reactor Temperature *F l

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1004.1

-Revision 4 ATTACHMENT II

EMERGENCY 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 What are the approximate radiation and/or contamination levels If so, is the injured person (s) contaminated Yes / No mR/hr

' 2 DPM/100 cm

8. Are there excessive radiation levels and/or contamination levelsy Yes / No If.so, list below:

a) Radiation Levels; 2

b) Contamination Levels DPM/100 cm at location:

Date Time Completed By 1

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j ATTACHMENT II l

EMERGENCY STAT _US REPORT I

SECTION II Fill out if a release has occurred or is occurring. Provide BRP all available information for verification call.

1. What is the approximate radioactive source term discharge rate from the plant (As determined by the Projected Dose Calculation proce-dure (1004.7)).

a) Noble gases C1/sec b) Iodine Ci/sec

2. What is the approximate meteorology 1

a) Wind speed mph b) Wind direction c) Stability Class Stable / Neutral / Unstable

3. What is the projected whole body dose rate and iodine concentration at the nearest offsite downwind point a) mR/hr b) uCi/cc Iodine c) (Location)

4. Estimated duration of the release a) If the release is terminated:

Starttime Stop Time Duration a

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EMERGENCY STATUS REPORT SECTION II Start time Stop time Duration b) If the release is still in progress:

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Start time Estimated duration (hrs / min / sec)

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i :FOR: USE IN UNIT ! ONLY 1004.1 l Revision 5 ATTACHENT 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 Applicable Part of 10 CFR 50.72 B.

Description:

l Date of Event Time Description of What Happened ,

C. Consequences of Event: (Complete depending on type of event) l Injuries Fatalities 1

Contamination (personnel) (property)

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Overexposures (known/possible)

Safety Hazard (describe - actual / potential)

Offsite Radiation Levels .

Integrated Dose Location 1

Meterology (wind speed) From (direction)

Weather Conditions (rain, clear, overcast, temperature) i Equipment / Property Damage D. Cause of Event:

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FOR USE IN UNIT 1 ONLY 1o04,1 Revision 5 ATTACHENT III CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE 114 ACCORDANCE WITH 10 CFR 50.72 E. Licensee Actions:

Taken Planned Emergency Plan Activitated (Yes/No) Classification of Emergency 1 Resident Inspector Notified (Yes/No) State Notified (Yes/No)

Press Release Planned (Yes/No) News Media Interest {Yes/No)

Local / National F. Current Status: (Complete depending on type of event)

1. Reactor Systems Status Power Level Before Event After Event Pressure Temp. ( tnot) (t cold I RCS Flow (Yes/No) Pumps On (Yes/No)

Heat Sink: Condenser Steam Atm. Dump

. Other Sample Taken (Yes/No) Activity Level ECCS Operating (Yes/No) ECCS Operable (Yes/No)

, ESF Actuation (Yes/No)

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

S/G Levels Feedwater Source / Flow Containment Pressure Safety Relief Valve Actuation (Yes/No) 1 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 Powei Plants.

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ATTACHENT III O CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 Containment Water Level Indication Equipment Failures Normal Offsite Power Availabe (Yes/No)

Major Busses / Loads Lost Safeguards Busses Power Source i D/G Running (Yes/No) Loaded (Yes/No)

2. Radioactivity Release Liquid / Gas Location / Source Release Rate Duration O steppe 4 (vee /#e) aeieeee nee 4terea (ve><"e>

Amount of Release Tech Spec. Limits Radiation Levels in Plant Areas Evacuated

3. Security /Saf :iuards 2 Bomb Threat: Search Conducted (Yes/No) Search Results Site Evacuated (Yes/No)

Intrusion: Insider Outsider i Point of Intrusion Extend of Intrusion Apparent Purpose Strike / Demonstrations: Size of Group i Purpose l

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

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Revision 5 l O attaca=#' tit i

CHECKLIST FOR NOTIFICATIOil 0F SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 Sabatoge: Radiological (Yes/No) Arson (Yes/No)

Equipment / Property i Extortion: Source (phone, letter, etc.)

Location of Letter Demands General: Firearms involved (Yes/No) Violence (Yes/No)

Control of Facility Compromised or Threatened (Yes/No)

Stolen / Missing Material Agencies Notified (FBI, State Police, local Police, etc.)

O Media Interest (present, anticipated)

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IW ORTANT TO SAFETY NON-ENVIRONENTAL IMPACT RELATED CONTROLLED COPY FOR THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EERGENCY PLAN IMPLEENTING PROCEDURE 1004.3 SITE EERGENCY Table of Effective Pages -

Page Revision Page Revision Page Revision Page Revision 1.0 6 21.0 6 2.0 6 22.0 6 3.0 6 23.0 6 4.0 6 24.0 6 5.0 6 25.0 6 6.0 6 26.0 6 7.0 6 27.0 6 8.0 6 28.0 6 9.0 6 29.0 6 10.0 6 30.0 6 11.0 6 31.0 6 12.0 6 32.0 6 13.0 6 33.0 6 14.0 6 15.0 6 O 16.0 17.0 6

6 18.0 6 19.0 6 20.0 6 Unit 1 Staff Reconsnends Approval Approval Date Cognizant Dept. Head

Unit 1 PORC Recontr. ends Approval A # l' ) }1{ / Date//l2 /

i Chairman of PORC l

> Mana er TMI I Approval T/7 Y J Date //j' Lh/

l l' QA Modifications / Operations Mgr Date Document ID: 0025W l

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THREE MILE ISLAND NUCLEAR STATION UNIT N0.1 EERGENCY PLAN IMPLEMENTING PROCEDURE 1004.3 SITE EERGENCY 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 Station (Unit 1) and to:

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

b. Ensure necessary actions are taken to notify GPU Nuclear management and offsite emergency response organizations.

c. Mobilize the emergency response organizations to initiate appropriate emergency actions.

The Emergency Director is responsible for implementing this procedure.

NOTE: Emergency Director responsibilities that may NOT be :

delegated include: :

a. Decision to notify offsite emergency management :

agencies. :

, : b. Making protective action recommendations as :

necessary to offsite emergency management :

agencies. :

: c. Classification of Emergency Event. :

d. Determining the necessity for onsite evacuation. :

e. Authorization for emergency workers to exceed :

10CFR20 radiation exposure limits. :

2.0 ATTACHENTS 2.1 Attachment I, Site Emergency Notifications.

2.2 Attachment II, Emergency Status Report.

2.3 Attachment III, Checklist for Notification of Significant Events Made in Accordance with 10 CFR 50.72.

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FOR USE IN UNIT I ONLY 1004.3 Revision 6 3.0 EERGENCY ACTION LEVELS

INITIATING CONDITION INDICATION 3.1 Known loss of coolant accident As indicated by automatic ECCS greater than makeup capacity initiation due to both high leading to RCS saturation. containment pressure (4.0 psig) and low reactor 4

coolant pressure (1600 psig or reactor coolant system pressure / temperature curves or subcooling monitor

indicate saturation conditions.

3.2 Primary to Secondary leakage As indicated by makeup tank

~

> 50 gpm. level decreasing at 2 inches / minute or makeup flow exceeding letdown by 50 gpm in conjunction with RM-A5 high alarm (8000 cpm) or steam line monitor high alarm.*

3.3 Loss of all offsite power co- Continuation of condition in O incident with a loss of both Diesel Generators for more than Alert EAL-5 for more than 15 minutes.

15 minutes.

3.4 Loss of all vital onsite DC Continuation of condition in power for more than 15 minutes. Alert EAL-6 for more than 15 minutes.

3.5 Complete loss of any function As indicated by a complete needed for plant hot shutdown. loss of any of the following

a. All means to feed 0TSGs.

b. All means to control Reactor Coolant Pressure

c. Makeup pumps or makeup flow control.

d. Control Rods.

3.6 Major damage to spent fuel in Caused by either:

containment or fuel handling a. An object, weighing more bu'1 ding. than the Technical

, Specification Limiting Condition for Operation 3.11.6 limits, impacting on spent fuel.

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b. The water level in the

((l/ reactor vessel or spent fuel pool drops below the top of the spent fuel.

3.7 Fire compromising the functions As judged by the Shif t of any safety system. Supervisor.

3.8 Most or all Annunciators lost and As judged by the Shift plant transient initiated or in Supervisor.

progress which may involve actual or likely major failures of plant functions needed for protection of the public.

3.9 Actual or projected doses at the As indicated by:

Exclusion Area boundary greater a. Valid count rate of > 1.0 than 1/20 of the lower limit EPA x 105 cpm on the gas-Protective Action Guidelines but channel of RM-A8.*

less than 1/10 of the lower limit b. Valid count rate of > 3.0 EPA Protective Action Guidelines x 105 cpm on the gas-but less 1/10 of the icwer limit channel of RM.-A9.*

EPA Protective Action Guidelines. c. A valid count rate increase of > 4.5 x 103 cpm / min on tee iodine channel of RM-A8.*

Os d. A valid count rate increase of >1.2 x 104 cpm / min. on the iodine channel of RM-A9.*

e. Avalidgoserateof>-

2.8 x 10 mR/hr on RM-G8.

f. Offsite radiological monitoring reports or dose projections of > 50 mR/hr (gamma) but

<100mR/hr (gamma).

3.10 Imminent loss of control of Shift Supervisor's judgment, the physical security of the based on the advice of the plant. Security Duty Sergeant.

3.11 Severe natural phenomena being Plant is not in cold shutdown exparienced or projected with and any of the following plant not in cold shutdown. phenomenon are experienced or projected:

a. An earthquake of magnitude > 0.129 horizontal and/or > 0.089 vertical acceleratTon (Safe Shutdown Earthquake).

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

c. Sustained Hurricane winds or tornados > 75 mph as indicated on the Wind Speed Recorder (NDS-501) .

3.12 Other hazards being experienced Plant is not in cold shutdown or projected with the plant not and any of the following in cold shutdown. phenomenon are experienced or proj ected:

a. Aircraft crash which, in the judgment of the Shif t Supervisor affects vital structures by impact or fire.

b. Explosion or missile damage which, in the judgment of the Shift Supervisor, causes severe damage to safe shutdown equipment.

c. Entry of toxic or flammable gases into n

( ,/

vital areas which in the judgment of the Shift Supervisor, affects operation of safe shutdown equipment.

3.13 Evacuation of the Control Room Control Room is evacuated and where control of the shutdown control of all of the systems is not established following systems or equipment within 15 minutes. is not established within 15 minutes:

a. Emergency Feedwater System

b. Turbine Bypass Valves or Atmospheric Steam Dump Val ves.

c. Makeup Pumps.

d. Makeup Flow Control Valve.

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e. Letdown Flow Control.

3.14 Reactor Building pressure As indicated by Reactor

-> 30 psig. Building Spray initiation and on Reactor Building Pressure Indicator.

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d' FOR USE IN UNIT I ONLY 1004.3 Revision 6 3.15 Total reactor coolant activity As indicated by any of the

-> 300 uCi/ml. following:

a. RM-L1 (High) reading >6.66 x 103 cpm.

b. Low RM-Lg x 10 c(pm.) reading >3.81

c. As determined by sample and analysis.

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

3.17 Failure of any actuated Emergency Shift Supervisor judges that Core Cooling System (includes HPI, ECCS setpoint is exceeded but LPI and Core Flood) to start and ECCS has not initiated.

run following automatic system initiation such that the number of components available is below the minimum assumed for accident analysis.

3.18 Other plant conditions exist that Whenever plant conditions war-warrant activation of emergency rant it, as judged by the centers and monitoring teams or a Shif t Supervisor / Emergency O precautionary notification to the public near the site.

Director.

These indications may be detennined via instrumentation that will be installed 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 Superintendent shall assume the duties of the Emergency Director. (Event should be assessed and declared within 10 minutes of the occurrence).

4.2 Announce to Control Room personnel that has (name) assumed the duties of Emergency Director.

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

NOTE: Turn on Whelen siren switch. :

ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: A SITE EMERGENCY HAS BEEN DECLARED IN UNIT I. ALL NON-ESSENTIAL PERSONNEL IN UNIT I REPORT TO UNIT I WAREHOUSE. ALL NON-ESSENTIAL PERSONNEL IN THE UNIT II AREA REPORT TO THE UNIT II WAREHOUSE . ALL PERSONNEL IN H.P. CONTROLLED AREAS PROCEED TO THE H.P. ACCESS CONTROL POINTS. ALL MEMBERS OF THE EMERGENCY ORGANIZATION REPORT TO YOUR STATIONS. THERE WILL BE NO SM0 KING, DRINKING OR EATING UNTIL FURTHER NOTICE. (Repeat message slowly) .

M .4 If emergency is radiation-oriented, direct that the Radiation Emergency Alarm be sounded.

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

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

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

4.7 Contact the Duty Section Superintendent and discuss Plant i

l Status and that the onsite and offsite Duty Section personnel i

are being called.

4.8 Depending on the emergency action level which was reached or l exceeded, ensure that the appropriate Emergency Operating Procedures have been implemented.

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FOR USE IN UNIT I ONLY 1004.3 Revision 6 4.9 If local services (fire, ambulance, police) are required, direct the Communicator 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 / Ambulance) . Security should be advised to implement EPIP 1004.19, Emergency Security / Dosimetry Badge Issuance.

NOTE: If the Emergency Response Personnel are required to :

respond outside the Protected Area affected by a :

radioactive plume, the Emergency Director or his :

designee will direct the issuance of TLD's from the :

North or South Gate. :

_ 4.10 If changes in onsite or offsite radiation levels are expected, direct the Radiological Assessment Coordinator:

a. Dispatch offsite and/or onsite radiation monitoring teams in accordance with EPIP's 1004.10 and 1004.11 and send a monitor to the Emergency Assembly Areas.

b. Implement offsite dose projections procedure (1004.7).

4.11 Activate the Technical Support Center (1004.28) and the Operations Support Center (1004.29).

4.12 If additional resources or notifications are required, refer j to gdditional Assistance and Notifications procedurd (1004.6). l 4.13 If the emergency involves in-plant health physics problems, l

direct the Radiological Assessment Coordinator to implement jn CN glant Radiological Controls During Emergencies procedure l

(1004.9).

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FOR USE lN UNIT I ONLY 1004.3 Revision 6 4.14 Assign an individual to complete Attachment II,Section I and give it to the Radiological Assessment Coordinator to transmit to the Bureau of Radiation Protection.

4.15 Direct the Radiological Assessment Coordinator to complete Attachment II,Section II to transmit to the Bureau of Radiation Protection if a radioactive release has occurred or is occurring.

4.16 Stop all liquid and gaseous discharges that are in progress until an assessment of their impact is performed and specific approval is given to continue the release by the Emergency Di rector.

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

A U 4.18 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.

4.19 After 30 minutes confirm that BRP verification has been made.

If no verification, instruct the communicator to proceed to Attachment I, Section 1, 2.(e) .

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

4.21 If a repSrt of the accountability has not been received within 30 minutes from the time it was ordered, contact the Security Coordinator at 8038, 8039, 8040 for a status report.

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FOR USE IN UNIT I ONLY 1004.3 Revision 6 4.22 If personnel are unaccounted for, initiate Search and Rescue procedure (1004.18).

4.23 Upon completion of a muster at the warehouse, an orderly evacuation by private vehicle shall be ordered by the following message over the public I:ddress system (merged):

NOTE: Turn on Whelen siren switch. :

ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: ALL NON-ESSENTIAL PERSONNEL IN UNITS I AND II PROCEED TO THE (MIDDLETOWN SUBSTATION /500 KV SUBSTATION) USING THE NORTH / SOUTH GATE. (DEPENDING ON PLUE PATHWAY). UPON ARRIVAL, ALL SUPERVISORS WILL ASSEMBLE AND LOG IN THEIR PERSONNEL AND PROVIDE FURTHER INSTRUCTIONS. (Repeat message slowly) .

NOTE: Turn off Whelen siren switch. :

4.24 Evaluate dose projections and estimates and, if necessary, recommend protective actions to the BRP consistent with the guidelines in Attachment I,Section IV.

4.25 Based upon assessment of plant conditior.s, the Emergency Director shall either close out the Site Emergency, escalate to a General Emergency or downgrade to a lower class as follows:

a. If Recovery Phase criteria have been met (see Recovery Procedure (1004.24), close out the Site Emergency by perfonning the notifications in Attachment I,Section III . Implement the Recovery Procedure (1004.24).

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b. If Recovery Phase criteria have not been met, but 9

Site Emergency action levels are no longer exceeded, de-escalate to a lower emergency class by notifying BRP on the Radiological Line and perfonsing the

, remaining n:t'fications in accordance with the applicable emergency procedure as specified in Step 5.2.

c. If emergency action levels exceed those for a Site .

