ML20028D726

Public Version of Revised Emergency Plan Implementing Procedures EPIP-07 Re Personnel injury,EPIP-09 Re Offsite Dose Projections & EPIP-22 Re Search & Rescue Operations

ML20028D726
Person / Time
Site:	Oyster Creek
Issue date:	12/22/1982
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20028D722	List: ML20028D725 ML20028D726
References
PROC-821222-01, NUDOCS 8301190383
Download: ML20028D726 (48)

Text

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12/22/82 Page 1 of 2 0

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f f EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX l .

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1 EPIP TITLE LISTING

'I EMERGENCY PLAN IMPLEMENTING PROCEDURES I

i LAST LAST l PROCEDURE NO. TITLE REV. NO. REV. DATE

, EPIP - 01 Classification of Emergency Conditions 3 07/20/82 i - EPIP - 02 Unusual Event 3 07/20/82

! EPIP - 03 Alert 3 07/21/82 1 EPIP - 04 Site Emergency 3 07/21/82 EPIP - 05 General Emergency 3 07/21/82 i EPIP - 06 .%t Issued 4 -EPIP - 07 Personnel Injury 2 11/02/82 .

i EPIP - 08 ~ Fire 1 02/10/82 i EPIP - 09 Offsite Oose Assessment 2 11/02/82 1 EPIP - 10 Emergency Radiological Survey - Onsite 1 09/23/82 l EPIP - 11 Emergency Radiological Survey - Offsite 1 03/04/82 i

EPIP - 12 Personnel Accountability 2 01/27/82

-l EPIP - 13 Site Evacuation and t Personnel Accountability After Site

Evacuation 1 02/17/82 ll EPIP - 14 Damage Control 1 03/04/82 i; EPIP - 15 Toxic / Flammable Gas Release 1 02/10/82 EPIP - 16 Radioactive Liquid Release Delete EPIP - 17 Activation of the Parsippany Technical Functions Center 0 02/26/82 l! EPIP - 18 Activation of the Remote Assembly Area 0 02/23/81 EFIP - 19 Emergency Dosimetry 1 02/17/82

[i EPIP - 20 Tornado /High Winds Delete l }'

l EPIP - 21 Personnel Decontamination 1 02/19/82

- EPIP - 22 Search and Rescue Operations 1 11/02/82 EPIP - 23 Thyroid Blocking 1 02/19/82 EPIP - 24 Emergency Respiratory l .

Equipment 0 02/19/82 EPIP - 25 Activation of the Nearsite Emergency j Operations Facility 1 09/23/82 i

EPIP - 26 Activation of the Technical Support Center 0 02/24/81 EPIP - 27 Activation of the Operations Support Center 0 02/24/81 l EPIP - 28 Activation of the Farsite Emergency j Operations Facility 0 02/24/81

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EPIP - 29 Recovery Operations 1 03/04/82

EPIP - 30 Post Accident In-Plant Radiation Measurement 0 09/23/82 j All EPAP's have been deleted 12/14/82

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Jgggy Cer) tral 02/19/81 (12/06/82) 12/16/82 Power & Light Company Revision No. Cate

,g Sucject Personnel Injury Autncnzsc Sy Director-Station Operations 3 ApprCvauCcacuffenc8 /1 Project Ovster Creek Nuclear Ceneratine Station

, LIST OF EFFECTIVE PAGES DATE REVISION NUMBER i

1 11/02/82 2 2 11/02/82 2 3 11/02/82 2

4 11/02/82 2 ~

5 11/02/82 2 6 11/02/.92 2-l 7 11/02/82 2

8 11/02/82 2 9 11/02/82 2

, 10 11/02/82 2 11 11/02/82 2 12 11/02/82 2 13 11/02/82 2 14 11/02/82 2 ATTACHMENT t For:n 7-1 (1 page) 11/02/82 2 l1 i

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1.0 I'URPOSE

1 This procedure provides the instructions necessary to assure prompt medical care is previded injured persons with contaminated minor or major injuries. Additionally, it provides guidance regarding the handling of t

contaminated or non-contaminated injured personnel and the methods used to prevent the unnecessary spread of contamination to areas such as an ambulance interior or a hospital.

2.0 ACTION LEVEL REFERENCES 2.1 EPIP-2, Unusual Event 2.2 EPIP-3, Alert 2.3 EPIP-4, Site Emergency i 2.4 EPIP-5, General Emergency ,

3.0 RESPONSIBILITIES l 3.1 The Emergency Director is responsible to ensure that injured persons

] receive medical treatment and if necessary transport to a medical facility. When the Operations Support Center is activated, the Operations Support Coordinator will normally be the designee for this procedure.

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', 3.2 The Emergency Director or his designee shall insure that the attached check list is completed and the information contained on the list is j' communicated to the appropriate agencies.

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!, 3.3 The Emergency Director and/o- the responsible physician will notify Radiation Management Corporation if he determines that the contaminated, injured situation exceeds the handling capability of the plant or supporting hospital (Consnunity Memorial Hospital) .

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'l i 4.0 PREREQUISITES j -

I 4.1 Wear proper protective clothing as directed by Radiological Controls.

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l 4.2 Use proper respiratory protective devices as directed by Radiological i

j Co ntrols.

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1 4.3 Wear proper dosimetry as directed by Radiological Controls.

.j 4.4 Radiation exposu,re to individuals exceeding 10 CFR 20 limits is i

! restricted as follows:

{ EMERGENCY EXPOSURE LIMITS PROTECTIVE OR LIFE SAVING

., ORGAN CORRECTIVE ACTIONS ACTIONS

[ Whole Body 25 Rem 75 Rem 1

Extremitie s 100 Res 300 Ram Thyroid 125 Ram No limit

4.5 Women capable of reproduction should not take part in a'etions 1

', requiring emergency exposure.

4.6 Emergency exposures for volunteerr. must be author!. zed by the

{ Emergency Director. This responsibility may not be delegated.

4.7 All exposures will be maintained ALARA.

, 5.0 REQUIREMENTS l

1 5.1 Initiating Conditions j Personnel injury may occur in any class of ersrgency (i.e., Unusual

} Event, Ale rt , Site Emergency, or General Emergency). The offsite ,

i transport of a contaminated or potentially contaminated injured

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'I person is an emergency action level that should initiate the Unusual I l Eveet class. A contaminated injured person provided medical care at j Oyster Creek Nuclear Generating Station and not transported to an 1

! offsite medical facility does not initiate an Unusual Event i'

classification.

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, Personnel Injury EPIP-7 Pete 4 ef 14 Empe Monmon Na 0*

2 11/02/82 5.2 Immediate Notifications ~

. 5.2.1 Immediately upon being aware that an injury has occurred, j the injured (if the wound is minor), or someone else in the 4

area, shall contact the Control Room and report the i

i occurrence.

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5.3 Evaluation of Injury

} 5.3.1 The Emergency Director or his designee will dispatch a t

member of the plant shif t trained in first aid and a

<j qualified Radiological Controls Technician to the injured person's location.

i 5.3.2 Based upon the First Aid Team observations of the injury, the Emergency Lirector or his designee will declare the

)) injury to be a Minor injury (treatable on site) or a Major injury (transportable).

5.3.3 If the injury occurred in a Radiation Work Permit area and appears to be minor in extent, the injured person should j leave the area or be removed, as appropriate. Remove any protective clothing worn and frisk prior (as soon as

,! possible) to departing the Radiation Work Permit area.

li 1 5.3.4 If the injury is judged to be a minor injury with l

contamination, the Emergency Director or his designee shall give instructions for the injured to be escorted to the

I plant personnel decontamination area.

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5.3.5 If the injury is judged to be a, Minor injury (treatable on site), proceed in accordance with paragraph 5.4 of this

{ p rocedure.

j 5.3.6 If the injury is judged to be a Major injury

.; (transferable), further disposition shall proceed in accoedance with paragraph 5.5 of this procedure.

, 5.4 Minor Injury e

5.4.1 If the injury ijt an open wound, proceed as follows: [If l the injury is not an open wound (such as, a shallow cut or I

j puncture), proceed to paragraph 5.5.2 of this procedure.]

5.4.1.1 Decontamination of open wounds shall be performed in the presence of nedical personnel. Cover the

wound and decorcaninate the surrounding area with

.j Betadine Scrub..

1 I 5.4.1.2 Uncover the wound and flush the wound using I

sterile water (if available) for at least two ninutes in the Monitor & Change Room sink.

5.3.1.3 If a specific object caused the wound, the object should be surveyed for contamination by Radiological Controls. .

l 5.4.1.4 Af ter the wound has been flushed, carefully blot dry the wound and surrounding skin area using i

sterile, absorbent material.

5.4.1.5 Survey the wound and the surrounding skin area i

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. using a thin window GM detector (such as the

, HP-210).

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5.4.1.6 If contamination leve,ls in or around the wound do not exceed 100 cpm above background, administer necessary first aid to treat the wound.

fl 5.4.1.7 If contamination levels in. or around the wound l

j exceed 100 cpm above background, proceed as follows:

t 4 o Use betadine scrub.

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, o Dip a cotton swab in the betadine scrub and

'l rub a small area of the skin immediately

'l surrounding the wound, using a motion which l starts by placing the cotton swab at the edge of the wound and then moves away from

{ the wound (do not rub towards the wound).

i j Use as many swabs as necessary to clean an I

l area 1-1/2" wide around the wound.

l-o Moisten a swab in sterile water if 1

available, and rinse the detergent from the l

j skin surrounding the wound, using the same 1

1 motion as that used for applying the betadine scrub. Use as many swabs as necessary until the skin is completely rinsed.

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, o Blot the skin dry using sterile, absorbent mat e rial.

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2 "'" 11/02/82 j 5.4.1.8 Survey the wound and , surrounding area using a i

l thin window GM detector. If contamination levels

, in or around the wound do not exceed 100 cpm I

j above background, administer necessary first aid I .

f to treat the wound.

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'I 5.4.1.9 Document on a Personnel Contaaination Report form any decontamination performed. (Form No.1556R)

,; 5.4.1.10 Af ter reasonable decontamination attempts are unsuccessful and the injury requires medical evacuation, che Emergency Director may authorize offsite transport of the contaminated injured person. The Energency Director or his designee will actify Community Memorial Hospital, Telephone (201) 349-8000, that a person with a 3

contaminated minor injury is being transported to

, the hospital.

{ 5.4.1.11 The Emergency Director or his designee shall make the necessary arrangements for transportation.

5.4.1.12 The Emergency Director or his designee will assign a qualified Radiological Controls i

Technician to accompany injured persons transported to offsite medical facilities. The

+ l escort will perform duties listed in paragraph

, 5.6 o f this procedure.

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2 11/02/82 f 5.4.2 If the injury is not an open wound, proceed as follows:

i l 5.4.2.1 Perform a complete body survey using a thin t

I window GM detector.

.1 1 5.4.2.2 If contamination levels on the skin in the area of the injury and on the remainder of' the body do f

not exceed 100 cpm above background, administer

'! necessary firs t aid to treat the injury.

'I 5.4.2.3 If contamination levels on the skin in the area

-) of the injury and/or on the remainder of the body

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! exceed 100 cpm .etove background, decontaminate in accordance with EPIP-21. Document the i

decontamination on a Personnel Contamination i

l Report Form. (Form No.1556R)

5.4.2.4 If the skin in the area of the injury is.

I' Ii contaminated and if decontamination is 1k

!, successful, administer neces'sary first aid to treat the injury.

5.4.2.5 If the skin in the area of the injury is contaminated and if decontamination is unsuccessful, notify the Emergency Director or his designee.

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> 5.4.2.6 Af ter reasonable deco,ntamination attempts are l

unsuccessful and the injury requires medical i evacuation, the Emergency Director may authorize ,

j offsite transport of the contaminated injured i perso n. The Emergency Director or his designee will notify Community Memorial Hospital,

Telepheue (201) 349-8000, that a person with a contaminated minor injury is being transported to the hospital.

l 5.4.2.7 The Emergency Director or his designee shall make the necessary arrangements for transporation.