Emergency, escalate to a General Emergency, notify BRP on the Radiological Line and make the remaining notifications in accordance with the General Emergency procedure (1004.4).

4.26 If necessary, due to potential contamination of normally non-contaminated sumps and/or tanks, or the need to closely 1

monitor liquid releases, initiate procedure 1004.14, Monitoring / Controlling Liquid Discharges.

5.0 FINAL CONDITIONS 5.1 A higher class of emergency has been declared by the Emergency Director and the General Emergency procedure (1004.4) is being i

implemented, or 5.2 A lower class of emergency has been declared by. the Emergency i

Director and one of the following procedures is being implemented:

! a. Unusual Event (1004.1)

b. Alert (1004.2)

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FOR USE IN UNIT l ONLY 1004.3 Revision 6 5.3 The Site Emergency has been closed out with the concurrence of the Emergency Support Director, since no recovery operations are required, or 5.4 The Site Emergency can be shifted to a recovery mode by implementing procedure 1004.24.

Date Signature of Person Responsible for Implementing Procedure O

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FDR USE IN UNIT I ONLY 1004.3 Revision 6 ATTACHENT I SECTION I INITIAL CONTACT INITIALS The Communicator shall notify the following agencies and personnel and update the Attachment I,Section II checklist af ter each notification.

1. Dauphin County Emergency Operation Center (If this is a reclassification notification, first notify BRP then on the radiological line go to Item 3, unaffected Control Room).

a. Telephone: 9-911 or 9-236-7976 (1) If no contact, activate Dauphin County radio system.

b. This is at the Three Mile (name/ title)

Island Nuclear Station Unit I calling. We have declared a Site Emergency at hours. (Based upon Emergency Qp (time)

Director judgment, deliver one of the following statements):

(1) We have not had a radioactive release, but do not expect this situation to result in detectable changes in offsite radiation levels, OR (2) We have had a radioactive release, but do not expect this situation to result in in detectable changes in offsite radiation levels, OR i

(3) We have had a radioactive release, but do not know if

there will be a detectable change in offsite radiation levels. We will be keeping the Bureau of Radiatior:

Protection informed of the results of our investigation, OR O

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ATTACHENT I SECTION I i INITIAL CONTACT INITIAL (4) We have had a radioactive release and expect to be able '

l i to detect changes in offsite radiation levels, but they 1

will be less than the levels calling for a General

. Emergency.

We will be keeping the Bureau of Radiation Protection informed.

(Give a short non-technical description of the emergency and the extent of radioactive release including i potentially af'ected populations and areas).

O

2. Pennsylvania Emergency Management Agency (PEMA) 1 (If this is a reclassification notification, go to Item 3, unaffected Control Room). >

4

NOTE: When protective actions are to be recommended, the :

Emergency Director should refer to the contents of :

i : Attachment I,Section IV. :

l l a. Telephone: 9-783-8150 l (A diverter furwards this call to PEMA duty officer after 1-l working hours).

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

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b. MESSAGE:

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

Nuclear Station Unit I calling. We have an emergency. Give me the Operations Duty Officer. (When Duty Officer answers):

This is at the Three Mile Island (name/ti tle)

Ncclear Station Unit I calling. We have declared a Site Emergency at hours. We request that you contact (time) the Bureau of Radiation Protection. Bureau of Radiation Protection call back should be made on the Radiological Line or 948-8069, 948-8071 or 944-0839. (Based on Emergency Director's judgement, deliver one 'i the following statements).

(1) We have not had a radioactive release, OR (2) We have had a radicactive release, but do not expect this situation 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 informed of the results of our investigation, OR 14.0 F.OR:USE IN UNIT l'ONLY

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'FOR USE IN UNIT l ONLY 100,,3 Revision 6 ATTACHENT I SECTION I INITIAL CONTACT INITIAL (4) We have had a radioactive release and expect to be able to detect changes in offsite radiation levels, but they will be less than the levels calling for a General Emergency. We will be keeping the Bureau of Radiation Protection informed.

c. Give a short non-technical description of the emergency and, if applicable, af ter release, state the direction of the projected plume pathway and potentially affected populations.

d. If PEMA was unable to be contacted, contact Dauphin County; advise them that PEMA cannot be contacted and direct them to notify PEMA, BRP, and Lancaster, York, Lebanon and Cumberland counties.

e. Message verification:

Expect Bureau of Radiation Protection (BRP) contact after PEMA notification. If no BRP confirmation is received within 30 minutes, notify PEMA of the situation. If unable to contact PEMA (line busy), call Dauphin County and notify them that BRP has not verified initial contact. Request Dauphin County to contact PEMA and BRP.

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T .FOR ~USE IN UNIT 1 ONLY 1004,3 Revision 6 q ATTACHENT I SECTION I V

INITIAL CONTACT INITIAL

3. Unaffected Control Room

a. Telephone: 8066, 8067, 8068 or inter Control Room hotline.

b. ESSAGE: Give a brief description of plant status to Shif t Supervisor.

4. Institute of Nuclear Power Operations '

(Do not notify if this is a reclassification notification).

a. Telephone: 404-953-0904

b. ESSAGE:

This is at Three Mile Island Nuclear

( name/ti tle) g Station Unit I calling. We have declared a Site Emergency l at hours. (Give a brief description of (time) the emergency).

5. Babcock and Wilcox 1-804-384-3413

(

This is at Three Mile Island

( name/ti tle)

Nuclear Station Unit I calling. We have declared a Site Emergency i

at hours. (Have a prepared Attachment II

( name/ti tle) available for reference while giving a brief description of the emergency).

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NOTE: From 0900 to 1700 Monday thru Friday the B and W :

trunk of the Operations Line may be used. (See :

Communications Plan). :

6. American Nuclear Insurers _ 74-1-203-677 7305 or 9-1-800-243-3172/3173 (af ter normal working hours)

ESSAGE:

This is at Three Mile Island Nuclear

( name/ ti tle Station Unit I calling. We have declared a Site Emergency at hours. (Give a brief description of the

( time)

O emergency).

V We had a radioactive release.

(have/have not)

7. If the 'ite Emergency involves radiation releases, notify the following agencies:

I

! a. Radiation Management Corporation 73-1-215-243-2950 Emergency Number 73-1-215-841-5141 O

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FOR USE IN UNIT I ONLY 1,0,,3 i Revision 6 ATTACHENT I SECTION I INITIAL CONTACT INITIAL MESSAGE:

This is at the Three Mile Island Nuclear

. ( name/ title)

Station Unit I calling. We have declared a Site Emergency at hours. (Give a brief description of the

( time) emergency).

O We have had a radioactive release.

We require assistance at this time.

(do/do not)

(Describe the assistance required, if any).

8. If police or medical assistance is required, notify the following l

agencies:

a. Hershey Medical Center 534-8333

b. Pennsylvania State Police 234-4051 l

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l a FOR-USE IN UNIT I ONLY

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l Revision 6 ATTACHENT I SECTION I INITIAL CONTACT INITIAL ESSAGE:

This is at the Three Mile Island

( name/ ti tle)

Nuclear Station Unit I calling. We have declared a Site Emergency at hours. We (time) (have/have/not) had a radioactive release. We requirt assistance as follows:

(State any assistance required) .

9. Nuclear Regulatory Commission (NRC) - Bethesda, K)

(Comminications with the NRC will be continuously maintained following contact).

a. Telephone: NRC Emergency Notification System (ENS)

(RED PHONE)

b. ESSAGE:

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

Nuclear Station Unit I calling. We have declared a Site l

Emergency at hours. (Based upon Emergency

( time)

Director's judgment, use one of the following statements):

(1) We have not had a radioactive release, OR l

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U I 1

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FOR USE IN UNIT I ONLY 1004.3 Revision 6 ATTACHENT 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, but do not know if there will be a detectable change in offsite radiation level s. We will be keeping the Bureau of Radiation Protection informed of the results of our investigation.

(4) We .iave had a radioactive release and expect to be able to detect changes in offsite radiation levels, but they will be less than the levels calling for a General l Emergency. We expect the levels to be < 100 mrem per hour (gamma). We will be keeping the Bureau of Radiation Protection informcd. (Give a short non-technical description of the emergency and the extent of the radioactive release, including affected populations and areas).

i

Date Time Completed Completed By O

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NOTE: After initial NRC notification is complete per :

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

: Notification Checklist, Attachment III. This :

: Checklist contains information desired by the NRC :

i : and may be helpful in providing follow-up :

, : information. :

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NOTIFICATION CHECKLIST

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,:: EVENT : ALERT : EMERGENCY : EMERGENCY:: EVENT : ALERT : EMERGENCY : EMERGENCY :

i. : AGENCY 7-

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Dauphin County

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Ig :: : : : :: : : : :

d' @ : PEMA 'J N s , :: : : : :: : : : : 2 m : .

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State Police :: *: *: *: :: : : : :

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RMC *: *: *: * :: : : : :

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ANI :: *: *: : :: : : : :

r- : : : :

B and W :: N/A : N/A : : ::

4 : :: : : : :: : : : :

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

Optional i

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FOlR USE IN UNIT I ONLY 1004.3 Revision 6 ATTACHENT I SECTION III SECONDARY CONTACT INITIAL.

The Communicator shall notify the frilowing agencies and personnel and update the' Attachment I,Section II checklist af ter each notification.

1. Bureau of Radiation Protection

a. Telephone: Radiological Line

b. ESSAGE:

This is at the Three Mile Island (name/ title

) ,

,' Nuclear Station Unit I calling. We have closed out the Site Emergency at hours and initiated recovery operations.

(time)

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

2. Unaffected . Control Room

a. Telephone: 8066, 8067 8068 L b. MESSAGE:

Il This is , at the Three Mile Island (name/ ti tie)

Nucl'e ar Station Unit I calling. We have closed out the Site e Es:ergency at hours and initiated recovery operations.

(time)

4. If applict ' ' , notify the following persons and/or agencies of close t

out of the Site Emergency:

a' .' Hershey Medical Center:

a, 3 9-534-8333

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FOR USE IN UNIT I ONLY 1,, ,3 Revision 6 ATTACHENT I SECTION III SECONDARY CONTACT INITIAL

b. Pennsylvania State Police: 9-234-4051

c. Radiation Management Corp.: 73-1-215-243-2950 (RMC) OR 73-1-215-243-2990 l d. American Nuclear Insurers: 74-1-203-677-7305 i

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e. Babcock and Wilcox: 74-1-804-384-3413 F. Othen - as directed by the Emergency Director.

Date Time Completed Completed By

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1004.3 Revision 6 ATTACHENT I SECTION IV PROTECTIVE ACTION RECOMENDATION GUIDELINES THESE RECOMENDATIONS MAY BE DELIVERED ONLY BY THE EERGENCY DIRECTOR

1. Consideration shall be given to sheltering if:

i a. Release time is expected to be short (Puff release, < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

(AND)

b. Evacuation could not be well underway prior to expected plume arrival due to short warning time, high wind speeds, and/or foul weather.

2. Consideration shall be given to evacuation if:

a. A release is expected to occur with projected doses approaching or exceeding:

1 Rcm Whole Body and/or 5 Rem Child Thyroid t

(AND)

b. Release time is expected to be long (> 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months )

(AND)

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

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FOR USE IN UNIT I ONLY 1004.3 Revision 6

(~') ATTACHENT II SECTION I

'w/

EFERGENCY STATUS REPORT

1. Description of Emergency:

2. Has the Reactor tripped Yes / No

3. Did the Emergency Safeguards Systems actuate Yes / No If so, which ones (a) High Pressure Injection Yes / No

,o

( ,)

(b) Low Pressure Injection Yes / No (c) Core Flood Yes / No (d) 4 No. Reactor Building Isolation Yes / No (e) Reactor Building Cooling Yes / No

4. What is the status of the plant (a) At power (b) Hot Standby (c) Hot Shutdown (d) Cooling down (e) Reactor Pressure _ __ psig (f) Reactor Temperature *F

5. Is offsite power available Yes / No o

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FOR USE IN UNIT I ONLY 1004.3 Revision 6 ATTACHENT II SECTION I EERGENCY 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 Yes / No (1) What are the approximate radiation and and/or contamination levels mR/hr 2

DPM/100 cm

8. Are there excessive radiation levels and/or contamination levels. Yes / No (a) If so, list below:

(1) Radiation levels (Whole Body)

(2) Contamination levels DPM/100 cm at Location:

Date Time Completed By n

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LFOR USE IN UNIT l'ONLY 1004.3 Revision 6 ATTACHMENT II SECTION II EERGENCY STATUS REPORT Fill out if a release has (is) occurring. Provide BRP all available information for verification call.

1. What is the approximate radioactive source term discharge rate from the plant (As determined by the Projected Dose Calculation Procedure (1004.7).

(a) Noble gases Ci/sec (b) Iodine Ci/sec

2. What is the approximate meteorology (a) Wind speed mph (b) Wind direction (c) Stability Class-Stable / Neutral / Unstable

3. What is the projected whole body dose rate and fodine concentration at the nearest offsite downwind point (a) mR/hr (b) uCi/cc Iodine (c) (Location)

4. Estimated duration 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)

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EERGENCY STATUS REPORT

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 Protective Action Guides be exceeded (i.e.,1 Rem Whole Body, S F.em Child Thyroid)/

Yes/No

b. If yes, estimate time to exceeding PAG:

hours and projected whole body dose Rem and child thyroid dose Rem.

O Date Time Completed Completed By 4

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FOR'USE INiUNIT I ONLY 1004.3 Revision 6 ATTACHENT 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 Applicable Part of 10 CFR 50.72 B.

Description:

Date of Event Time Description of What Happened C. Consequences of Event: (Complete depending on type of event)

Injuries Fatalities Contamination (personnel) (property)

Overexposures (known/possible)

Safety Hazard (describe - actual /pov ntial)

Offsite Radiation Levels Integrated Dose Location Meterology (wind speed) From (direction)

Weather Conditions (rain, clear, overcast, temperature)

Equipment / Property Damage D. Cause of Event:

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FOR USE IN UNIT 1 ONLY 1004.3 Revision 6 hb ATTACHENT 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) Classification of Emergency 1 Resident Inspector Notified (Yes/No) State Notified (Yes/No)

Press Release Planned (Yes/No) News Media Interest (Yes/No)

Local / National F. Current Status: (Complete depending on type of event)

1. Reactor Systems Status Power Level Before Event After Event Pressure Temp. ( thot) (t cold I RCS Flow (Yes/No) Pumps On (Yes/No)

Heat Sink: Condenser Steam Atm. Dump Other Sample Taken (Yes/No) Activity Level ECCS Operating (Yes/No) ECCS Operable (Yes/No)

ESF Actuation (Yes/No)

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

S/G Levels Feedwater Source / Flow Containment Pressure Safety Relief Valve Actuaticn (Yes/No) 1 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.

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CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS W.DE IN ACCORDANCE WITH 10 CFR 50.72 Containment Water Level Indication Equipment Failures Normal Offsite Power Availabe (Yes/No)

Major Busses / Loads Lost Safeguards Busses Power Source D/G Running (Yes/No) Loaded (Yes/No)

2. Radioactivity Release Liquid / Gas Location / Source Release Rate Duration Stopped (Yes/No) Release Monitored (Yes/No)

Amount of Release Tech Spec. Limits Radiation Levels in Plant Areas Evacuated

3. Security / Safeguards 2 Bomb Threat: Search Conducted (Yes/No) 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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1004.3 Revision 6 i

ATTACHENT 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: Firearms involved (Yes/No) Violence (Yes/No)

Control of Facility Compromised or Tnreatened (Yes/No)

Stolen / Missing Material Agencies Notified (FBI, State Police, Local Police, etc.)

Media Interest (present, anticipated)

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FOR USE IN UNIT I ONLY 1004.5 Revision 1 11/13/81 0 IMPORTANT TO SAFETY NON-ENVIRONENTAL IMPACT RELATED CONTROLLED COPY FO USE IN UNIT 1 CNLY THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IPPLEMENTING PROCEDURE 1004.5

. COMMUNICATIONS AND RECORDKEEPING Table 'of ' Effective Pages Page Revision Page Revision Page Revision Page Revision 1.0 1 2.0 1 3.0 1 4.0 1 5.0 1 6.0 1 7.0 1 8.0 1 9.0 1 10.0 1 11.0 1 12.0 1 13.0 1 14.0 1 15.0 0 16.0 1

1 Unit 1 Staff Recommends Approval Approval -

M/ Date Cognizant Dept. Head Unit 1 PORC Recommends Approval P f (l PK' Date ////E ll Chairman of PORC Mana er TMI I Ap rov 1

/ W Date // Bfff f/

V QA Modifications / Operations Mgr

// Date Docur,ent ID: 0011W FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.5 Revision 1 THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IW LEMENTING PROCEDURE 1004.5 COMMUNICATIONS AND RECORDKEEPING 1.0 PURPOSE The purpose of this procedure is to 1) provide a list of all logs to be taken and records to be kept, and 2) delineate when each log and record should be maintained.