5.4.2.8 The Emergency Director or his designee will assign a qualified Radiolo.gical Controls Technician to accompany injured persons transported to of fsite medical facilities. The escort will perform duties listed in paragraph 5.6 of this procedure.

5.5 Major Injury 5.5.1 The Emergency Director or his designee shall notify first aid and rescue personnel:

5.5.1.l' Notify the Lacey First Aid Squad, Telephone (609) 693-6636 to arrange for transportation.

5.5.1.2 on-Site Medical Department Wor M ll 5.5.1.3 Site Protection Sergeant 1]lll[or]lll[

5.5.1.4 Shif t Radiological Controls Technician 4660 or

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5.5.2 Upon arrival at the scene, the First Aid Team leader or designee will establish communications with the Energency Director and apprise him of the nature and severity of the injury.

5.5.3 The First Aid Team will administer first aid to'the injured person in accordance with established medical prac,tices.

5.5.4 If the injured is located in a radiological control area and the person's condition permits, move the injured (a stretcher may be required) to minimize radiation exposure and/or contamination to the injured and First Aid Team members. When making decisions concerning the disposition of the injured, the injured's well-being and need for

. medical attention shall always take precedence over.

decontamination efforts.

5.5.5 Survey the injured person for contamination. (If the

( injured person is wearing protective clothing and his condition permits, remove the clothing prior to performing this survey). Do not delay transport in order to perform survey or decontamination.

5.5.6 If contamination levels on the injured person exceed 100 cpm (using a thin window GM detector), proceed as follows:

o The Dnergency Director or his designee shall notify Community Memorial Hospital, Telephone (201) 349-8000, that a person with a contaminated injury is being transported to the hospital (describe the injury).

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Personnel Injury EPIP-7 Arge 11 cf 14 Seges Mensson No. 2 0811/02/82 o Notify the Security Department (Telephon6

, that an ambulance is enroute to the plant. When it arrives, permit entry of the ambulance and attendants and escort it to the building entry closest to the injured person. Issue dosimetry in accordance with Procedure 906.6.

o The Emergency Director or designee will assign a qualified Radiological Controls Technician to accompany injured persons transported to offsite

• , medical facilities. The escort will perform duties listed in paragraph 5.6 of this procedure.

5.5.7 If contamination levels are less than 10') cpm proceed as follows:

l 5.5.7.1 The Emergency Director or his designee shall notify the Community Memorial Hospital, Telephone, (201) 349-8000, that a person with a

. major injury is being transported to the hospital (describe the injury).

5.5.7.2 Notify the Security Department that an ambulance is enroute to the plant. When it arrives, permit immediate entry of the ambulance and attendants, and escort it to the building entry closest to the injured person. Issue dosimetry in accordance with Procedure 906.6.

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, haiect: hocoewe Na Personnel Lajury EPIP-7 Psga 12 of 14 mens Monmon N" 2 08 11/02/82 5.5.7.3 The Emergency Director or designee will assign a

qualified Radiological Controls Technicia 1 to accompany injured persons transported to of fsite medical facilities. The escort will perform duties listed in paragraph 5.6 of this procedure.

5.6 Of fsite Medical Escort Responsibilities, 5.6.1 The Escort assigned by the Emergency Director or designee to ride in the ambulance is responsible (do not delay transport to accomplish these items) to:

5.6.1.1 Issue each ambulance attendant protective clothing (as appropriate) .

5.6.1.2 Take steps (as appropriate) to protect the ambulance interior from contamination (such as by ,

the use of plastic sheeting).

5.6.1.3 If appropriate, check the hospital to ensure that l proper steps have been taken to nininize the potent'al for contamination of tha hospital, such as paper on the floor, etc.

5.6.1.4 Issue a TLD and a dosimeter to each medical person who will be near the injured (if 300 mrem exposure is likely to be received) . (Plant Procedure 906.6)

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" " ' 2 *** 11/02/82 5.6.1.5 Survey the ambulance attendants and the vehicle interior for contamination.

o If contamination on the attendants is detected in excess of.100 cpm above background, decontamination should be performed at the hospital. If the attendants are not contaminated, or af ter decontamination, collect all TLD's and dosimeters from the attendants, obtain the necessary data for the TLD Issue Sheet and release the attendants. Document the results of the contamination survey.

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o If contamination inside the ambulance is detected in excess of 100 cpm above background and it cannot be decontaminated at that location, contact the Radiation Protection Coordinatorm for assistance.

If th~e ambulance is not contaminated, or after decontamination, release it. Document the results of the contamination survey.

5.6.1.6 Survey the hospital receiving and treatment areas. If contamination in any of those areas is 1

detected in excess of 100 cpm above background, decontaminate the areas. Document the results of the contamination survey, before and after decontamination.

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2 c" 11/02/82 5.6.1.7 Collect any protective clothing used and any potentially contamintted materials and transport them back to the plant.

5.6.1.8 Record the results of each. survey performed and deliver a copy to the Emergency Director.

5.6.1.9 , Recover victim's dosimetry for evaluation.

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• 2 Co:e 11/02/82 Form 7-1 DOCUMENTATION CHECKLIST TIME / INITIALS

/ Injured person report received.

/ Shif t member (trained in first aid) and Radiological Control Technician dispatched to injured person's 1ccation.

/ On site medical department notified Telephone W or M

/ RMC notified.

/ Offsite assistance requested (as required)

/ o Lacey First Aid Squad notified Telephone (609) 693-6636

' Notify Oyster Creek Nuclear Generating Station Security Department if offsite medical assistance has been requested.