This procedure is implemented when referenced by any Emergency Plan Implementing Procedure. Facility coordinators shall assign individuals responsible for implementation of this procedure.

2.0 ATTACHENTS 2.1 Attachment I, Emergency Director's Log i

2.2 Attachment I'I, Telephone Communications Logsheet 2.3 Attachment III, Master Log to be completed by the appropriate persons (Group' Leaders, Chemistry, Health Physics, Administration, Security Support, etc., see above responsibility for implementa-ti on) .

3.0 EERGENCY ACTION LEVELS, 3.1 This procedure to be initiated upon declaration of any of the l following:

I 3.1.1 Unusual Event (1004.1) l 3.1.2 Alert (1004.2) l 3.1.3 Site Emergency (1004.3) i

! 3.1.4 General Emergency (1004.4)

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'FOR USE IN UNIT l ONLY 1004.5 Revision 1 Initial 4.0 REQUIREENTS 4.1 Comunications 4.1.1 All significant communications (i.e., Notifications, Protective Action Recommendations, Requests for outside assistance, etc.) should be documented on a telephone communications log sheet. (Attachment II).

4.1.2 Other communications should be documented on the Logs maintained by key personnel as noted in Step 4.2.

4.2 Record Keeping Ensure the Logs and Records are used as foilows:

4.2.1 Emergency Director's Log

1) When conditions permit, the Emergency Director's Log (Attachment I) should be started shortly after an emergency is declared, and maintained by the Emergency Director, or his designated Logkeeper, until the emergency is closed-out by the Emergency Director.

2) The following is a list that is indicative of the type of information that should be con-sidered for documentation in this Log:

a) Time, shift, date the emergency is de-clared.

b) Names of personnel assuming key positions in the emergency organization.

c) Plant status at the time of the declara-tion of the emergency.

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< p h Initial d) Major steps taken during the emergency (i .e., alarms sounded, procedures imple-mented, major equipment status changes, etc.)

e) Important data received (i.e. cajor plant parameters pertaining to the Emergency, etc.).

f) Recommendations given to or received from Off-Site agencies, not recorded by com-munications assistant, (i .e., the NRC, Pennsylvania Bureau of Radiation Protec-tion, Dauphin County Emergency Management Agency, etc.).

. g) Final notifications of Off-Site agencies upon close-out of the emergency or change of emergency classification by the Emer-gency Director.

4.2.2 Radiological Assessment Coordinator's Log

1) Conditions Pennitting, this Log (Attach-ment III) should be started shortly after the duties and responsibilities of the Radiological Assessment Coordinator are assumed, and main-tained by the Radiological Assessment Coordina-tor, or his designated Log-keeper, until the l emergency is closed-out by the Emergency Director.

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2) Items for consideration in this Log are as follows:

a) Time responsibilities are assumed.

b) Names of personnel filling key positions under the Radiological Assessment Coordinator.

c) Results from radiation surveys.

d) Results from dose projections and release calculations, etc.

i e) Reconnendations to or from the Bureau of Radiation Protection.

f) Transfer of responsibility for control of Off-Site Radiological and Environmental Moni-toring to the Environmental Assessment Coordi-nator at the Environmental Assessment Command Center.

l g) Time of close-out of the emergency, as directed

by the Emergency Director.

4.2.3 Operations Support Center Coordinator's Log

1) Conditions Pennitting, this Log (Attachment III) should be started shortly af ter the duties and responsibilities of the Operations Support Center Coordinator are assumed, and maintained by the Operations Support Center Coordinator or his designated Logkeeper, until the emergency is closed-out by the Emergency Director.

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2) Items for consideration in this Log are as follows:

a) Time, shift, and date duties are assumed.

b) Names of personnel assuming key positions in the emergency support organization.

c) Significant uents that occur or important data /information recieved.

d) Recommendations exchanged with other affected agencies.

e) Any teams (Search and Rescue, onsite/

offsite radiation monitoring) assembled and dispatched, the names of the team leaders, and the purpose of team dispatch.

4.2.4 Emergency Support Director

1) Emergency Support Director's Log a) Conditions permitting, this Log (Attach-ment III) should be started shortly after the duties and responsibilities of the Emergency Support Director are assumed, and maintained by the Emergency Support Director, or his designated Logkeeper, until the emergency is closed-out by the Emergency Director.

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\ Initial b) Items for consideration in the Log are as follows:

1) Time responsibilities are assumed. -

2) Names of personnel assuming key positions in the Off-Site Emergency Organizatior..

3) Significant events that occur or important data received, (i.e.,

radiation survey results, major plant parameters pertaining to the emer-gency, etc.).

4) Major steps taken during the emer-gency (i.e. procedures implemented, organization changes /re-locations due 4

to special considerations, etc.).

{ 5) Recommendations given to or received 1

from Off-Site agencies (i.e. the NRC, Pennsylvania Bureau of Radiation Protection, Dauphin County Emergency Management Agency, etc.).

6) Time of close-out er re-classifica-

, tion of the emergency as directed by the Emergency Director.

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.O k.) Initial

2) Technical Support Representative Log a) Conditions permitting, this Log ( Attachment III) should be started shortly after the duties and responsibilities of the Technical Support Representative are assumed.

b) Items for consideration in the Log are as follows:

1) Time duties are assumed.

2) Names of personnel on support staff.

3) Significant events that occur or infonna-tion pertaining to recommendations or observations made (i .e., time, recommenda-k) tion / observation, to whom, etc.).

4) Information transferred from Parsippany technical functions

5) Time of the close-out or re-classification of the emergency, as directed by the Emergency Director.

3) Group Leader - Chemistry Support Log a) Conditions permitting, this Log (Attachment III) should be started shortly after the duties and responsibilities of the Group Leader -

Chemistry Support are assumed.

(~'T V

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FOR USE IN UNIT I ONLY 1004.5 Revision 1 Ini tial b) Items for consideration in the Log are as follows:

1) Time duties are assumed.

2) Names of personnel on support staff.

3) Significant events that occur or infonna-tion pertaining-to recommer.dations or observation made (i .e., time, recommenda-tion / observation, to whom, etc.).

4) Time of close-out or re-classification of the emergency as directed by the Emergency Director.

1

4) Assistant Environmental Assessment Coordinator Log

'a) Conditions permitting, this Log (Attachment-III) should be started shortly after the duties and the responsibilities of the Assistant Environmental Assessment Coordinator are assumed.

b) Items for Consideration in this Log are as follows:

1) Time responsibilities are assumed.

2) Names of personnel filling key positions under the Environmental Assessment Co-ordinator.

3) Results from environmental, radiological, and meteorological surveys.

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4) Any teams (Environmental, Offsite, Meteor-ological, Monitoring) assembled and dispatched, their purpose and names of team leaders.

5) Recommendations to or from the Radio-logical Assessment Coordinator.

6) Time of announcement of assumption of responsibility for receipt of all offsite radiological and environmental monitoring data.

7) Time of notification to the Radiological Assessment Coordinator (via dedicated I Line) of assumption of responsibilities for offsite monitoring.

8) Time of close-out of the emergency as directed by the Emergency Director.

4.f .5 The following Logs should be kept by key personnel at the Alternate Near-Site Emergency Operations Facility.

(Crawford Station)

1) Group Leader - Security Support Log a) Conditions permitting, this Log (Attach-ment III) should be started shortly af ter the duties and responsibilities of the Group Leader - Security Support are assumed.

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- Initial b) Items for consideration in this Log are as 1

follows:

1) Time duties are assumed.

2) Location duties are performed- .

3) Any changes in location due to special considerations, etc. !

4) Any special orders received and person issuing these orders.

2) Group Leader - Radiological Controls Support Log a) Conditions permitting, this Log (Attach-

! ment III) should be started shortly after the duties and responsibilities of the

} Group Leader - Radiological Controls Support are assumed.

b) Items for consideration in this Log are as follows

1) Time duties are assumed.

2) Names of personnel filling key positions under the Group Leader -

Radiological Controls.

, 3) Important data received (i.e. results from radiation and contamination surveys, contaminated personnel, j etc.).

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4) Locations of monitoring / sampling stations and any subsequent reloca-tion for special considerations, etc.

5) Time of close-out or reclassification or the emergency, as directed by the Emergency Director.

3) Group Leader - Administrative Support a) Conditions permitting, this Log (Attach-ment III) should be started shortly after the duties and responsibilities of the '

Group Leader - Administrative Support are assumed.

b) Items for considerarion is this Log are as follows:

1) Time duties are assumed.

2) Names of personnel filling key positions under Group Leader Admini-strative Support.

3) Offsite services contacted and expected time of arrival of support.

4) If applicable, time of notification of local and state police.

5) Time of close-out or reclassification of the emergency as directed by the Emergency Director.

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4) Group Leader - Maintenance Support Log a) Conditions pennitting, this Log (Attach-ment III) should be started shortly after the duties and responsibilities of the Group Leade" - Maintenance Support are assumed.

b) Items for consideration in thes Log are as follows:

1) Time duties are assumed.

2) Names of personnel filling key positions under the Group Leader -

Maintenance Support.

O)

( 3) Time of the close-out or reclassifi-cation of the emergency as directed by the Emergency Director.

4.2.6 The following Log should be kept by the Environmental Assessment Coordinator at the Environmental Assessment i

l Congnand Center.

I

1) Environmental Asssessment Coordinator's Log Conditions permitting, this Log (Attachment III) should t,e started shortly af ter activation l of the Environmental Assessment Command Center

and maintained by the Environmental Assessment i

Coordinator, or his designated Logkeeper, until l the emergency is closed-out by the Emergency j'h

(,) Director.

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2) Items for consideration in this Log are as follows:

a) Time duties are assumeri.

b) Names of personnel filling key positions under Environmental Assessment Coordinator.

c) Important data received (i.e. results from radiation and contamination surveys, contami-nated personnel, etc.).

d) Time of assumption of offsite monitoring responsibilities.

e) Results from environmental, radiological, and !

meteorological surveys.

f) Any teams assembled and dispatched, their purpose and names of team leaders.

g) Recommendations to or from the Radiological Assessment Coordinator.

h) Time of close-out or reclassification of emergency.

5.0 FINAL CONDITIONS 5.1 Communication Lines are establised and being maintained as i

required.

5.2 Logs are started and maintained as required.

f l

5.3 Completed Logs are forwarded to the Shift Supervisor / Emergency l Director.

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) Time "$$N'[j or***"****

^pa-stions Coordinator

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- - # i TELEPIIONE C0}CIUNICATIONS LOGSliEET ,

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tg OUTGOING ' Phone Circuit Used:

DATE: TIME: _ INCOMING TO: FROM: ,.

Message: , ,

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DATE: TM: _ INCOMING OUTGOING Phone' ircuit used: '

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DATE:

TO: FROM:

Message:

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' THREE MILE ISLAND NUCLEAR STATION

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' InQ&7QS&dN UNIT I ONLY 1004.10 NON-ENVIRONMENTAL IMPACT'RELATED

]< Revision 2 11/13/81 O THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EFERGENCY PLAN IMPLEMENTING PROCEDURE 1004-10 CONTROLLED COPY FOR ONSITE RADIOLOGICAL MONITORING USE IN UNIT I ONLY.

, Table of Effective Pages (, y /b NC ,

Page Revision Page Revision Pg Revision Page Revision 1.0 1 2.0 2 3.0 2 4.0 2 5.0' '2 6.0 1

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s Unit 1 Staff Recomends Approval Approval Date ,

Cognizant Dept. Eead i Unit 1 PORC Recommends Approval P / UIL- Date // Z 'l Chainnan of PORC Manager TMI I Approv 1 W ,, %/ Date #

3 /

y QA Modifications / Operations Mgr c llh Date Document ID: 0022W '

FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.10 Revision 1 O THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.10 ONSITE RADIOLOGICAL MONITORING 1.0 PURPOSE The purpose of this procedure is to prov4.ie guidance to radiation monitoring teams for adequate onsite monitorino of radiation levels, following the accidental release of radioactive materials to the environment. The precedure establishes monitoring team actions to be perfomed to supplement nomal Health Physics procedures. The Radiation Monitoring Team is responsible for implementing this procedure.

2.0 ATTACHMENTS 2.1 Attachment I, Radiation Survey Log 2.2 Attachment II, Dosimeter Log 3.0 EMERGENCY ACTION LEVELS 3.1 This procedure is to be initiated upon any of the following conditions:

a) Alert (as detemined by Alert procedure 1004.2) b) Site Emargency (as detemined by Site Emergency Procedure 1004.3) c) General Emergency (as detemined by General Emergency Procedure 1004.4) d) As directed by the Emergency Director.

b i o

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I FOR USE IN UNIT I ONLY 1004.10 Revision 2 4.0 EERGENCY ACTIONS INITIALS 4.1 Proceed to the Processing Center and obtain an emergency kit, instrument kit, portable radio, and pager.

4.2 Verify seals on the emergency kit and then operationally check radiation meters. (Battery Check, Visual Inspection) 4.3 If seals are broken, conduct a brief inventory of equipment.

4.4 Prior to leaving the Processing Center, ;onduct a radio check with the Radiological Assessment Coordinator (RAC) in the Control Room using channel 3. Inform the RAC of your telephone pager nu.aber.

4.5 Obtain a designated emergency vehicle at the Processing Center.

4.6 Ensure your dose rate meter is turned on from the time you leave the Processing Center.

4.7 Proceed to the designated onsite monitoring location as directed by the RAC. (See onsite arp in emergency kit for specifically designated monitoring point locations.)

4.8 Perform radiological surveys (as directed by the RAC).

4.8.1 To perform dose rate surveys with the R0-2(A):

First take an open window reading at waist level, then take a closed window reading at waist level. Enter these readings and duration of meter readings on the Attachment I. Calcula+e true Beta dose rate and enter this on Attachment I. Report closed window reading and true Beta dose rate to the RAC.

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1004.10 Revision 2

. 4.8.2 Perfom contamination surveys if directed by the RAC as

follows

Obtain smears and coin envelopes from emergency kit, label envelope with date, time and location. Wipe the smear over a 100 cm (4 in. x 4 in.) area. Count the smear with RM-14/HP210 if available and background is less than 300 CPM. If background is toa high, move to an area of acceptable background in order to count smears.

Enter gross CPM and BKG CPM on Attachment I. Subtract

, background from gross CPM to obtain net CPM. Report net CPM for each smear to the RAC. Save smears in coin envelopes for later analysis as directed by the RAC.

4.8.3 Perfom air samples in accordar.ce with Airborne Radioactivity Sampling and Analysis, Procedure 1004.31. ,

4.9 Call in sampling results to the RAC and await further

)

i instruc tions.

4.10 If radio communications are lost and the pager is activated, attempt to re-establish radio communications with the RAC. If radio communications cannot be re-established, drive to the nearest phone and contact the RAC at Ext. 8069, 8070, or 8071.

4.11 Minimize personnel exposuras by moving out of areas of high radiation when recording data or awaiting further instructions by the RAC.

4.12 Ensure all team members keep track of their exposure on Attachment II .

3.0 FOR USE IN UNIT I ONLY

~

FOR USE IN UNIT I ONLY 1004.10 Revision 2 4.13 Maintain all completed Attachments I tor permanent records.

Request direction from the RAC as to the disposition of these completed foms.

4.14 Notify the RAC when approaching 300 nREM. Recommend to the RAC that your team be relieved if possible. Relief should be conducted in a low radiation area.

4.15 Retain all samples for later counting and analysis. Samples may be returned to the H.P. Lab or designated collection point l at a convenient time as directed by the RAC.

5.0 FINAL CONDITIONS 5.1 Onsite radiation monitoring established and being maintained as required.

O .

O 4.0 FOR USE IN UNIT I ONLY

s

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1004.10 Revision 2 "TI ATTACHMENT I O

Location :

: : Open : Duration: Closed: Duration: : : : : 1

: Window : of Meter: Window: of Meter: True s*: : : : Activity Number : Date: Time: symR/hr: Reading : ymR/hr: Reading : mR/hr. : CPM (gross): CPM (bkgd): Vol (ft 3 ): (pCi/cc)

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g,FOR USE IN UNIT I ONLY 1004.12 Revision 1 11/13/81

/'~'i IMPORTANT TO SAFETY b NON-ENVIRONIENTAL IMPACT RELATEL CONTROLLED COPY FOR USE IN UNIT I ONLY.

THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.12 ENVIRON > ENTAL MONITORING Table of Effective Pages -

Page Revision Page Revision Page Revision Page_ Revision 1.0 1 2.0 1 3.0 1 4.0 0 5.0 0 6.0 0 7.0 0 8.0 0 9.0 0 10.0 0 11.0 0 12.0 0 13.0 0

('%

O Unit 1 Staff Recommends Approval Approval [f Cognizant Dept. Head Date Unit 1 PORC Recommends Approval s ! h^F1G Date // 2 '/

Chairman of PORC Manager TMI I Approval Wf/ kJ Date nl/3h/ !

V QA Modifications / Operations Mgr

/~'s ,4 Date U -

Document ID: 0030W FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY '

- 1004.12 Revision 1 O THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.12 ENVIRONENTAL MONITORING 1.0 PURPOSE The purpose of this procedure is to provide the requirements and methods for environmental monitoring during or after a declared emergency at Three Mile Island. The Environmental Assessment Coordinator is respon-sible for implementing this procedure.

2.0 ATTACHMENTS 2.1 Attachment I - TMINS TLD Program 2.2 Attachment II - Radiological Environmental Sampling Program 3.0 EMERGENCY ACTION LEVELS 3.1 This procedure is to be inititated upon declaration of the following:

a. Site Emergency (as determined by the Site Emergency Procedure 1004.3).

b. General Emergency (as determined by the General Emergency Procedure 1004.4).

c. As directed by the Emergency Director.

4.0 EMERGENCY ACTIONS 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 deter-mine the appropriate environmental sample locations.

O O

1.0 FOR USE IN UNIT I ONLY l

FOR USE IN UNIT I ONLY 1004.12 Revision 1 4.2 Dispatch offsite monitoring teams and the mobile monitoring lab when the Environmental Assessment Consnand Center is activated per procedure 1004.30.

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

4.4 When mobile lab reports to designated location, ensure that additional meterological information from its portable tower is obtained.

4.5 Ensure that field data from the mobile lab and the monitoring teams is relayed to the Control Room and the Near-site Emergency Operations Facility.

4.6 Ensure that all effluent monitoring data is fed into the Environmental Assessment computer.

4.7 Determine the frequency for the changeout of the thermo-luminescent dosimeters (TLD's) listed in Attachment I.

4.8 Determine specific types of samples and sampling frequencies required to determine offsite radiological conditions. Refer to Attachment II.

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

4.10 Ensure that all samples are labelled in accordance with i

Environmental Controls Procedure 1503 through 1503.7.

4.11 Ensure that environmental monitoring is continued to comple-tion in all situations, even though the emergency status has terminated before sampling is complete.

O 2.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.12 Revision 1 O 4.12 e s re th t rea#iree 9119 receres re ce pieteo e maintained in accordance with procedure 1004.5 (Communications and Recordkeeping). Attach log to procedure.

5.0 FINAL CONDITIONS 5.1 All samples have been analyzed and the results reported and evaluated.

O 9

O 3.0 FOR USE IN UNIT I ONLY

. . -. ~ . - . _ .

100 Revision 0 ATTACHMENT I T' ENVIRONMENTAL MONITORING O

TMINS TLD PROGRAM HEIGHT DISTANCE ASIMUTH LOCATION FEET MILES o DESCRIPTION STATUS O T TM-ID-152 4 0.4 0 North Weather Station E, Q O

y TM-ID-2S2 3 1/2 0.7 25 North Bridge E z

C TM-ID-452 3 1/2 0.3 71 Top of Dike Q O TM-SS2 4 0.2 95 Top of Dike 0 -

m -i

___ TM-ID-851 6 0.4 167 Pole No.33-ME-T-60 E, N _ ,_

TM-ID-9S2 4 1/2 0.8 184 South TMI E Q

C TM-ID-1052 6 0.4 200 Pole No.ME-33-T-28 E, N 2 Z r

- TM-ID-11S1 4 0.1 221 Mechanical Draft Towers Q f d TM-ID-13S1 7 0.4 270 Due West on Shelley's

~

Island N TM-ID-1452 3 1/2 0.4 293 Shelley's Island Z

F TM-ID-1551 6 1/2 0.5 317 Shelley's Island N TM-ID-16S1 4 0.2 340 North Boat Dock E, Q TM-ID-3Al 3 0.6 35 Route 441 E,N,Q TM-ID-4A1 7 0.5 65 Laurel Road E TM-ID-SA1 3 0.4 86 Observation Center E, 0 TM-ID-6Al 6 0.5 117 Route 441 on Light Pole E, N Status: E = ETS Location, N = New Location, Q = Quality Control Location !

4.0

100 Revision 0 ATTACHMENT I (Cont'd) T O

HEIGHT DISTANCE ASIMUTH j LOCATION FEET MILES 0 DESCRIPTION STATUS C TM-ID-7A3 3 0.6 143 Route 441 E,N,Q m

TM-ID-11A2 6 0.5 221 Beech Island N -

i O 0.4 z

, y TM-ID-16Al 4 332 Kohr Island

{ TM-ID-10B1 2 1/2 1.1 204 Shelley's Island

! @ TM-ID-1181 6 1.9 227 Route 262 Pole No.ME2890, -

j m BK722-306 E, N d-4 1.3 253 Goldsboro Air Station E

]TM-ID-12B1 i TM-ID-1381 7 1.2 265 Goldsboro Marine on Light i C Pole E, N, Q Z Z r~

j TM-ID-1481 7 1.4 290 Still House Road on Tree E, N g

* ~

TM-ID-1531 6 1.8 304 Still House Road No.ME2397NB,

233L-35L E, N TM-ID-101 4 2.6 O Middletown Substation E a Z j p- TM-ID-8C1 4 2.3 159 Falmouth-Collins Substation Q TM-ID-1E4 6 4.3 3 Vine Street Exit From Route

. 283, Pole No.ME2481-10 E, N TM-ID-2E1 6 4.8 18 School House Lane and Miller '

Road, Pole No.NE782-10 j 'TM-ID-3E3 6 4.5 46 Kennedy Lane, Pole No.74-ME-97 E, N TM-ID-4E5 4 4.9 71 Beagle Road E, N i Status: E = EST Location, N = New location, Q = Quality Control Location 5.0 i . . _ _

O- O to< 0 Revision 0

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ATTACHMENT I (Cont'd) Tl '

HEIGHT DISTANCE ASIMUTH O

LOCATION FEET MILES o DESCRIPTION STATUS TM-ID-5El 6 4.6 85 N. Market Street (Route 230) C and Zaeger Road, Pole No.PP and L (f) 31084, S30386 E, N m 6 4.6 115 Amosite Road, Pole No.PP and L ~

O TM-ID-6E6 31016, S29272 E. N 2~

2 TM-ID-7E6 6 4.8 131 Bainbridge Road (Route 241) and Risser Road, Pole No.ME825 C C Z (f)TM-ID-8E2 6 1/2 4.1 161 Guard Shack at Brunner Road E, N _._.

TM-ID-9El 6 4.9 182 Canal Road, Conewago Heights, Pole No.ME497EM, BK244122 E, N ~

TM-ID-10E3 6 5.0 200 Conewago Creek Road, Strines- O C town Pole No.ME924CE, BANK 231-139 Z

7 p TM-ID-11E3 6 4.1 228 Stevens and Wilson Roads, Pole <

No. ME2521NB E, N' TM-ID-12E4 6 4.3 245 Lewisberry and Roxberry Roads, O Newberrytown, Pole No.ME725NB E, N TM-ID-13E1 6 4.9 268 Yocumtown Road and Old Trail, I No. ME1050NB E, N N Route 262 and Beinhower Road, TM-ID-14E4 6 4.9 281 -

Pole No.ME13SFA E, N TM-ID-15El 6 5.0 313 Lumber Street, Highspire, Pole No.PP and L 26827, S31990 E, N TM-ID-2F1 6 9.0 15 West Areba Ave., and Mill Street, Hershey, Pole No.PP and L 30383, 534608 E, N Status: E = ETS Location, N = New Location, Q = Quality Control Location 6.0 i

12 Revision 0

'T1 ATTACHMENT I (Cont d)

O HEIGHT DISTANCE AZIMUTH 2 LOC ATION FEET MILES o DESCRIPTION STATUS C

TM-ID-5F1 6 6.8 89 Hummelstown Street, Eliza- (f) bethtown, Pole No PP and L 32190, S30207 E, N g

g O TM-ID-7F1 4 9.0 132 Drager Farm Q Z I TM-ID 3G1 4 19.7 47 Cumberland Street (Route 422) at 16th Street, Sub

[

[ station, Lebanon N 7 fil TM-ID-4G1 6 10.0 68 Route 241 E, Q 6 21.1 113 Steel Way and loop Road, 7 TM-ID 6G2 Lancaster, Pole PP and L 21274 39808,. S36930 O

{ N Z

Z TM-ID-7G1 5 1/2 15.0 124 Columbia E I d

TM-ID 9G1 4 13.0 183 North York Substation E TM-ID-14G1 6 12 2 300 Erford Road, Camp Hill, Pole No.PP and L ( ATTACHMENT) 23347, O S33615 N

[- TM-ID-15G1 3 1/2 15.0 3 08 West Fairview E, Q d TM-ID-15G2 6 11.5 307 Penn and Forster Sts. Hbg.

Pole No.PP and L 25874, S35291 N TM-I D-16El 6 4.9 339 Spring Garden Drive and Route 441. Pole No. PP and L 27716, S232497 E, N Status: E = ETS Location, N = New Location, Q = Quality Control Location 7.0

{'

s

/')

k/ 100'f)0 Rev 'sa ATTACHMENT I (Cont'd) -

HEIGHT DISTANCE AZIMUTH O LOCATION FEET MILES o DESCRIPTION STATUS y (Conewago School) Met-Ed TM-ID-3F1 6 7.16 48 1039 CW 764/185 on School C

House Road Rd. 1/8 mi. W of b Schanks Church N ITl O TI-ID-4F1 y

6 1/2 8.53 72 Bellaire PP and L 32920 S 31503 1/4 mi. E. of Bellaire ]

Crossroads on Mt. Gretna Rd. N

{

@ TI-ID-6F1 6 1/2 9.36 113 (Donegal Springs) PP and L 33225 2 S28173 1/8 mi. W of Colebrook -

[Tl Rd and Donegal Springs Rd inter- d section on Donegal Springs Rd. _

Z 11_iD-8F1 6 1/2 7.37 163 (Starview) Met-Ed 193 EM 1/8 Q mi. N of Starview Methodist C Church in Starview on 2 Z Saginaw Road N F 6 1/2 13.15 157 (Wilsbire Hills) ME793SE SW H TI-ID-8G1 corner of Orchard Pd and Stonewood Rd Wilshire Hills N TI-ID-9F1 6 1/2 6.48 177 (Manchester C53-LIM ME240 MT Z on Maple Street in Manchester across from High Street at p- -

corner of Cemetary Drive N 4

TI-ID-10F1 6 1/2 7.39 196 (Zion's View) ME1459 CE SE corner of Coppenhaffer Road and Rt. 295 Intersection N TI-ID-10G1 6 1/2 12.96 204 (Weiglestown) El and P (old Met-Ed) 6632 opposite corner of Alta Vista Road and Fox Run Rd 100 yds East of Rt 74 N Status: E = ETS Location, N = New Location, Q = Quality Control Location 8.0

"i p' A (V

v C34.12 Revision 0 ATTACHMENT I (Cont'd) Tl HEIGHT DIS TANCE AZIMUTH O

LOC ATION FEET MILES o DESCRIPTION STATUS 2 TI-ID-11F1 6 1/2 7.96 225 ( Andersontown) ME611 DO 2017/ b 100 on Andersontown Rd (f)

R 1/8 mi SW of Orchard N m

Q TI-ID 11G1 6 1/2 11.71 225 (Mt. Royal) ME3053 DO Bank -

321 -232 W Side of Rt. 74 at 2 3 Mt. Royal Full Gospel Church N C

C TI-ID-12F1 6 1/2 8.56 242 (Maytown) 16E/78/End Dj/63 7

(f) on Alpine Rd.150 yds S on _

m Rt. 177 at Maytown N q TI-ID-12G2 6 1/2 11.94 236 (Rossville) ME574 WR Bank Z 474-100 W. Side of Rt 74-O 1/4 mi. from Rt.177 cross-C roads by Earch Craft Barn N Z

7.77 260 (Lewisberry) PP and L 24599 I

_ TI-ID-13F1 61/2 I

' q S 29513 W side Rt 382 ~1/2 mi. N of Lewisberry N TI-ID-13G2 61/2 10.4 274 (Lisburn) PP and L 23149 S 30533 O NW corner of Lisburn Rd end M i" St. of Lisburn (Rt ii4)

Z N I TI-ID-13G1 61/2 13.19 276 (Mt. Allen) Attach 21728 d S 30984 of Orchard Lane and Hertzler Rd due S of water tower N TI-ID-14F1 61/2 7.96 29 2 (Reeser's Summit) Attacn 24757 5 31644 on Evergreen Rd by Fairview Brethren in Christ Church Reeser's Summit N Status: E = ETS Location, N = fMw Location, Q = Quality Control Location 9.0

p) n .

k s 100 C/

Rev. .on 0 ATTACHMENT I (Cont'd) 'Tl '

HEIGHT DISTANCE AZIMUTH O

LOCATION FEET MILES o DESCRIPTION STATUS 2 TI-ID-15F1 6 1/2 8.49 308 (Steelton) PP and L 21570 C S 32926 across from parking (f) lot of Steelton Water Co. N m

7 8.07 340 (Rutherford Heights) Attach -

Q TI-ID-16F1 27280 5 34073 on Derry St. at 2 2 66th St. Rutherford Heights, NE corner N C Twenty TLD's collected monthly.

m (Fifty-three additional collected quarterly).

y Status: E = ETS Location, N = New Location, Q = Quality Control Location O C Z Z r H

O Z

r 10.0

rt D

V n

100 %./

Reve ion 0 ENVIRONMENTAL MONITORING ATTACHMENT II O RADIOLOGICAL ENVIRONMENTAL SAMPLING PROGRAM y 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.

m T The following table should be used in determining environmental samp!es (and quantity to be _

Q sampled): Z 2 TABLE I

{

C Quantity / Volume 2

@ Medium Sampled Each Sample Analysis Preferred Sample Location -

m H Gross __.

Air-particulate 7E4 cc (25 ft3) Beta, gamma Downwind from site z Gross o

C Air-Iodine 7E4 cc (25 ft3) Beta, gamma Downwind from site 2 F

Z Gross f y Air-Noble Gases 7E4 cc (25 ft3) Beta, gamma Downwind from site

- Gross W 2 liters Beta, gamma 10 downriver from site O(ater-River Note 1) isotope 2 uns. eem from site for controi Z

I 2 liters Gama 2 from control ~25km from site

< Water-Tap Isotope 4 downwind from site (Note 2)

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

11.0

100 Rev'...on 0 TABLE I (Cont'd) T' Quantity / Volume Medium Sampled Each Sample Analysis Preferred Sample Location 3 C

Vegetation 1 kg. Gamma 2 from control ~25 km from site (f)

(Note 3 Isotope 6 downwind from site pq T

O siik 2 iiters i 131 cs 137 Sr90 4 from control -2 sum from site Z Z (Note 4) 10-20 downwind from site C C (f) Precipitation 2 liters Gamma Onsite collection Z m -i 2 O C Z Z r-

-i O

Z r-4 i

l I

12.0

FOR USE IN UNIT I ONLY 1004.12 Revision 0 D.

V ENVIRONMENTAL MONITORING ATTACHMENT II

~

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

Note 2: Control samples should come from least prevalent wind direction from township (municipal) water supply.

Note 3: Control samples should come from least prevalent wind direction at nearest TLD site for sample accountability. Downwind samples should be taken at/near TLD locations for sample accountability.

Note 4: Milk samples should be raw, untreated milk from dairies in least prevalent wind direction for control purposes NOT ALL SAMPLES ON TABLE I NEED TO St. COLLECTED DURING EMERGENCY CONDITIONS, HOWEVER, A REPRESENTATIVE SAMPLE SHOULD BE TAKEN ON THOSE LISTED, AS TIME PERMITS.