/ Telephone W or 6 o Community Memorial Hospital notified, l, Telephone (201) 349-8000, and provided i

/ with the following information:

INJURY Ma jor Minor Life Threatening Non-Life Threatening Co ntaminated No n-Co ntaminated High Imvel Radiation Iow Level Radiation Number of Patients RfC Notified RMC Not No,tified Transportation Used:

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,i Pa tient's Name/Tiele:

l Who is with patient:

Titie:

1 Description of Injury:

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2mm (12/17/s23 12/27/82 Power &-Light Company Revisica No. Cate

/2/82 Subj*M- of fsite Dose Projections Autncnzsc Sy Director-Station Operations ApprovGCQnCUINnC* -

, y 1n_1 Project Oyster Creek Nucleai- Generating Station LIST OF EFFECTIVE PAGES DATE -

REVISION NUMBER 1 11/2/82 2 2 11/2/82 2 3* 11/2/82 2 4 11/2/82 2 5 11/2/82 2

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6 11/2/82 2 7 11/2/82 2 8 11/2/82 . 2 9 11/2/82 2 10 11/2/82 2 11 11/2/82 2 12 11/2/82 2 '

13 11/2/82 2 ATTACHMENTS Attachment 1 (2 pages) 11/2/82 2 Attachment 2 (1 page) 11/2/82 2 Attachment 3 (3 pages) 11/2/82 2 FORMS i

Fom EPIP 9-1 (1 page) 11/2/82 2 l Fom EPIP 9-2 (2 pages) 11/2/82 2 l

Fom EPIP 9-3 (1 page) 11/2/82 2 Fom EPIP 9-4 (1 page) 11/2/82 2 l Psm EPIP 9-5 (1 page) 11/2/82 2 l

l NON-CONTROLLED This Document will Not Be Kept Up To Date

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. 1.0 PURPOSE The purpose of this procedure is to provide:

1.1 Techniques and methods for calculating projected doses (whole body and child thyroid) which might result from airborne releases of radioactive materials from OCNGS. ~

1.2 Documentation and accountabilley,1f 10 CPR 20, Appendix B, Table II, Column 2 concentrations for liquid effluents have been exceeded in the discharge canal initiating an Unusual Event emergency classification.

2.0 REFERENCES

2.1 EP IP-2 Unusual Event 2.2 EPIP-3 Alert

( 2.3 EPIP-4 Site Emergency 2.4 EPIP-5 General Emergency 3.0 RESPONSIBILITIES 3.1 The Shift Radiological Controls Technician *.ill be responsible for implamentation of this procedure until activation of the Environmental Assessment Command Center.

4.0 PREREQUISITES t

! 4.1 No ne 5.0 REQUIREMENTS 5.1 Airborne Releases

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5.1.1 Obtain meteorological parameters from Coutrol Room instrumentation located on the rignt of Panel 13R. Update meteorology approximately every fifteen minutes.

NOTE: Of fsite organizations for meteorological data l are:

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( Department of the Air Force Department of the Navy 609-724-3568/3994 201-323-2334 5.1.1.1 Obtain vind direction (*) from chart recorder and record on Form 'EPIP 9-1 (wind is from this direction) .

[

5.1.1.2 Calculate converted downwind value by the following ' equations and record on Form EPIP 9-1.

5.1.1.2.1 If wind direction value from 5.1.1.1 is between O' - 180*, then:

1 (wind direction ( *) + 180*) =

t converted downwind value ( *)

5.1.1.2.2 If wind direction value from 5.1.1.1 is between 181* - 3 60*, ; hen:

i (wind direction ( *) - 180*) =

. converted downwind value ( *)

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of fsite Dose Projections EPIP-9 P59e 4 of 13 pe;es 2 *** 11/2/82 5.1.1.3 Determine affected sector based on converted downwind direction using the following table:

Affected Sector Converted Downwind Direction (*) Compass Point 349 to 0, O to 11 N 11 to 34 NNE 34 to 56 NE 56 to 79 ENE 79 to 101 E 101 to 124 ESE 124 to 146 SE 146 t o 169 SSE 169 to 191 . S 191 to 214 SSW 214 to 237 SW 237 cc 259 WSW 259 to 231 W 281 to 304 WNW 304 to 326 NW 326 to 349 NW .,

. Record affected sector (compass point) on Form EPIP 9-1 and Fcrm EPIP 9-4.

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$.1.1.4 Obtain At (temperature differential) between 380

, f t. and 3 3 f t. elevation of meteorological tower and record on Attachment. l.

5.1.1.5 Determine stability class from 4 t(*),

referencing the following graph and constraints UNSTABLE NEUTRAL STABLE I I I 6

-4.0 -3.0 -2.0 -1.0

-3.3 +(*F) -1.1 e If at is between (-3.3*F and -1.1*F) condition is i NEUTRAL.

e If at is 4. (-3.3*F) condition is UNSTABLE.

e If 6t is > (-1.l*F) condition is STABLE.

Record stability class on Form EPIP 9-1 and Form EPIP 9-4. Also, record on Form EPIP 9-2 for design basis accident dose projection,1f applicable.

l' 5.1.1.6 Obtain wind speed in mph. Calculate windspeed in m/sec.

sph I 0.45 m/sec = m/sec.

nph .

Record results on Form EPIP 9-1 and Form EPIP 9-4. Also, record on Form EPIP 9-2 for design basis accident dose projection,1f applicable.

Communicate windspeed (mph), converted downwind value, stability class and affected sector to the Emergency Director.

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of 13 Peges Monsion. Ma. 2 core 11/2/82 5.2. Design Basis Accidents - Inir.ial Do'se Assessment.

- 5.2.1. The following are FDSAR referenced design basis accidents:

- Refueling accident

- Control rod drop accident

- Ioss of coolant inside drywell

- Steam line break outside reactor building Upon assessment of' a design basis ac'cident by the Emergency Director, utilize Form EPIP 9-2,

" Postulated Offsit'e Doses from Design Basis Accidents". De termine dose in REM for the current stability class and windspeed as decennined from Page 1, Form EPIP 9-2, for Design Basis Accidents.

Basis Dose (Rem) = Dose (Rem) for 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> release Windspeed (:n/sec)

, 5.2.2 Record results on Form EPIP 9-2, Page 2 and communicate to Dnergency Director.

l 5.2.3 Perform further dose projections utilizing Sections 5.3 through 5.6.

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l; 5.3 Determine the source strength for an elevated release. Record i

! data and results on Form EPIP 9-3. .

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5.3.1 Obtain stack gas monitor value from Panel 10F, Channel A or B in counts /sec.

NOTE: If stack gas monitor is offscale, notify Radiation Controls to dispatch a technician to the downwind 0.25 mile location c3 obtain dose rate. Proceed to Section 5.7 to project source strength from dose rate.

5.3.2 On Form EPIP 9-3, circle each ventilation system that is operating (as verified by red light indication on Panel 11R) and sum to obtain total stack flow.

NOTE: "New" Radwaste ventilation flow can be verified by contacting the New Radwaste Contro1 Room.

L  !

5.3.3 Obtain conversion factor for uCi/see per count /see in

! Channe1 A or B from Pane 1 10F.

NCYrE: Use same Channel (A and B) for conversion factor utilized for stack gas monitor value.

5.3.4 Determine the stack correction factor from the Craph on Panel 10F as a function of total stack flow.

5.3.5 Calculate the source strength in ci/sec based on the formula: ' -

(Stack Monitor counts /sec) (Conversion Factor uCi/see) (1.0.E-06 Ci) Ci count /sec uCi = sec (Stack Correction Factor) 5.4 Determine the source strength for a ground release. Record

( data and results on Form EPIP 9-3.

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5.4.1 ~ Calculate source strength based on the formula:

, Air Sample Activity X Release Rate X Conversion Factor = Source Strength 3

uCi X ft X 4.7 2E-04 = Ci/sec cc min where: uCi/cc = Air concentration in source of release as detarmined by Radiation Controls Dept.

f t 3/ min = Release Rate as assessed by the Emergency Director or his designee 4.7 2E-04 = 2.832E+04 cc X 1 min X 1.0E-06' i E3 60 see uE NOTE: If air concentration and/or release rate are unavailable, notify Radiation Controls to dispatch a technician to the downwind 0.25 mile location to obtain dose rate.

Proceed to Section 5.7 to project source strength from dose rate.

5.5 Project offsite dose race from source strength data. Record data and results on Form EPIP 9-4.

5.5.1 Record type of release 'E' for elevated (stack release), 'G' for ground.

5.5.2 Eater 'l' in "s ource s trength method" column to indicate that source strength was determined fro:

j plant parameters.

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" "" 2 11/2/82 5.5.3 Calculate whole body dose race. Initially, project dose rate at 0.25, 2, 5, and 10 miles downwind based on the formula:

Dilution Factor I 1 X Source Strength X Dose Factor = ' Dose Rate windspeed

-1 .

Xu (m-2) X 1 (m/sec) X Ci X mrem /h r = mrem Q u sE C1/mJ hr where: Xu = Atmospheric Dilution Factor from Attachment 1 Q based on type of release, stability class, and l downwind distance.

1 = Inverse of windspeed in (meters /sec)~1 I

• Y Windspeed obtained from Form EPIP 9-1.

E = Source Strength determined on Form EPIP 9-3.

see mrem /hr = Whole Body Dose Factor from Attachment 2 as a l C1/mJ function of time af ter shutdown. Obtain t13e

. after shutdown from Emergency Direct.cr or his designee.

5.5.4 Project integrated whole body dose from the formula:

Dose rate X estimated duration of release =

integrated dose mrem I hr = mrem hr where: mrem = whole body dose rate at downwind distance hr

! hr = duration of release as estimated by'the.

Emergency Director or his designee. default value = two hours.

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5.5.5 Obtain integrated child thyroid dose by referencing Attachment 3, comparing whole body dose rate to projected exposure time (default value = two hours).

Calculate child thyroid dose rate by dividing integrated child thyroid dose by projected exposure time to obtain Rem /hr.

5.5.6 Calculate " time to reach PAG" (Protective Action Guides-EPA-520) for whole body dose rats and child thyroid dose rate by the formulae:

Whole body " time to reach PAG" (hr.) = 1000 mrem /whole body dose rate (mrem /hr)

Chil'd thyroid " time to reach PAG" (hr. ) = 5 Rem / Child thyroid dose rate (Rem /hr) k 5.5.7 Once all data and calculations are recorded on Form i

EPIP 9-4, communicate results to Emergency Director.

Provide the noble gas release rate (Ci/sec),

estinsted duration of release (hr.), whole body dose i

rate (mrem /hr) and integrated dose (mrem), child thyroid integrated dose (rea) and iodine

' concentration (uci/cc) for site boundary (0.25 mile),

2 mile, 5 mile, and 10 mile downwind locations.

5.6 If applicable, calculate integrated whole body dose and child' thyroid dose from offsite monitoring data on Form EPIP 9-5.

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hotocr: P.eceewe Ne, Offsite Dose Projections EPIP-9 Page 11of 13 Sepm b" " 2 Cam 11/2/82

. 5.6.1 Obtain dose rate net counts per minutes (NCPM) and scaler ef ficiency from monitoring team. Calculate air concentration in uCi/cc by the formala:

uCi s NCPM x 7.5E-11 cc  % Efficiency where: 7.5E-11 = 4.5E-07 uC1/dpm x 100 %

6.0E + 5 cc 5.6.2 Record monitoring location and azimuth - distance (degrees - miles) as determined from EPIP-11, Attachment 1.

5.6.3 Compare air concentration to projected exposure time on Attachment 3 to obtain child thyroid dose.

5.6.4 Calculate integrated whole body exposure by k multiplying dose rate by projected exposure time (hr.).

l 5.6.5 Once all data and calculations are completed, communicate results to Emergency Director.

5.7 Project source strength from offsite monitoring dose rate data utilizing Form EPIP 9-4.

5.7.1 Enter '2' in source strength method column to

• indicate that source strength was determined from offsite dose rate.

5.7.2 Enter type of release 'E' for elevated (stack releas e) , 'G' for ground.

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e 5.7.3 Enter monitoring location downwind distance in miles.

, 5.7.4 Calculate source strength based on the formula:

dose rate x windspeed = source strength dose factor x dilution' factor mrem /hr x u (meter /sec) = Ci mrem /hr x Xu (m-4) Ec Ci/mJ Q where : mRam = whole body dose rate at downwind distance hr from Form EPIP 9-5.

u = windspeed in meter /see from Form EPIP 9-1.

_ mrem /hr = whole body dose factor f om Attachment 2 Ci/mJ as a function of time af ter shutdown g = atmospheric dilution factor from Q Attachment 1 based on type of release, stability class, and downwind distance.