This procedure may continue for a relatively long period of time after the emergency has been cancelled. As a minimum, this procedure should continue in effect until all required samples have been collected, prepared, and analyzed.

sm 13.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT 1 ONLY 1004.16 Revision 1 11/13/81 0 I WORTANT TO SAFETY NON-ENVIRONENTAL IMPACT RELATED CONTROLLED COPY FOR THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EERGENCY PLAN IMPLEMENTING PROCEDURE 1004.16 CONTAMINATED INJURIES / RADIATION OVEREXPOSURE T-Table of Effective Pages '

Page Revision Page Revision Page Revision Page Revision 1.0 1 2.0 1 3.0 1 4.0 1 5.0 1 6.0 1 O

Unit 1 Staff Recomends Approval Approval k Cognizant Dept. Head Date Unit 1 PORC Reconnends Approval tv. 'S t' kP/r Date // 2 /

Chairman of PORC Manager TMI I Approval W /m Date sif/J f/

v QA Modifications / Operations Mgr A Date Document ID: 0031W FOR USE IN UNIT I ONLY

- - - - - ______o

~ '

FOR USE IN UNIT I ONLY 1004.16 Revision 1 O THREE MILE ISLAND NUCLEAR STATION UNIT N0.1 EERGENCY PLAN IWLEMENTING PROCEDURE 1004.16 CONTAMINATED INJURIES / RADIATION OVEREXPOSURE 1.0 PURPOSE

~

To define the conditions where person (s) injured while working at Three Mile Island and exposed to ionizing radiation and/or contaminated with radioactive material will be removed from site to Milton S. Hershey Medical Certer (HMC), Hershey, PA. To further define the steps involved in notifying HMC to allow time for preparation of the Radiation Emergency Area (REA) to receive the injured person (s). To provide for several

! levels of treatment based on the severity of the injury (ies) and the degree of exposure / contamination involved. The Radiological Controls I Foreman /RAC and Shif t Supervisor are responsible for inplementation of this procedure.

2.0 ATTACHMENTS None 3 .0 E ERGENCY ACTION LEVELS 3.1 Person (s) are injured in a radiologically controlled area and have a contaminated injury that can be treated on-site and released.

3.2 Person (s) are injured in a radiologically controlled area and must be transported off-site for medical observation / treatment.

l 3.3 Person (s) are injured or ill and have radioactive contamination on l their clothing or skin and must be transported off-site for medical l

observation / treatment.

3.4 Person (s) have received radiation dose in excess of the limits of

! 10 CFR 20.

O 1.0 FOR USE IN UNIT I ONLY L. . . - .- . . .- . - _

FOR USE IN UNIT I ONLY 1004.16 Revision 1

$ 4.0 EERGENCY ACTIONS 4.1 The Shif t Supervisor and Radiological Controls Foreman shall be l, notified immediately upon discovery of the injured personnel.

NOTE: The following steps may be perfonned concurrently. :

4.1.1 The Shift Supervisor, upon notification of injured personnel, shall:

a. Notify Site Medical Personnel at 8450. If Site Medical Personnel are unavailable, the Shif t Super-visor shall have first aid administered to the injured or ill-personnel.

b. Ensure that First Aid / medical personnel evaluate the injury, to determine the need of medical treatment beyond that provided by on site personnel and that Radiological Controls evaluate the radiological condition of the victim and both report their assessment back to him.

c. If off-site medical assistance is required, the Shift Supervisor (or his designee) will notify Dauphin Co. E0C by dialing 9-911 and repeat the following message: "THIS IS NAE / TITLE AT TMI NUCLEAR STATION. WE REQUEST AN AMBULANCE AND EDIC TO REPORT TO TMI UNIT 1 PROCESSING CENTER. WE i HAVE PERSONNEL WITH FOLLOWING INJURIES: (BRIEF I

DESCRIPTION OF INJURIES) REQUIRING EDICAL ASSISTANCE."

O V

l 2.0 FOR USE IN UNIT I ONLY

~

~FOR USE IN UNIT I ONLY 1004.16 Revision 1 Call Security at Extension 8039, 8040 to inform security of off-site medical assistance arrival so that they can direct of f-site medical personnel to the injured person. The Shif t Supervisor shall also initia'te the requirements of EPIP 1004.19 " Emergency Dosimetry / Security Badge Issuance"

d. Declare an Unusual Event in accordarme with EPIP 1004.1 and perfonn actions as required in Step 4.5 below. j 4.1.2 The Shift Supervisor shall direct personnel with minor injuries, not requiring more medical attention than site first aid, to the decon facility for decontamination and treatment of the injury, per step 4.3.

C

\ 4.2 The Shift 3*eervisor shall, with concurrence of the site l medical personnel, when available, have the victim transported outside of the controlled area if the injury and contamination levels will allow movement for further treatment and surveys.

4.3 If the injury allows, Radiological Controls personnel shall assess the degree of radiation exposure and/or radioactive contaminatior prior to removal from site.

NOTE: All injuries occurring in a radiologically controlled :

area shall be considered contaminated until monitored :

and cleared. :

4.4 The Shift Supervie.or, with concurrence of the site medical ~l staff, shall order the injured person (s) off-site for more extensive medical treatment.

O

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3.0 FOR USE IN UNIT ! ONLY .

'FOR USE IN UNIT I ONLY

~

1004.16 Revision 1

NOTE: By agreement with the Milton S. Hershey Medical :

Center (HMC), Hershey, PA, all contaminated persons :

with injuries too severe to be handled onsite shall :

be sent to H.M.C. for deconta'nination and treatment. :

4.5 The Shift Supervisor shall perform the following steps in the event an injured person (s) is to be transported to HMC.

4.5.1 The Shift Supervisor shall assume the duties of the l Emergency Director.

4.5.2 The Emergency Director shall implement the require-4 ments of Emergency Plan Implementing Procedure 1004.1 " Unusual Event", and request ambulance service from the Dauphin County Emergency Operations Center, as needed, for offsite assistance.

~

4.5.3 The Emergency Director shall call, or have the Shif t !

Foreman call, Charge Nurse, Emergency Room, HMC at 9-534-8333, and using the following message, alert HMC of the arrival of the injured victim:

THIS IS (NAE / TITLE) AT THREE MILE ISLAND ACTING AS (FORi THE EMERGENCY DIRECTOR. TMI IS PREPARING TO 4

TRANSFER A POTENTIALLY CONTAMINATED VICTIM WITH

! INJURIES TO HERSHEI EDICAL CENTER. THE RADIATION EMERGENCY AREA SHOULO 3E PREPAPID TO RECEIVE THIS VICTIM. PLEASE ACKNOWLEDGE AND VERIF'.' THIS MESSAGE I

BY CALLING 948-8069 (8070/8071) AND ASK FOR THE EMERGENCY DIRECTOR. .

O 4.0 FOR USE IN UNIT I ONLY

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'FOR USE IN UNIT I ONLY _

1004.16 Revision 1 g .

[-

Q 4.5.4 The Emergency Director, or his designee, shall then-

briefly describe the injury (s)

give the name of the victim (s)

report levels of contamination, if known -

request special equipment required A .

estimate time of arrival at HK -

describe method of transportation

estimate expected dose rate hazard to HMC Staff f -

Personnel based on dose rate taken 12 inches above '

the victim .

record the name and title of the person receiving '

(( x .,

the notification call, and the time notified _

s 4.5.5 Person (s) decontaminated shall require whole body court-(jx s ing in accordance with RCP 1612 and RCP 1628.

4.6 The Emergency Director shall require transportation of per- .

son (s) with acute radiation exposures in excess of 25 REM whole body to HMC. In this case,the victim (s) can be trans-ported in a conventional manner and will not require activa-tion of the Emergency Plan.

4.7 The Emergency Director and/or RAC may request assistance in evalua-tion of extreme radiation overexposure (i.e. 25 REM or more) from various Health Physics Specialists, (Porter Consultants, Radiation Management Corporation, etc.)

n (v )

5.0 FOR USE IN UNIT I ONLY

r 1

'FOR USE IN UNIT I ONLY 1004.16 Revision 1 4.8 The Emergency Director and Radiological Assessment Coordinator

.1 -

shall restrict personnel who have received internal contamination

,of greater than 50 Percent of the Derived Investigation level, as

- stated in RCP 1628.1, from fJrther work in Airborne Radioactivity

[

_ Areas, until evaluation is made._ Complete and direct the personnel e.. - ',

er ,

., for whole body counting, in accordance with RCP 1612, for evalua- l

- ~

s '- ,;

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tion of Budy Durdens.

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,s. .. 5.0{ FINAL CONDITION , . ,. .

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~35 The perscn(s) has been dec(dtaminated, treated for injury and released for work by the Site Medical Staff.

1 -

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s.

s,..

(s' '.,' -

. 5$.lThe~ person (s) has been entered into the bioassay. program for whole

~. . . .. ~.

p 6kdycountingperRCP1612andRCP(628.

t p 5 . 3, Th5 victim (s) has been transpor+ed to HMC and is receiving treat-

% ment.

~ 3' . .. . .

< * - 5.4 . 'The Radiation Emergency Area and ambulance (s)' used for transporta-a j.~ p s .. ,

+. y,, , tion of the victim (s) has been surveyed and cleared or decon-k ~ , . .

', r f j [ tahinated and cleared.

y 5.5Qihelin'sual u Event has been closed out by the Emer3ency Director.

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3 O 6.0

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FOR USE IN UNIT I ONLY

. s,o FOR USE IN UNIT I ONLY 1004.18 Revision 1 11/13/81 IWORTANT TO SAFETY NON-ENVIRONENTAL IMPACT RELATED CONTROLLED COPY FOR E

UNIT I ONLY THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EERGENCY PLAN IWLEENTING PROCEDURE 1004.18 SEARCH AND RESCUE Table of Effective Pages Page Revision Page Revision Page Revi sion Page Revision 1.0 1 2.0 1 3.0 1 4.0 1 5.0 1 6.0 1 7.0 1 8.0 1 9.0 1 10.0 1 4

O Unit 1 Staff Recommends Approval Approval d Date Cognizant Dept. Head Unit 1 PORC Recommends Approval U C 0 HD Date // 2 l Chairman of PORC Manager TMI I Approval 4 7)

// '

b_ ) Date H '

3lh l /

QA Modifica(tions/ Operations Mgr

[ Date Document ID: 0026W FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.18 Revision 1 THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EERGENCY PLM IELEENTING PROCEDURE 1004.18 SEARCH AND RESCUE 1.0 PURPOSE To provide guidelines to the Operations Support Center Coordinator and Search and Rescue team leaders in emergency Search and Rescue operations.

The Search and Rescue Team Leader is responsible for implementing this procedure, when directed by the Operations Support Center Coordinator.

2.0 ATTACHENTS 2.1 Attachment I - Location of 100 person Emergency Medical Kits 2.2 Attachment II - Search and Rescue Team Emergency Actions 2.3 Attachment III - Search and Rescue Team Checklist 3.0 EERGENCY ACTION LEVELS 3.1 This procedure shall be implemented:

a. When an individual (s) has not exited the protected area, as !

directed by Security Procedure 1005.12 (Personnel Accountability), and cannot be contacted.

b. Individual (s) is unable to exit an area without assistance.

c. Upon direction of the Emergency Director /0SC Coordinator.

d. Upon the OSC Coordinator assembling Search and Rescue Team (s) and appointing a team leader.

NOTE: Search and Rescue team (s) should consist of at least :

three (3) volunteers. The team (s) should consist of :

personnel from Operations Maintenance and/or Health :

Physics. (All Search and Rescue team members shall :

have had first aid training.) :

9 O

1.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.18 Revision 1 O

U INITIALS 4.0 EMERGENCY ACTIONS 4.1 Designate a team member as Communicator.

4.2 Direct a team member to be responsible for obtaining first aid equipment from one of the locations in Attachment I.

4.3 Direct a team member to obtain any safety equipment that may be required, including portable radio (s).

4.4 Ensure that all equipment to be used by the team is functional and perform a radio check (s).

4.5 Confer with Radiological Controls Coordinator for possible radiological hazards.

4.6 If radiological hazards exist, implement In-Plant Radiological Controls During Emergencies procedure (1004.9).

4.7 Complete Attachment II of this procedure.

4.8 When the individual (s) is found, relay the following information to the Ops Support Center Coordinator.

, a. location

b. extent of injuries, if applicable

c. contamination levels, if applicable 4.9 If persons are injured and contaminated implement EPIP 1004.16.

l 4.10 If offsite medical assistance has been requested, standby to I provide assistance. Refer to EPIP 1004.16.

4.11 After Search and Rescue is complete, debrief the Search and Rescue Teams in accordance with In-Plant Radiological Controls During Emergencies (1004.9) using Attachment I of 1004.9 for debriefing requirements.

1 1

2.0 FOR USE IN UNIT I ONLY

! FOR USE IN UNIT 1 ONLY 1004.18

, Revision 1 4.1E After debriefing, collect all logs and records pertaining to l the Search and Rescue Operation and have them forwarded to the Ops Support Center Coordinator.

j 5.0 FINAL CONDITIONS 5.1 Missing individual (s) located, removed from any hazardous area, and with First Aid being administered.

l 5.2 Medical and ambulance assistance summoned as necessary and i 1004.16 implemented.

a O

O 3.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT i ONLY 1004.18 Revision 1 ATTACHENT I Location of 100 Person Emergency Medical Kits

1. Building 48 l 2. Trailer 127A (Training)

3. Unit 1 Warehouse North

4. Unit 1 Warehouse South

5. Health Physics Lab I

6. Control Room - Instrument Shop Hallway

!. Rive Water Pump House, Unit 1 Entrance O 4.0 FOR USE IN UNIT I ONLY

._ ~

FOR USE IN UNIT I ONLY 1004.18 Revision 1 ATTACHENT II SEARCH AND RESCUE TEAM EERGENCY ACTIONS The Search and Rescue team leader is responsible for the actions in this attachment.

INITIALS

1. Proceed to designated area with Radiation Survey Meter turned on and using Radiological Controls precautions.

2. Ensure that communications, at predetermined intervals, are maintained with the Operations Support Center.

3. Ensure that the Operations Support Center Coordinator is kept informed of team's location, observations and survey results.

4. If radiological hazards exist, ensure that:

(m) (a) The HP team member is continuously monitoring radiation levels and that any changes are reported to the Operations Support Center Coordinator.

(b) Team members are checking their dosimeters regularly.

(c) Dose limits as specified in 10CFR20 are not exceeded.

(d) That stay times as established by the Radiological Controls Coordinator are not exceeded.

(e) If applicable, ensure that the Emergency Director has authorized exceeding whole body or thyroid /for emergency life saving or equipment saving activities.

O 5.0 FOR USE IN UNIT l ONLY

FOR USE IN UNIT I ONLY 1004.18 Revision 1 ATTACHENT II

_ SEARCH AND RESCUE TEAM EERGENCY ACTIONS

5. When the individual (s) is located, check the person for:

(a) Injuries, illness, respiration and pulse.

(b) If injured, administer First Aid. (Infonn Emergency Director and use EPIP 1004.16).

(c) Contamination

6. Report the following findings to the Operations Support Center Coord. (via radio or plant paging system)

(a) location (b) extent of injuries (c) contamination . level s (d) first aid administered

7. Request assitance from the Operations Support Center Coordinator, for transport of any injured or contaminated individuals.

8. Aid the offsite medical personnel as requested.

9. Upon completion of Search and Rescue operations, report to the Operations Support Center for debriefing.

6.0 FOR USE IN UNIT I ONLY

~ .

FOR USE IN UNIT l ONLY 1004.18 Revision 1 ATTACHENT III SEARCH AND RESCUE TEAM CHECKLIST (C0!PLETE AS TIE PERMITS)

DATE: TIE:

EERGENCY DIRECTOR:

OPERATIONS SUPPORT CENTER C0ORDINATOR:

1. Team member's name, organization and badge number:

a. , , (Team Leader)

b. , ,

c. , ,

d. , ,

i

2. Identity of missing person (s): a.

b.

c.

3. Last known location:

4. Job or function of missing person (s):

5. Search team special instructions:

O 7.0 FOR USE IN UNIT I ONLY

!' FOR USE IN UNIT I ONLY l Revision 1 ATTACHENT III l SEARCH AND RESCUE TEAM CHECKLIST

6. Team equipment

PC's First Aid Equipment r Dosimetry Communications, if applicable Scott-Paks (Specify) i l Lighting (Specify)

7. Offsite emergency aid notified / requested:

Organization / Person Time Time Personnel Notified Notified On Site a.

b.

c.

d.

8. Time Security informed of-emergency offsite response:

9. Time Search begins:

8.0 FOR USE IN UNIT I ONLY

_~-a 4 4: _--_-_A5_m . - a q- +_,,a,_

,__=1 _ ghA s y A_ p 4

! FOR USE IN UNIT I ONLY 1004.18

, Revision 1 ATTACHENT III i

SEARCH AND RESCUE TEAM CHECKLIST f

., 10'. ' Communications l Checks:

i i

TIE BY TIE BY TIE BY i'4.