5.7.5 Project offsite dose rate at other downwind distances using source strength determined in Section 5.7.4.

, Enter '2' in the " source strength method" column for each projection. Reference Section 5.5.3 through 5.5.6 for calculation methodology.

l l

5.7.6 Once all data and calculations are complete, communicate

[ results to Emergency Director.

l.

5.8 Liquid Release 5.8.1 If average diluted concentration of discharge canal exce,eds 10 CFR 20, Appendix B. Table II, Column 2 limits as i

,e determined by chemistry sample analysis, notify Group Shift I Supervisor and/oc Emergency Director and recotanend declaration of an Unusual Event Emergency Classification.

I 10 CFR 20 Limits exceeded Time Date

[

NorE: Include a copy of sample analysis with this procedure.

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5.8.3 Continue sampling Discharge Canal until sample analysis by chemistry confirms that average diluted concentration of Discharge Canal is less than 10 CFR 20, Appendix B, Table II, Columa 2 limits. Record results on Liquid Release Sample Results and cotumunicate to Emergency Director.

LIQUID RELEASE SAMPLE RESULTS Analysis Sample tocation ( Time) Date  % 10 CFR 20 Confirmed by Time / Initials

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ATTACIDDLNT 1 l l

Atmospheric Dilution Factors as a Function of Downwind Distance and Atmospheric Stability Class ELEVATED RELEASE

~

Dilution Factor Xu (m )

Q Distance (miles) Unstable Neutral Stable 0.25 4.57E-12 2.77c-21 1.31E-20 0.50 8.69E-07 8.64E-22 4.12E-21 1.0 3.40E-C$ 5.68E-12 2.3 9E-18 2.0 9.37E-07 3.3 2E-08 6.48E-11 l 3.0 5.25E-07 5.3 9E-07 3.24E-08 4.0 3.92E-07 1.08E-06 3.77E-07 5.0 3.29E-07 1.3 2E-06 1.12E-06 10.0 1.87E-07 1.20E-06 3.33E-06 From: "CRISO-Dispersion and/or Dose Isopleths for Emergency-1 Class A Model" by Pickard, Love, & Garrick, Inc.

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Offsite Dose Projections DIP-9  %  ? d  ? D 4enmon No. Cote 2 11/2/32 ATTACHMENT 1 (cont'd)

Atmospheric Dilution Factors as a Function of Downwind Distance and Atmospheric -

Stability Class GROUND RELEASE Dilution Factor Xu (m" )

Q Distance (miles) Unstable Neutral Stable 0.25 4.83E-0 5 3.18E-04 8.91E-04 0.50 1.69E-05 1.35E-04 4.8 6E-04 1.0 4.15E-06 5.2 7E-05 2.2 6E-04 2.0 9.06E-07 2.16E-05 1.08E-04 3.0 5.11E-07 1.02E-05 5.81E- 05 4JO 3.88E-07 6.9 5E-06 4.18E-05 5.0 3.26E-07 5.25E-06 3.21E-05 10.0 1.8 7E-07 2.11E-06 1.50E-05 Prom: "CRISO-risp. raion and/or Dose Isopleths for Faergency-Class A Model" by Pickard, Iowe, & Garrick, Inc.

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l ATTACHMENT 2 WHOLE BODY DOS 2 FACTOR AS A FUNCTION OF TIME AFTER SHUTDOW TIME AFTER SHUTDOWN WHOLE BODY DOSE FACTOR (HRS) mRani/hr per Ci/m 0 5.3E + 05 1.5 5.0E + 05 2.5 4.3E + 05 3.5 3.7E + 05 4.5 3.1E + 05 6.5 2.3E + 05 12.5 1.2E + 05 FROM: Federal Emergency Management Adcinistration Course " Dose Projection" by Joe E. Logsdon

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se,.se: Prosseure No, Of faite Dose Projections _. EPIP-9  % 1 d 1 D Aenman No. Cete -

FORM EPIP 9-1 METEOROLOGICAL PARAMETERS TABLE Chart Affected .

Record er Co nverted Sector Wind Wind Wind Downwind (Compas s at Stability Speed Speed Time /

Direction (*) Value (*) Po int) (*F.) Class (mph) (m/sec) Initial .

1. /

2. /

3. /

4. /

5. /

6. /

7. /

8. /

9. /

10. /

11. /

12. __

/

13. _

/

14. /

15. /

16. /

17. -

/

18. /

19. /

, 20. ---

/

1 .,

I Form EPIP 9-1

--_ - __,c: _..y,.~.m.

_. ei_.C & ? Is?

_ .. _ _ _ _ _ . . _ . _ . __ _. _ . . - _ - . _ _ _ . ._.. .. ._2. . ..

I .

k amect: hows No.

Of fsite Dose Projections EPIP-9  % 1 8f 2  %

Memmon No. Cete FORM EPIP 9-2 POSTULATED OFFSITE DOSES FROM DESIGN BASIS ACCIDENTS Not e : All doses are in REM Whole Body Dose for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> release at'a windspeed of 1 mph (0.45 m/sec)

1. Refueling Accident (Rem) - Basis Dose Distatce Stability Class (Milos) Stable Neutral Unstable 0.25 2. 5 5E-04 2. 5 5E-04 4. 00E-0 4 0.50 2.09E-04 2.2 7E-04 3.4SE-04 l.0 1. 45E-04 1.91E-04 1. 7 3E-04 2.0 8.8 2E-05 1.18E-04 6.27E-05

2. Control Rod Drop Accident (Rem) - Basis Dose Distance Stability Class (Miles) Stable Neutral Unstabia 0.25 3.0E-01 3.09E-01 4.5 5E-01 0.50 2. 6 4E-01 2.82E-01 4.00E-01 l 1.0 1.91E-01 2.3 6E-01 2.09E-01 2.0 1.27E-01 1.55E-01 7.82E-02

3. Ioss of Coolant Inside Drywell Accident (REM) - Basis Dose Distance Stability Class (Miles) Stable Neutral Unstable 0.25 7. 45E-0 6 7. 5 5E-06 1. 0 9E-05 0.50 6.36E--05 6,91E-06 1.00E-05 1.0 4. 64E-06 5.7 3E-06 5.09E-06 2.0 2.91E-06 3.64E-06 1.91E-06

4. Steam Line Break Outside Reactor Buildita (REM) - Basis Dose ,

Distanc e Windspeed Basis of 50 mph, DO NOT DIVIDE BY WIND SPEED (Miles) Whole Body Dose ( Rem) 0.25 3. 6E-0 6 l 0.50 2.0E-0 6

, 1.0 8.6E-07 2.0 3.2E-07 5.0 6.6E-08 l 10.0 1.9E-08 Form EPIP 9-2 o

,- - - = * - -- -

,,,. .. . . . . , , . . . ,~~

. 'v , i2 wV-

,* ~

- kogeer: Proceews No.

Of faite Dose Projections EPIP-9 Page 2 of 2 pogos Aension No. Cote FORM EPIP 9-2 "POS1VLATED OFFSITE DOSES FOR DESIGN BASIS ACCIDENTS" WORKSHEET Date / /

Time / Initials 1

Type of Design Basis Accident

' /

Affected Se ctor Wind Wind 0.25 mi 0.50 mi.1.0 mi. 2.0 (Compass Stability Speed Speed Dose Dose Dose Dose Po in t'. Class (MPH) (M/Sec) (Ram) (Rem) (Rem) (Ram)

1. /

2. /

3. /

l

4. /

5. /

S. /

7. /

8. /

9. /

10. ,

/

l Form EPIP 9-2

'J

' FOGM EPIP 9-3 .

SOURCE STRENGTNlliffiilNATIOu TAatt Date / / -

1. Elevated Releas, A. TOTAL STACE AIR FLOW Reactor Turbine Old Radwasta New Radwaste Standby Gas Other Bida. (Cfe) Side. (Cfe) 81de. (Cfe) 81de. (Cfa) Ireatment (Cfe) (Cfe) Total (Cfm) Time / Initials

l. 65.000 82.000 14.600 38.000 2.600 /

2. 65.000 42.000 14.600 38.000 2.600 / ,

t

3. 65.000 82.000_ 14.600 38.000 2.600 /

f

4. 65.000 82.000 14.600 38,000 2.600 _

/

5. 65.000 42.000 14.600 38.000 2.608 / f

8. STACK RELEASE SOURCE STRENGTN Stack Monitor Converston Factor Stack Correction (Counts /Sec) (uCl/Sec per count /sec) Factor C1/uCl Cl/Sec Time / Initials

1. -

1.0E-06 / t

2. 1.0E-06 / i

3. l.0E-06 / \

f

4. 1.0E-06 /

.l 5. 1.0E-06 /

C. GROUND RELEASE SOURCE STRENGTN 4 Air t

Source of Release Activity Release Rate Conversion [

(Area or location) _(uCl/Cc) (ft3 / min) Factor C1/seC Tlas/ Initials j l. 4.72E-04 j-

't 2.

e

-3 4.72E-84 +

1 ri 3. 4.72E-04

4. 4.72E-84

5. 4.72E-04 EPIP-9 11/2/02 Rev. 2 Page 1 of 1 jl Form EPIP 9-3 l

2.' '

f ll  ;

,1  ;

Al .

1 p *e'

4 FORM trip 9-4 .

OFFSITE DOSE PROJECTION TABLE Date: / /

, 1. OFFSITE NOSE - WHOLE 800Y EXPOSURE Affected

, Sector Type _

. Integrated NRS Source (Compass Dist. of Stablitty Nu La-2) u C1 meem/hr Dose Rate Mrs. of Dose Time to Time / -

St. Meth. Point) Mlle Release Class 7 (m/sec) _sec ~ CITi3 mrem /hr Re1. seen Reach PAG Initials

1. /

! 2. / .

~

3. _. ._  !

4. _ . _ _

/

5. /

6. .,

/

, 7. /

8. /

I 9. ,

/ -

10. /

i

2. OFFSITE DOSE - CHILO TNYROID

-! Affected si Sector h is Body Proj. Chlid Child (Rem /Nr) HRS r.4; Source (Compass Dist. Exposure Exp. Time Thyroid Thyroid Time to Time /

) $ 6 Meth. Point) ,MjJg mRec/hr (NR) Dose (Rem) Dost Rate Reach PAG Inttials I! 1. /

,b 2. /

3' -. /

'jj 4. / ,

[i

.:]

5. /

,Q.l 6. , _ /

^l '

,. 7. , /

S. /

. 9. / '

1

.. I 10. / ,

i . '.l 1

., EPIP-9 11/2/82 Rev. 2 Page I of 1 .

Form EPIP 9-4

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

r.

FORM EPIP 9-5 ,

OFFSITE MONITORING DOSE PROJECTION TA8tE Date / /

l. INTEGRATED DOSES j' Integrated Wole Body L'ntegrated Monitoring Aztsuth Dist. Air Conc. Projected (hrt Cht1d Thyroid Dose Rate mole Body Time /

Location (Deerees) Miles (uCt/cc) [ oosure Time Dose (Rem) mrem /hr Dose (mrem)_ Initials

1. /

2. /

3. - /

f

4. _ /

5. /

6. *

/

! 7. /

8. /

3. /

10. /

]l 4

2. AIR SAMPLE ACTIVITV

, Monitoring Azimuth Dist. Converston Time /

Location (oeerees) Miles NCPM Factor 4 Efflctency uCt/cc Initials

'i: 1. 7.5E-Il / _ j

.'! 2. 7.5E-11 /

at l'I, 3. ,, 7.5E-Il / 1, O

T:, 4. 7.5E-1I /

"I - 5. 7.3E-11 /

I;)* 6. _ 7.5E-Il /

I a

"t 7. 7.5E-Il / '

'.*.1 i 1 8. 7.5E-Il /  ;'

i

,', j 9. 7.5E-Il /

'.,'. 10. 7.5E-Il -- /

s g

EPIP-9 11/2/82 Rev. 2 Page 1 of I $

}

Form EPIP 9-5 3

ProceCute No.