7 iO

11. Missing individual found:

I a. Time:

} b. Medical condition: l

c. Remarks on removal from areas:

d. Location individual discovered ,

i

!- I

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!O l 9.0 F.OR USE IN. UNIT I ONLY

i FOR USE IN UNIT I ONLY 1004.18 Revision 1 ATTACHMENT III SEARCH AND RESCUE TEAM CHECKLIST i ,

12. Hershey Medical Center notified:

a. Time:

a

b. Who contacted:

c. By:

d. Description of injuries / contamination:

i i 13. Team debriefing (special coments):

1 4

i f

14. Team secured:

a. Time:

b. By:

1 lO 10.0 FOR USE IN UNIT I ONLY

-. ,-.,-- ,,,..r .. , -. ,-- --,- . . .,-,,,-,,,,-,,,,,-n,-,--,...-,,.e,-,n-,-,..,,,...--,---, ,--n-..~, ,--

2 FOR USE IN UNIT l ONLY 1004.19 Revision 1 11/13/81 IMPORTANT TO SAFETY

O. NON-ENVIRONENTAL IMPACT RELATED CONTROLLED COPY FOR ,

THREE MILE ISLAND NUCLEAR STATION USE IN UNIT l ONLY UNIT NO.1 EERGENCY PLAN IPFLEENTING PROCEDURE 1004.19 EERGENCY D0SIETRY/ SECURITY EADGE ISSUANCE Table of Effective Pages Page Revision Page Revision Page Revision Page Revision 1.0 1 2.0 1 3.0 1 4.0 1

'O s.J Unit 1 Staff Reconnends Approval Approval /

Cognizarft Dept. Head Date Unit 1 PORC Reconnends Approval e G G f4L Date // 2 $/

Chairman of PORC Manager TMI I Approv 1 Y_,; ,

W Date//f/3f#/

V QA Modifications / Operations Mgr O

~

Date V

Document ID: 0013W FOR USE IN UNIT I ONLY

1 FOR USE IN UNIT I ONLY 1004.19 Revision 1 THREE MILE ISLAND NUCLEAR STATION s - UNIT NO. I EMERGENCY PLAN IWLEMENTING PROCEDURE 1004.19 EMERGENCY D0SIETRY/ SECURITY BADGE ISSUANCE 1.0 PURPOSE To establish tne method cf issuance of Thennoluminescent Dosimeters (TLD) and ER Security Badge (Escort Required) to emergency personnel requiring access to TNI.

For Fire / Ambulance / Police emergencies, the on duty Site Protection Sergeant (SP0) shall be responsible for inplementing the actions outlined in section 4.1 and 4.2.

For all other emergencies, the Group Leader, Security Support / Personnel Monitoring Coordinator will be responsible for implementing the actions outlined in section 4.3.

2.0 ATTACHMENTS 2.1 Attachment I - Emergency TLD/ER Security Badge Issuance Data Sheet, Processing Center / Search II/ North Gate / South Gate. l 3.0 EMERGENCY ACTION LEVELS 3.1 Upon requesting Fire / Ambulance / Police for a TMI Emergency requiring processing via North / South Gate.

3.2 Upon requesting additional support personnel for an Alert, Site or General Emergency requiring processing via the Alternate Emergency Operations Facility (AE0F) (Crawford Station), Middletown.

3.3 Upon determining the need to wear TLD's at the EOF.

3.4 As directed by the Eme gency Director.

O FOR USE IN'6 NIT I ONLY

FOR USE IN UNIT I ONLY 1004.19 Res;sion 1 4.0 EERGENCY ACTIONS 4.1 Fire / Ambulance / Police 4.1.1 Af ter notification by the Emergency Director, or his designee, that Fire / Ambulance / Police have been dispatched to the site, the Site Protection Sergeant shall notify North / South gate Site Protection Officer to allow emer-gency vehicles immediate access onto Island.

h 4.1.2 When emergency crew (s) arrive on site, if emergency does not require access to the protected area, no badges (ER or TLD) are required.

NOTE: If the emergency crew (s) are required to work outside :

the protected area affected by a radioactive plume, :

TLD's will be issued at the North / South Gate as :

directed by the Emergency Director _or his designee. :

If emergency personnel must enter the Protected Area, the SP0 at the Processing Center (PC) or Search Gate No. 2 shall proceed as follows:

a. Open grey emergency TLD box and remove several ER/TLD badge combinations, and Emergency Crew Roster.

b. Verify identification of emergency crew and issue badges to emergency crew as they pass through PC or

Search 2.

c. If emergency crew must enter through an alternate gate, the SP sergeant shall meet the emergency crew at the gate to issue ER/TLD badges.

d. As soon as the emergency crew has entered the

) protected area, notify Dosimetry at extension 8473.

2.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.19 Revision 1 4.1.3 Upon completion of the emergency, retrieve the TLD/ER badges from the emergency crew at either PC, Search 2 or entry point, obtain all remaining information from crew members, and notify Dosimetry personnel at extension 8473 (or by plant page) for TLD processing.

4 .2 - All fire vehicles shall stage in areas at direction of SP Sergeant until required.

4.3 For emergency personnel not requiring immediate entry to TMI, i.e.,: Support personnel from other sites and agencies processing into TMI from the AE0F (Crawford Station), Personnel at the E0F, f etc.

4.3.1 Activate the Security badge issuance area of the AE0F.

4.3.2 Issue emergency security badges in accordance with SP 1005.10.

4.3.3 Activate the dosimetry issuance area of the AE0F. If TLD issuance is required at the EOF, dispatch a dosimetry clerk to the EOF to issue TLD's.

4.3.4 Issue emergency dosimetry in accordance with RCP 4200.

5.0 FINAL CONDITIONS 5.1 Fire / Ambulance / Police personnel have entered TMI, performed the required emergency actions and exited site, leaving TLD/ER badge with SP0 at entry gate.

5.2 Support personnel from other sites and agencies are properly processed into TMI via the AEOF (Crawford Station).

5.3 TLD's have been issued at the EOF if needed.

O FOR USE IN 6 NIT I ONLY '

FOR USE IN UNIT I ONLY 1004.19 Revision 1

(~'T EERGENCY DOSIETRY/ SECURITY BADGE ISSUANCE k)

ATTACHENT I EERGENCY TLD/ER SECURITY BADGE ISSUANCE DATA SHEET, PROCESSING CENTER / SEARCH II/

NORTH GATE / SOUTH GATE Security ER : TLD : : Social Security

: : i Badge Number : Number : Name : Number !

l l

: : l

("3 : : :

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: : l

('s

/

4.0 FOR USE IN UNIT I ONLY

'FOR USE IN UNIT I ONLY 1004.20 Revision 2 IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED CONTROLLED COPY FOR THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLANNING IMPLEENTING PROCEDURE 1004.20 PERSONNEL / VEHICLE MONITORING AND DECONTAMINATION O

Table of Effective Pages -

Page Revision Page Revision Page Revision Page Revision 1.0 2 2.0 2 3.0 2 4.0 2 5.0 2 6.0 2 7.0 1 8.0 2 9.0 2 10.0 2 _

O v

Unit 1 Staff Recomends Approval Approval / Date Cognizant Dept. Head Unit 1 PORC Recomends Approval f

l h (f ( / Date /// 7/

Chairman of PORC Manager TMI I Approval G7f f / /

nJ Date //

/3lff/

G' QA Modifications / Operations Mgr

[ Date DOCUENT ID: 00001W FOR USE lN UNIT I ONLY

'FOR USE IN UNIT I ONLY 1004.20 Revision 2

(~h THREE MILE ISLAND NUCLEAR STATION

( ,/

UNIi NO.1 EERGENCY PLANNING PROCEDURE 1004.20 PERSONNEL / VEHICLE MONITORING AND DECONTAMINATION 1.0 PURPOSE.

The purpose of this procedure is to provide guidance for the monitoring and decontamination of personnel and vehicles that have exited contami-nated or possioly contaminated areas.

The Radiological Assessment Coordinator is responsible for the implemen-tation of this procedure.

2.0 ATTACHENTS 2.1 Attachment I - Monitoring Team Leader Checklist 2.2. Attachment II - Personnel Contamination Report 2.3 Attachment III - Vehicle Contamination Report

! 2.4 Attachment IV - Checklist for Decontamination Team Leader

(^)

( 3.0 EERGENCY ACTION LEVELS 3.1 This procedure will be implemented by the Radiological Assessment Coordinator when:

3.1.1 An evacuation has been ordered and personnel or vehicle are, or are suspected to be contaminated.

3.1.2 As directed by the Emergency Director.

4.0 EERGENCY ACTION 4.1 The Radiological Assessment Coordinator will determine the location to be used for personnel / vehicle monitoring a'nd vehicle decontamination. (Normally the Middletown/500 Kv Substation.) Contaminated personnel are sent from the mon-itoring location to Crawford Station after monitoring.

1 (m) /

1.0 l FOR USE IN UNIT I ONLY l

'FOR USE IN UNIT I ONLY 1004.20 Revision 2 4.2 Assign one team leader each for the personnel and vehicle monitoring teams and one team leader for the vehicle decon-tamination team. Assign one team leader for the personnel decon team to proceed to the Alternate E0F.

4.3 Instruct the tean leaders that they are responsible for completing the actions listed in their respective attachments.

4.3.1 Vehicle Monitoring Team Leader - Attachments I, III, and IV.

4.3.2 Vehicle Decontamination Team Leader - Attachments III and IV.

4.3.3 Personnel Monitoring Team Leader - Attachments I and II.

4.3.4 Personnel Decontamination Team Leader - Attachments II and IV.

4.4 Direct the team leaders to implement their respective attach-ments.

4.5 Assign a sufficient number of qualified personnel to each team to perform the designated task.

4.6 When informed by the team leader that the monitoring team is ready for operation:

4.6.1 Assign a team member to maintain communications and record keeping per procedure 1004.5.

4.6.2 Instruct the team leader that personnel monitoring will be in accordance with Unit 1 Radiological Controls Procedure 1612.

4.6.3 Ensure that a Communication Equipment check is performed.

O 2.0 FOR USE IN UNIT I ONLY

'FOR USE IN UNIT I ONLY 1004.20 Revision 2 4.7 When informed by the team leader that the de:ontaminat1.,n team is ready for operation:

4.7.1 Brief the teams on tneir interaction while performing their various duties.

4.8 Ensure transportation is available for the teams.

4.9 Dispatch the teams to the designated monitoring /

decontamination locations.

4.10 Dial 9-911 and request a fire truck be sent to the 500 Kv Substation /or Middletow.s Substation for washdown of vehicles.

5.0 FINAL CONDITION 5.1 Teams are on station providing personnel / vehicle monitoring and decontamination.

5.2 Decontaminated indivHuals who have had whole body counts and are standing by at Crawford Station, dismissed or back at

their work locations.

5.3 'he Radiological Assessment Coordinator has been notified of i

all individuals who could not be decontaminated.

5.4 Decontaminated vehicles are returned to service. Contaminated vehicles have been impounded and roped off, i

I O

3.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.20 Revision 2 ATTACHENT I MONITORING TEAM LEADER CHECKLIST The personnel and vehicle monitoring team leader is responsible for carrying out the action items in this attachment.

1. Procure a radio from the locker in the Processing Center.

NOTE: Personnel monitoring team also obtain PCs fr om :

warehouse. :

2. Procure Emergency Monitoring Kit and Protective Clothing from the Emergercy Equipment Locker in the Unit I Warehouse.

l 3. Perform an operational check of the communications equipment.

A 4. Assemble with the personnel monitoring team members for a V briefing with the Radiological Assessment Coordinator or his designee.

5. Proceed with the monitoring team to the designated site and report by radio to the Radiological Assessment Coordinatcr or his designee.

6. Assign personnel as personnel monitors and vehicle monitors as applicable.

7. Direct the Comunicator/ Record Keeper to complete Attachment 11 for each person monitored or Attachment III for each l vehicle monitored.

O U

4.0 FOR USE IN UNIT I ONLY

'FOR USE IN UNIT I ONLY 1004.20 Revision 2 ATTACHENT I MONITORING TEAM LEADER CHECKLIST

8. Ensure that all persons with contamination greater than 1000 disintegrations per minute (100 cpm above background on RM-14 with HP-210 probe or equivalent) report to the decontamination area with Attachment II filled out.

9. Ensure that the contamination levels are documented for each individual and vehicle, both before and af ter decontamination.

10. Direct that vehicles found to have contamination levels greater than 1000 dpm be taken to the decontamination team leader for decontamination and complete Attachment III.

11. Direct the team member to have each contaminated individual /

vehicle take Attachments II and III to decon area and give to decon team.

12. If after successive attempts to decontaminate an individual, levels cannot be reduced below 1000 dpm, direct the communi-cator to contact the Radiation Protection Coordinator and request further instructions.

O O

5.0 FOR USE IN UNIT I ONLY

'FOR USE IN UNITI ONLY i 1004.20 l Revision 2

( ATTACHMENT I MONITORING TEAM LEADER CHECKLIST

13. If after successive attempts to decontaminate a vehicle, i

l- levels cannot be reduced below 1000 dpm (100 cpm above back-1

! -ground on RM-14 with HP-210 orobe or equivalent) detain the

! vehicle for additional ev:Jiuation and possible additional i

i decontamination.

l 14. Periodically perform background surveys to ensure that back-ground has not increased significantly.

1 Monitoring Team Leader Date Time 4

3 i

l t

o 6.0 FOR USE IN UNIT I ONLY

i OR USE IN UNIT I ONLY 1004.20 Revision 1

. ATTACHMENT II I

PERSONNEL CONTAMINATION REPORT Name SSN __ Company / Dept. __

Date __ _. _

Time._._ .-_ _ _ _ ___

Address (If Not Met-Ed) _ _ _ _ . _ _ _ _ - .

Survey Instr'~ ant Used: ,

Model - . _ . - ,

V Probe \ [, E ,, , '

S/N

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[ \l ( )Left vv i ( )Right ./ \ )

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Contaninated Body Area Initial After One After Two After Thrt-(Indicate On Drawin;) Activity Decon Decon Decon (dpm) _, dpm) ___ __ __dpm)

( ( . (dpm)__, __,

p.

A. . . . . . .- , ,

30TJ: Pay c1 pngg{ tfNa0 mot taONEYeet for potentia 1 Contamina lon.

~FOR USE IN UNIT I ONLY 1004.20 Revision 2 3

ATTACHENT III VEHICLE CONTAMINATION REPORT 1 -

1%KE MODEL LICENSE NO.

COLOR OWNER

,mn -=-

m

" 9 O a

L73: \/

m LjJ s-l -w__

_w -

CONTAMINATED VEHICLE AREA : INITIAL ACTIVITY dpm : AFTER ONE DECON ETC.

1

NOTE: Pay close attention to air cleaner, grille, tires :

and roof for potential contamination. :

V, 8.0 FOR USE IN UNIT I ONLY

'FOR USE IN UNIT I ONLY 1004.20 Revision 2 O

V ATTACHENT IV

" DECONTAMINATION TEAM LEADER CHECKLIST" The decontamination leader is responsible for carrying out the action items in this attachment.

1. Procure sufficient decontamination aids for vehicle decontami-nation.

a) Absorbent Towels b) Detergent c) Scrub brushes

NOTE: Personnel decon equipment is located at Crawford :

Station. :

2. Assemble with the decontamination team members for a briefing with the Radiation Protection Coordinator.

3. Proceed with the decontamination team to the designated decontamination site.

4. Upon arrival at the site designate the area to be used for decontamination activities.

5. With assistance from the Fire Department personnel direct the setup of the vehicle decontamination facility.

6. Assign team members for personnel / vehicle decontamination.

7. Direcc the team members in their decontamination duties and ensure they receive Attachment II and III.

O V

9.0 FOR USE IN UNIT I ONLY

'FOR USE IN UNIT I ONLY 1004.20-Revision 2

.V O ATTACHENT IV

" DECONTAMINATION TEAM LEADER CHECKLIST"

8. Ensure that, af ter each decontamination attempt, each per. son /

vehicle is surveyed and the results recorded and filed upon completion.

9. Direct the Comunicator/ Record Keeper to retain Attachment II for each individual decontaminated.

Decontamination Team Leader Date Time O

O 10.0 .

FOR USE IN UNIT.I ONLY

' FOR USE IN UNIT I ONLY 1004.27 Revision 2 11/13/81

' 0 IW ORTANT TO SAFETY NON-ENVIRONENTAL IMPACT RELATED CONTROLLED COPY FOE USE IN UNITI ONLY THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EERGENCY PLAN IWLEENTING PROCEDURE 1004.27 ACTIVATION OF THE NEAR-SITE EERGENCY OPERATION FACILITY Table of Effective Pages d Page Revision Page Revision Page Revision Page Revision

, 1.0 1 2.0 1

> 3.0 1 l

4.0 1 5.0 2

.i 6.0 1 7.0 1 8.0 1 9.0 1 10.0 1 11.0 1 l-O l

1 l

Unit 1 Staff Recomends Approval Approval ~

[ Date Cognizant Dept. Head i

Unit 1 PORC Recommends Approval e kG k/7G Chairman of PORC Date // ' //

l Man er TMI I Approval h/

l /M , Date //,

// '

V QA Modifications / Operations Mgr k/A, oate

^

Document ID: 0015W

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FOR USE IN UNIT I ONLY en,--w,n,-.,e ,rn,-,--,,--,-,w----e,,-.,,-,r -,---<~,----,-c.--_a.~

' FOR USE IN UNIT 1 ONLY l

1004.27 Revision 1 THREE MILE ISLAND NUCLEAR STATION UNIT 1 NO. EttERGENCY PLAN IMPLEMENTING PROCEDURE 1004.27 ACTIVATION OF THE NEAR-SITE EfERGENCY OPERATION FACILITY 1.0 PURPOSE The purpose of this pmcedure is to pmvide guidelines for the Emergency Support Dimetor to activate the Hear-Site Emenjency Operations Facility (Observation Center).

The Emergency Support Dimetor is msponsible for implementing this i

p mcedu m.

2.0 ATTACHMENTS 2.1 Attach 1ent I, Emergency Support Dimetor's Checklist.

4 2.2 Attachnent II, Emenjency Support Communicator's Checklist.

2.3 Attachnent III, Group Leader - Chemistry Support Checklisf.

2.4 Attachnent IV, Technical Support Repmsentative Checklist.

2.5 Attach 1ent V, Assistant Environmental Assessment Coordinator's Checklist.

l 2.6 Attach,ent VI, Near-Site Emenjency Operations Facility Floor Plan.

, 3.0 EffERGENCY ACTION LEVELS i 3.1 This pmcedure is to be initiated upon declaration of any of the

! following:

3.1.1 Site Emrgency (1004.3) 3.1.2 General Emenjency (1004.4)

I

! 3.1.3 At any other time wher, the Emenjency Dimetor feels plant t

conditions warrant it.

i O

l FOR USE IN f) NIT I ONLY

( .

l

'FOR USE IN UNIT I ONLY 1004.27 Revision 1

()

(j 4.0 EMERGENCY ACTIONS INITIALS 4.1 Coordinate the activation of the Near-Site Emergency Operations Facility as follows:

4.1.1 Assistant Emerge;'ev Support Di rector:

Report to the Observation Center and assist the Emergency Support Dimetor in performing the Emer-gency Support Director's Checklist ( Attach 1ent I),

which is located in the Near-Site Emergency Opera-tions Facility (EOF) ESD Office. He will also assist in implementing this procedure.

4.1.? Emergency Support Comunicator:

Report to the Observation Center and complete the

(~')

v Energency Support Comunicator's Checklist (Attach-ment II), which is located in the Emergency Opera-tions Facility Emergency Kit.

4.1.3 Group Leader - Chemistry Support:

Report to the Observation Center and complete the Group Leader - Chemistry Support Checklist (Attach-nent III), which is located in the Emergency Opera-tions Facility Emergency Kit.

4.1.4 Technical Support Representative:

Report to tie Observation Center and complete the Technical Support Representative's Checklist

( Attach 1ent IV).

f~

t)/

FOR USE IN 2 UNIT I ONLY

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

!' 'FOR USE IN UNIT I ONLY 1004.27 Revision 1 4.1.5 Assistant - Environmental Assessnent Coordinator:

j - Report to tN Observation Center and complete tN Assistant Envimnmental Assessment Coordinator -

i' Checklist (Attachnent Y).

5.0 FINAL CONDITIONS

INITIALS l 5.1 The Near-Site Emergency Operations Facility is operational with tN i

desimd positions manned and functional. Comunications are established among the necessary organizations and agencies, i

)

4 i

O I

4 2

4 O -

{ FOR USE IN UNIT I ONLY 4

-- , , . , - , ,-.,--,..m9.-w. - 4.- - - - - ,-v_w',

f FOR USE IN UNIT l ONLY 1004.27 Revision 1 ATTACHMENT I EffERGENCY SUPPORT DIRECTOR CHECKLIST INITIALS HOT E: The Emergency Support Staff / Emergency Pir ming i

! Tlepresentative should complete this Chr 0 :st. '

1. Assign personnel to assume the following positions, as necessary, and direct those personnel to report to tre area indicated and complete the mquired cbcklists (located in locker in ESD Office):

i a) Emegency Support Communicator - Obsertation Center b) Group Leader - Chemistry Support - Observation Center c) Technical Support Representative - Observation Center d) Assistant Environmental Assessment Coordinator Observa-tion Center.

2. Start the Emergency Support Directors Log ( Attactinent III of 1004.5) in accordance with the Communications and Recordkeeping procedure by performing tre following:

a) Log the date, time and shift in the upper lef t-hand co rne r.

b) Complete tre title of tie log and the name of the person assumitig the responsibility of the Emergency Support Di recto r.

c) Log the names of tre personnel assigned to the positions listed in tre upper righthand corner.

d) flake an entry by logging tre '.ime, and describing the i.;nergency, plant status, and any major evolutions in p rog ress.

FOR USE IN L NIT I ONLY

FOR USE IN UNIT 1 ONLY 1004.27 l Revision 2 e ATTACHENT I EERGENCY SUPPORT DIRECTOR CHECKLIST INITIALS _

e) Ensure the Emergency Support Communicator assigns someone to act as a logkeeper to maintain this log.

3. Assign a person to set up and maintain the- Near-Site Emergency

\

Operations Facility Status Boards.

4. When the completed checklists from the assigned Offsite Emergency Support Organization positions are received, inform the Emergency Director that the Offsite Emer7ency Organization is operational.

5. If TLD issuance is necessary, notify the personnel monitoring coordinator at the AEOF and have him/her dispatch a clerk to issue TLD's.

NAE TIE DATE Emergency Support Director 4

t 4

4

-Q i 5.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.27 Revision 1 C\

V ATTACHMENT II EMERGENCY SUPPORT COMMUNICATOR CHECKLIST INITIALS

1. Ensum tre required phones am obtained from the ESD Office and plugged into the receptacles at the apprepriate areas for the locations listed below (See Near-Site Emegency Operation Facility Plan - Attactrient VI):

a) Radiological Line (EACC Rep.)

b) Operational Line (Technical Support Group) c) Emergency Director's Line (ESD desk) d) Conventional Telephones (Communicator) e) Energency Notification System (NRC) n f) Health Ptysics Networt (NRC) k g) Environmental Assessment Line (EACC Rep.)

h) Parsippany/TMI Line (Technical Support)

2. Turn on the systens comunications radio.

3. Assign personnel for the following positions, as necessary:

NOTE: Instmct the phonetalkers to record all emergency 1 related calls on the Telephone Comunications Log- !

i sheet ( Attachnent II of EPIP 1004.5, Comunications

! and Recordkeeping). :

a) Logkeeper (to maintain the Emergency Support Director's Log) b) Radiotalker (to monitor radio communications and log any important regJests/recomendations, etc) c) Status Board Keeper d) Phonetalkers to answer the Conventional Telephones on the L

p).

(

! Phonetalkers table.

l FOR USE IN t:PNIT I ONLY

FOR USE IN UNIT I ONLY 1004.27 Revision 1 ATTACHMENT II EMERGENCY SUPPORT COMMUNICATOR CHECKLIST INITIALS e) Phonetalkers, as necessary, to nan the following lines of communications (If the cegnizant Group Leader / person doesn't have personnel available to man tre phones).

(1) Radiological Line (2) Operational Line (3) Parsippany/TMI Line (4) Emertjency Director Line (5) Environmental Assessment Line

4. Ensure all phonetalkers have a supply of Teleptone Communications Logsheets (Attachnent II of the EPIP 1004.5, Comnunications and Recordkeeping) stored in ESD Office.

5. When completed, collect checklists f rom the following personnel and report to the Enertjency Support Di rector.

a) Group Leader - Chemistry Support T

b) echnical Support Representative c) Assistant End ronmental Assessment Coortfinator

6. Develop a wateFbill for persons under your direct control.

_7. Plotify the Emergency Support Staff /Emenjency Planning Representa-tive that tre duties of the Emergency Support Comunicator have been assumed and return this form, along with the checklists collected in Step 5 above, to tiem.

NAP'E TIME DATE TmcGoney Support Comunicator O

FOR USE IN tJNIT I ONLY

FOR USN IN UNIT I ONLY 1004.27 Revision 1 ATTACH?ENT III GROUP LEADER-CHEMISTRY SUPPORT CHECKLIST INITIALS 1.

Set up the Chemistry Status Board and work ama as illustrated in Attachnent VI.

2.

Start the Group Leaders Chenistry Support Log (Attachaent III of '

EPIP 1004.5, Comunications and Reconikeeping).

3.

Comunicate with tN Chenistry Coordinator to detennine tN man-pcwer and chemistry equipment needed to support the energency.

4.

4 Contact other facilities and recuest additional assistance as needed as per 1004.6, Additional Assistance and Notification.

5.

Notify the Emergency Support Staff / Emergency Planning Reprrsenta-tive that the duties of the Group Leader Chenistry Support have been assumed.

(Forward this completed form to tN Emergency Support Staff / Emergency Planning Representative.

NAtiE i TIfE DATE (Group Leader-Chemistry Support) 4

, O FOR USE IN81oJNIT I ONLY

FOR USE IN UNIT I ONLY 1004.27 Revision 1 ATTACHMENT IV

)

TECHNICAL SUPPORT REPRESENTATIVE CHECKLIST INITIALS

1. Set up Tech Support wort area and Parsippany/TMI telepNne as illustrated in Attachnent VI (phone located in utility room).

2. Start the TecFnical Support Representative log ( Attachnent III of EPIP 1004.5, Communications and Recordkeeping).

3. Assign a phonetalker to connunicate on the Parsippany/ Tit! Line with the onsite Comunicator in tte TSC (Technical Support Center) and the Parsippany Technical Support Center. InstnJct tte phonetalker to log all pertinent infomation on tie telephone Conmunications Logsbeets ( Attactment II of EPIP 1004.5, Connunications and Record-keeping).

sj 4. Activate the CRT and connence perfoming accident assessnent functions by monitoring present plant parameters and conducting trend analysis of key parameters.

5. Obtain prints, technical manual s, reference material s, etc. , f run ESD Office Files and set-up as required in tre area of the Techni-cal hpport Representative.

6. Develop a watchbill for your organization.

7. Notify the Emergency Support Staff /Energency Planning Representa-l tive that the duties of the Technical Support Representative have l

I been assumed. (Forward this completed fom to the Emergency Support Staff /Energency Planning Representative).

l 1

NAME TIttE DATE TecPnical Support Representative m

m, l FOR USE IN UTIT l ONLY l

' FOR USE IN UNIT I ONLY 1004.27 Revision 1 (3

G' ATTACHMENT V ASSISTANT ENVIRONMENTAL ASSESSFENT COORDINATORS CHECKLIST INITIALS

1. Hook-up the EACC telephone (phone stored above connunicator's desk, jack behind ventilation grill opposite steps) and set up EACC wort ama as illustrated in Attactnent VI.

2. Start the Assistant Envimnmental Assessment Ceordinator's Log (Attach 1ent III of EPIP 1004.5, Communications and Recordkeeping).

3. Assume the position of phonetalker to maintain comunication on the Environmental Assessment Line with tN Envirenr. ental Assessment Communicator at the Envimnmental Assessment Comand Center. Log r\

/ all pertinent infomation on the telephone comunications log sheets ( Attactnent II of EPIP 1004.5, Comunications and Record-keeping).

4. Ensum that the Environnental Assessnent Communicator provides tN Near-Site Emegency Operations Facility with the proper radio communications.

5. Notify the Emergency Support Director and the Environnental Assess-nent Comand Center that the duties of the Assistant Environnental Coordinator have been assumed. (Fonvard this completed fom to tN Enemency Support Staff /Emegency Planning Coordinator).

HAffE DATE TIftE Assistant Envimnmental Assessment Coordinator O

Q)

FOR USE IN T1 NIT I ONLY

~

'FOR USE IN UNIT I ONLY 1004.22 j Rsvision 1 ATTACIO:E':T VI NEAR-SITE EMER(JNCY OPERATIONS FACILIIT F1MR PLAN Route 441 l I l u j *,

1. l E 8. l b

h l Table l ]h Table I

I 6.

1.

ei 10 1* ~

Tilu

Flic 3. bill l Table l T tivl , ,

tj 1.10. 7 AREAS:

A. E=ergency Support Director's Office gPrinter and Conference ,

E ** # -- - PHONE LINES:

B. Cc==unicator and liiiL ' 2. ! Ta'ol * ,, ,

1. Dimension Phone.

Assistants @- j ld

2. Operational Line.

C. NRC Representatives I i ' i~ 3. Radiological Line D. Parsippany Tech-

4. EACC Line.

1 'iviil g gg nical Support

- Grcup. 6. NRC ENS Line.

State and Cot.nty I =3 E. 7. Parsippany/TMI Representative. Table ' Line.

F. Public Affairs ^

8. E=ergency Directo Representative. D Hot line - Unit 1 G. E=ergency Plan- 4. 9. Emergency Directe

ning Represen-Hot line - Unit 2 tative/E=ergency - LO. Outside Lines (2)

Support Staff. ..

! H. .Envirceental/ _

h h i C

Portable Radio.

Chemistry Support i.: y i Groups.

! I. Emergency Support 3. !

Director's Desk.

J. Securi6y Guard. G briij STATUS BOA' DS: h F e, i 1. Rad!;he=.

Table

i 11. TMI Site .

iii. Plant Layout Sche =atic h

l iv. Offsite Organ-l ization 1 l

v. Equipment Status l ri. REMP map Ovii. Blank boards ,,

1 i e .

FOR USE IN y.Q1lT I ONLY y +-------em--- g .g ,r=> c ymeva ,_wg.

,-c -eri-- ,.v--a - , , , , -y -- ,- -,,-, - y -

..f.

FOR USE IN UNIT I ONLY 1004.29 ..

Revision 3 m 11/13/81 (y IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED CONTROLLED COPY FOR THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY IMPLEMENTING PROCEDURE 1004.29 ACTIVATION OF THE OPERATIONS SUPPORT CENTER Table of Effective Pages EN -< -[

f 6/

Page Revi sion Page pvision Page Revision Page Revision 1.0 3 2.0 3 3.0 3 4.0 3 5.0 3 O

Unit 1 Staff Recorrnends Approval Approval k Cognizant Dept. Head Date Unit 1 PORC Recocraends Approval i;

fl. (? / ! ?tL Date // 2 f/

Chairman of PORC Manager TMI I Approval

'N/ '

au Date // .3 /

f/

V QA Modifications / Operations Mgr

^

// h Date O-- Document ID: 0033W FOR USE IN UNIT I ONLY

"FOR USE IN UNIT l ONLY 1004.29 Revision 3 THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EERGENCY PLAN IELEENTING PROCEDURE 1004.29 ACTIVATION OF THE OPERATIONS SUPPORT CENTER 4

1.0 PURPOSE The purpose of this procedure is to provide guidelines for the Operations

Support Center Coordinator to activate the Operations Support Center.

The Operations Support Center Coordinator is responsible for implementing this procedure.

2.0 ATTACHENTS 2.1 Attachment I, Operations Support Center Floor Plan.

3.0 EE RGENCY ACTION LEVELS 3.1 This procedure is to be initiated upon declaration of any of the following:

3.1.1 Alert as determined by the Alert Procedure, 1004.2.

3.1.2 Site Emergency as determined by the Site Emergency procedure 1004.3.

3.1.3 General Emergency as determined by the General Emergency procedure, 1004.4.

3.1.4 As directed by the Emergency Director.

4.0 EERGENCY ACTIONS Initials 4 .1 The Operations Support Center Coordiutor will ensure completion of the following:

4.1.1 Activate the Maintenance and Instrument Phone Line (M and I) and obtain information pertaining to the emergency from the phonetalker in the Eri.ergency Control Center.

O 1.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT l ONLY 1004.29 Revision 3 4.1.2 Assign a phonetalker to man the M and 1 Phone Line and to Log all appropriate messages sent and received, on the Telephone Communications j Logsheet (Attachment III of.the Consnunications and Recordkeeping procedure, 1004.5).

4 4.1.3 Initiate and maintain log in accordance with Communications and Recordkeeping,' procedure 1004.5.

4.1.4 Establish muster points for personnel reparting to the Operations Support Center.

4.1;5 As directed by the Radiological Assessments

Coordinator / Operations Coordinator implement the following procedures

1 a. Onsite Monitoring 1004.10 l b. Offsite Monitoring l 1004.11

, c. Search and Rescue 1004.18

d. In Plant Radiological 1004.9 Controls During Emergencies

e. Any other procedure as directed by j the Radiological Assessment Coordinator / Operations Coordinator.

O i 2.0 l FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.29 Revision 3 4.1.6 If directed to dispatch monitoring teams, ensure vehicles are available at the processing center.

Obtain vehicle keys from:

a. Rad Con H. P. van

b. Maintenance I and C vehicle

c. Other vehicles as needed.

4.1.7 If accountability is being conducted, collect all security badges and turn them over to the Site Security Officer who will be dispatched to Dick them up.

) _____________-________________________________________________________

r : NOTE: All personnel must retain their keycards. :

4.1.8 Inform the Emergency Director, via the communicator, that the Operations Support Center is Operational.

5.0 FINAL CONDITIONS pitials 5.1 The Operations Support Center will be operational with muster areas established for duty section personnel and communications established on the Operational Line.

5.2 Duty section personnel are available for assignment as necessary.

O v

3.0 FOR USE IN UNIT I ONLY

'FOR USE IN UNIT I ONLY 1004.29 Revision 3 ATTACHENT I OPERATIONS SUPPORT CENTER OFFICE LAYOUT-HP

- To Turbine Bldg.

-y ' --- _

10 13 8

~

2 ,

j -

Health Physics

,j 3 offic, j

g l Fuel Handling and Auxiliary Building (br c l

) Access Control Point 3 .

6- :g 2 4 4 5 -

e 3

f7 11 g

,l &

s .

To Fuel Handlina i and Auxilia ry;

"" "9

Building 8 i

8 l

4 O

4.0 FOR USE IN UNIT I ONLY

~

' FOR USE IN UNIT I ONLY 1004.29 Revision 3 ATTACHENT I i OPERATIONS SUPPORT CENTER OFFICE LAYOUT-HP Key to OSC Equipment i

1. RM-14 with HP-210 Probe !

2. Table

{

3. Desk j

4. File Cabinets l

5. Storage Cabinet for Instrumentation

6. Status Boards

7. REMP Map

8. Cabinets

9. Plant Page Phone I

10. First Aid Cabinet

11. Emergency Locker (Flow diagrams, prints, etc.) l

12. High Rad area Key Locker

[

13. Xerox Copier

{

Equipment in Radio-Counting Room; f f

Ludium-2000 beta-gamma Counter-Scaler Wide-Beta l

Ortec beta-gamma Counter-Scaler !

i Tri-Carb Liquid Scintillation i Nuclear Measurements Corp. beta-gamma, alpha Counter-Scalers Stabilized Assay Meters O

5.0 FOR USE IN. UNIT I ONLY

"FOR USE IN UNIT I ONLY 1004.31 Revision 2 11/13/81

(.]m IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED CONTROLLED COPY FOR THREE MILE ISLAND NUCLEAR STATION SE IN UNIT I ONLY UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.31 AIRBORNE RADI0 ACTIVITY SAMPLIN'i AND ANALYSIS Table of Effective Pages l' b Page Revision Page Revi. ion Page Revision Page Revision 1.0 2 2.0 2 3.0 2 4.0 2 5.0 2 6.0 2 7.0 2 8.0 2 9.0 2 10.0 2 Unit 1 Staff Recommends Approval Approval // Date Cognizant Dept. Head Unit 1 PORC Recommends Approval

4 &O P H_ , Date ///IE */

Chairman of P0.4C Manager TMI I Appr al

($b W(/ '

/ W Date // 3 V

QA Modifications / Operations Mgr (N

q) [ Date Document ID: 0018W FOR USE IN UNIT I ONLY

'FOR USE IN UNIT I ONLY 1004.31 Revision 2 THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EKRGENCY IMPLEKNTING PROCEDURE 1004.31 AIRBORNE RADIOACTIVITY SAW LING AND ANALYSIS 1.0 PURPOSE The purpose of this procedure is to define the method of air sampling and analysis for Airborne Radioactivity in areas both in-plant and out-of-plant during an emergency.

The Radiological Assessment Coordinator is responsible for implementing this procedure.

2.0 ATTACHMENTS 2.1 Attachment I, Airborre Radioactivity Sampling and I-131 Analysis Data Sheet.

2.2 Attachment II, Iodine Air Sample Nomograph.

2.3 Attachment III, Particulate Air Sample Nomograph.

2.4 Attachment IV, Minimum Detectable Radiciodine Nomograph. !

3.0 EMERGENCY ACTION LEVELS 3.1 This procedure shall be implemented at any time during any class of declared emergency, when a potential or actual release of radio-activity to the environment exists; or 3.2 As directed by the Emergency Director, Radiological Assessment Coordinator or their designee.

4.0 EMERGENCY ACTIONS INITIALS 4.1 Emergency Equipment Required to be available for use:

4.1.1 SAM-II/RD19 Detector Probe 4.1.2 Radeco H-809 Air Sampler 4.1.3 Stopwatch O

1.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY

~

1004.31 Revision 2 4.1.4 GY-130 Silver Zeolite Cartridge 4.1.5 Particulate Filter 4.2 SAMPLE COLLECTION FOR OUT-0F-PLANT AREAS 4.2.1 For particulate and radiciodine sampling, insert an iodine cartridge (charcoal or silver zeolite) with

the arrow in the direction of air flow and partic-ulate filter in the Air Sampler unit holder with the

.i fibrous glass backing side of the particulate filter facing toward the sampler. The particulate filter must be apstream of the cartridge.

4.2.2 Wit. the filters in place, set the flow selector switch on the air sampler unit to variable and i adjust the flow so as not to exceed (2) CFM. Run the sampler unit for sufficient time to obtain a

minimum of ten (10) cubic feet. Record the sample 4

time and volume on the data sheet. Periodically check the air flow indicator while the sampler is

, running.

1 i

NOTE: A minimum of ten (10) cubic feet is required to :

i

obtain an MDA of IE-8 uCi/cc. The larger the :

l : sample, the lower the MDA will be. :

i l

I l

O 2.0 i FOR USE IN UNIT I ONLY l

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

FOR USE IN UNIT I ONLY 1004.31 Revision 2 4.2.3 To set up the Sam II, perform the following steps.

a. Check settings on the SAM-II unit to comply

. with the following table. Adjust settings as necessary:

SAM-II Operational Settings Channel 1 Channel 2

1. Threshold 3.44 3.44

2. Window 0.40 0.40

3. + of f- +

l off

4. in out in out

b. Adjust HV to 7.50

c. Set the Scaler display switch to "0N", Count (

Mode to "2", "XI", " timed".

NOTE: This will set the SAM-II for a 2 minute count. For :

high radioiodine sample count rates as indicated on :

the cou'it rate meter, lower counting times may :

be used. :

d. Connect the detector to the front panel of the SAM-II.

e. Turn the power switch "0N" and the stalnlizer "0N", and allow unit to stabilize for approxi-mately five (5) minutes.

3.0 FOR USE IN UNIT I ONLY

f FOR USE IN UNIT 1 ONLY 1004.31 i

Revision 2 4.3 SA>PLE ANALYSIS 4 4.3.1 Prior to counting the first sample, count a back-

, ground with the SAM-II in set-up mode as defined in i

step 4.2.3. Count background whenever radiological conditions have changed or are suspected to have

~

changed at the counting location. Count background i

i af ter changing locations.

3

NOTE: If the SAM-II unit is stable and not located in the :

plume or a high background area, the background count :

: should be less than 50 counts per minute. :

i 1

4.3.2 Label a coin envelope with the necessary informa-tion, i.e., date, time, volume, location, and person 4

taking sample. Then remove the sample cartridge and

particulate filter from the air sampler unit, separate the filter disc from the radioiodine cartridge and place the filter disc in the coin j envelope for later counting and analysis. Count and analyze in accordance with RCP 1605.

i i

NOTE: A more rapid determination of airborne particulate :

radioactivity may be made using the AIRBORNE :

i : PARTICULATE SAMPLE NOM 0 GRAPH, ATTACHENT III. :

4.3.3 Place the iodine cartridge in the SAM-Il shield chamber, and count the sample for two (2) minutes.

j a

(Or less if the high count rate is indicated for the sample. )

!. O-4.0

! FOR IJSE IN UNIT I ONLY

l 4

FOR USE IN UNIT I ONLY 1004.31 Revision 2

NOTE: If problems are encountered with the Sam II while ' :

counting, check the following: :

1. Power supply and connections. :

2. Physical damage and proper probe connections. :

3. Adjustments and settings per 4.2.3.a. :

i- : 4. Response to provided source. .

, 4.3.4 Record the serial number of the SAM-II, efficiency (as indicated on the SAM-II), background count rate, and count time on the sample data sheet. (Att. 1),

4.3.5 Af ter counting sample, record the iodine sample counts and counting time on the data sheet.

4.3.6 Calculate the radioiodine activity by use of the 1

data sheet or nomograph. If the gross count rate of l the sample is low, (less than 2 X background) calculate the Minimum Detectable Count Rate (MDCR).

If the MDCR is greater than the san.ple count rate, use the MDCR for activity calculations and report the measured activity as less than this activity.

POA for radioiodine samples may also be obtained by use of the Minimum Detectable Radioiodine Activity I

Nomograph (Att. IV).

4

NOTE: Analysis of all samples may be performed by use of I :

the TMI Unit 1 GeLi/MCA system in accordance with :

SCP 1958.3, the TMI-Unit 2 GeLi/MCA unit, or the : I

GeLi/MCA unit operated by the Environmental

Assessment Section. *

NOTE: A more rapid determination of radiof odine concen- :

tration may be made using the AIRBORNE I0 DINE SAWLE :

NOM 0 GRAPH, ATTACHIENT II . :

5.0 FOR USE IN UNIT I ONLY i

FOR USE IN UNIT I ONLY 1004.31 Revision 2 4.3.7 For dose calculations due to off-site radioactive releases, refer to EPIP 1004.7.

NOTE: If during sample analysis, the sample activity :

exceeds the ability of the instrument being used, :

(i.e., high count rate), one or all of the following :

4

alternatives may be used as directed by the RAC: :

a. Reduce the sample volume :

b. Utilize different counting geometries :

c. Utilize counting instrumentation with lower :

efficiency / sensitivity :

4.3.8 Place all samples in separate plastic bags and label the samples with sample date, time, location and calculated activity and return all samples taken to the OSC and give to the Rad Con Coordinator.

4.4 In-Plant air sampling for Radioactive Gas shall be performed in !

a

) accordance with RCP 1607. with care to problems expressed in the note below 4.3.7.

4.5 In_ Plant air sampling for Radioactive Iodine shall be performed in l accordance with RCP 1605 with care to problems expressed in the note below 4.3.7.

NOTE: A more rapid determination of radioiodine concen- :

tration may be made using the AIRBORNE IODINE SAMPLE :

NOM 0 GRAPH, ATTACHENT II . :

4.6 In-Plant air sampling for Radioactive Particulates shall be per- l formed in accordance with RCP 1605 with care to problems expressed in 4.3.7.

NOTE: A more rapid determination of airborne particulate :

radioactivity may be made using the AIRBORNE PARTIC- :

ULATE SAFPLE NOM 0 GRAPH, ATTACHENT III. :

60 FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.31 Revision 2 4.7 All air samples shall be handled in accordance with RCP 1605.1.

4.8 Post accident sampling of reactor containment air shall be per-formed in accordance with RCP 1631. Special consideration should be given to the potential for very high radiation and contamination levels of samples and sampling equipment.

CAUTION: Obtaining a reactor containment atmospheric sample :

after an accident may involve high levels of gaseous :

and particulate activity. Special precautions as :

outlined in EPIP 1004.9 should be observed. :

5.0 FINAL CONDITIONS 5.1 All samples taken after release has been terminated.

5.2 All monitoring teams ordered to return to base.

5.3 All samples given to radiological controls for analysis. !

O d

O 7.0 FOR USE IN UNIT 1 ONLY

'FOR USE IN UNIT I ONLY 1004.31 Revision 2

()

r~s AIRBORNE RADIOACTIVITY SAFPLING AND I0 DINE - 131 ANALYSIS DATA SHEET ATTACHENT I

- Sample Collection Iodine Sample Counting

1) Time on , Time off 1) Serial No. of SAM-II Run Time min.

2) Sample Flow CFM, 2) Efficiency

3) Volume = min x CFM 3) Background counts (1) T2T

4) Background count time min x 2.832 x E 4 cc/ft3= cc

5) Background count rate-

4) Location: min = cpm (3) (4)

5) Date: 6) Sample Counts

6) Time: 7) Sample Count Time min.

n 7) Sampler Type: 8) Sample Count Rate =

() Serial No.: min = cpm (6) (7)

8) Collected by: 9) Sample Net Count Rate (Net CPM)

- = cpm Sample (B) Bkgd(5)

10) Date and Time of Counting:

11) Counted by:

'odine Activity = Net CPM =

uCi/cc (Vol) (Eff) (2.22 E6)

CPM

uCi/cc

( cc) ( ) (2.22 E6)

MDCR = 3.3 x VBkgd. Count Rate (NOTE: This is for 95 percent Confidence Level and is valid only if Bkgd Count Time and Sample Count Time both equal 2 minutes).

= 3.3 x V CPM = CPM 8.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY

~

ATTACHMENT II 1004.31 Net CPM TODIE ATR SAMPLE NOMOCPApu Revision 2 (N oss CPM-Bkg. CFM)

Note: This nomograph is to be used for Iodine 131 10- air samples counted with a SAM II. This nomograph g

assumes an ave. counter factor of 7800 for SAM II's.

B I I31 Aig Sample Volume Airborne Activity (Ft ) (ml or cc) ("

-9 Yk-5 s

-7 40~

-1E3 ~*

-s

-2E3 -4 70- .1-.

4E3 -3 100-- *24

.~:-7E3 3

,4. -1E4 200_ ,' - 2E4

1. 00-

-i E-6

-4 E4

- 9, 400 - h7E4 -7

-lES ~*

4 . 0- -3 700 -

7.0$-2E5 4 10 :.

4E5 -3 x 1000- 20 7E5 y 40 --lE6 2000_ 70 k - 2E6 1004 - -' E-7

-9

-s 4000 [#,

-s 7000 ," "'

-3 10000J

-2 20000 ,

t E-8

, Instructions: Draw a line through Net CPM (A) 40000 - and Air Sag {e Volume (B) using a straight edge -7 and read I Airborne A:tivity (C) on the line. -6

-s

~'

70000l

_3 100000 ;

-2 0

-i E-9 FOR USE IN Q. WIT I ONLY i

8

~

' 'FOR USE IN UNITdreNinY

^ AIRBORNE PARTICULATE SAMPLE NOM 0 GRAPH C gns ah NET CPM Note: '"his nc=ograph is :0 be Airborne A :1vity (Gross ;P_w.-Skg. CPM) used for par:1cula:e air sa=ples (uC1/=1) counted with an RM-ll./EP-110

.L io Se:a-Ga==a Coun: Rate Meter. 'l. . . . . . .

This no=ograph assu=es a counting {3s efficiency of 15%. *7

+ 15 14

. . t.

ir -

. .). 3 <

1 Air Sa=ple Volu=e

..e

, ,1 fa d 5, (=1 or cc) (Ft3) , , ,, f I

au

.l ee

.1me

.a - .as . i.es*'

1 49 d6 3

. O.L al. ?

Ito I I n o'.

.(

, o..,

g [10 t

z. .. e., ""

,m I*

.5

. s..

z. . . .s su.r, p& 7"

. saa t

~ 4.o . . s.t i

y s.o .

- - 1.*

.sw . 10 . . i s to ,

..eo < .q

.p

. Le 1y Lasoo $6

. I sla'=

.y. <

t

..too.

to .. Se *"

3, J**

.3 ye.

.., l i

s. .- 6L I s I o' .

f. ... . , ,

bf js...

p l.

. ,.0 7i T*

,,,,,,, tiSTR!;C"' IONS : Draw a line thre:gh Net [7.

C?M (A) and air sa=ple volu=e (3) using

.w a straight edge and read airborne ac- lf tivity (C) en the line. l

-t

.l .

l t

FOR USE IN UN1T I ONLY i 1

- _ . .- -. .- . . . . - -.

ML20039B019

Contents

Text

Description:

Description:

CPM

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