P M J:W#IfiLA I a ,,((u72 sn clt, t 5 Jersey Central 2/24/s1 c12/a/823 12/1s/s2 Power & tight Company aev=ca No- o*ta 1 11/2/82 Sueject- search and Rescue AutnQnZ9C SY Director-Station Operations ApprovauConcurrence 4 ,

j Project #

Ovster Creek Nuclear Generating Station 4

LIST OF EFFECTIVE PAGES DATE REVISION NLMBER 1 11/2/82 l' 2 A1/2/82 1 3 11/2/82 1 4 11/2/82 1 ,

5 11/2/82 1 AITACIDfENT I

For:n 22-1 (,1 page) 11/2/82 1 n

NON CONTnoLLED ,

t gg Docum60, y,a ;sa i>e MP ppTo Date em> e oe 8""#** ' * * ' *W e e *

• Ta= w eg w q ,. p g , , , , , , , , , , , p, ,,

t l

i

' Pm:eews Ne, gageen Search and Rasene EPIP-22 Pese 2 of 5 Pelos 1 11/2/82 _

1.0 PURPO SE This procedure prescribes the implementation of Search and Rescue Operations at Oyster Creek Nuclear Generating Station.

4

2.0 REFERENCES

2.1 EP IP-2 Unusual Event 2.2 EPIP-3 Alert 2.3 EP IP-4 Site Emergency 2.4 EPIP-5 Ceneral Emergency 2.5 EP IP-7 Personnel Injury 3.0 RESPONSIBILITIES 3.1 The Emergency Director is responsible to evaluate conditions which could require initiating of Search cud Rescue Operations.

3.2 The Operations Support Center Coordinator is responsible to assemble, prepare and dispatch all Search and descue parties and to carry out

( the requirements of this procedure when activated.

3.3 The Operations Support Center Coordinator is responsible to insure the attached Checklist is completed in accordance with Section 5.0 of this p rocedure .

4.0 PREREQUISITES 4.1 Search and Rescue may be initiated durirg any class of emergency l

(i.e., Unusual Event, Ale rt , Site Daargency, and General Energency)' or l

l by any initiating condition within these classifications.

l l 4.2 Additionally, Search and Rescue Operations may be initiated as a result of Personnel Accountability (EPIP-12).

4.3 The following precautions will be taken:

4.3.1 Wear proper protective clothing as directed by Radiological Controls.

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4.3.2 Use proper respiratory protective devices as directed by Radiological Controls.

4.3.3 Wear proper dosimetry as directed by Radiological Controls.

.t 4.3.4 -Radiation exposure to individuals exceeding 10CFR20 limits is restricted as follows:

, EMERGENC'i EXDOSURE LDfITS PROTECTIVE OR LIFE SAVING ORGAN CORRECTIVE ACTION ACTION Whole Body 25 Ram 15 Rem Extremeties 100 Ram 300 Ram Thyroid 125 Rem No limit 4.3.5 Women capable of reproduction should not take part in actions requiring emergency erposure.

4'. 3. 6 Emergency exposures for volunteers must be authorized by the Emergency Director. This responsibility may not be delegated.

4.3.7 All ext sures will be maintained ALARA.

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5.0 REQUIREMENTS

, 5.1 Immediate Notifications 1

5.1.1 Upon discovering that an individual is trapped or disabled or missing, the individual who discovers the situation shall call the Control Room, report the situation and provide the following information if known:

5.1.1.1 Name of the individual trapped, or disabled, or l

missing.

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Search and Rescue EP IP N 4 d 9 D

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, 1 11/2/82 5.1.1.2 Location of the individual trapped or disabled.

5.1.1.3 Any circumstances which may affect Search and Rescue Operations, such as fire, explosion, or i

high radiation levels (see Section /s.3).

5.1.2 If an individual is missing, Search and Rescue Operations shall prcceed in accordance with Section 5.2.1. If an individual is trapped or disabled, Search and Rescue Operations shall proceed in accordance with Section 5.2.2.

5.2 Search and Rescue Operations 5.2.1 If a missing person report is received in the Control Room from Station Accountability or any other source, the following actions should be initiated to locate the missing person:

5.2.1.1 Contact the individual's supervisor.

5.2.1.2 If the individual's supervisor does not know his location, page the individual using the Public Addret's System (repeat the page).

5.2.1.3 If the page is not answered in two minutes, telephone the individual's home (if the number can be obtained).

5.2.1.4 If the missing individual has not been located following the completion of Step 5.2.1, the Emetgency Director or his designee shall direct the Search and Rescue team to be dicpatched from the OSC to locate the individual.

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Search and Rescue EPIP-22  % 5 'f 5  %

Movision No. Cote 1 11/2/82 5.2.1.5 The OSC Coordinator or his designee will organize the search, using any information available concerning the potential . location of the missing individual.

5.2.1.6 Af ter the individual has been located and if medical assistance is necessary, the Search and Rescue team shall render first aid and EPIP-7 will be initiated by the OSC Coordinator.

5.2.2 If a trapped or disabled person report is received in the Control Room, the Emergency Director shall direct the Search and Rescue team to be dispatched from the OSC accompanied by the Medical Representative, if available, and a Radiological Controls Technician, if appropriate assistance 10 required.

EPIP-7 will be implemented.

5.3 Termination of Search and Rescue Operations 5.3.1 Search and Rescue operations may be terminated by the Emergency Director or his designea when all of the following conditions are met:

5.3.1.1 All missing persocs have been accounted for.

5.3.1.2 All injured or disabled persons are in the care of medical personnel in accordance eith EPIP-7 or have been released by the Medical Representative.

5.3.1.3 All trapped persons have been rescued and released from their entrapment to return to their duties.

5. 3.1. l* Search and Rescue teams ha ne ret.orned to their l duty station to stand by. ,

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Search and Rescue EPIP-22 Pese 1 of 1 pages Mensson No. Cete

. 1 11/2/82 i Form 22-1 SEA 2CH AND RESCUE CHECKLIST 1 l

Note: When activated, the Operations Support l Coordinator or his designee vill complete  :

this cheeklist. I Time / Initials

/ Trapped / disabled / missing persons report received

• i Name (if known) l Location (if known) l

/ Supervisor contacted for information on whereabouts.

/ Plant page used to contact missing person (vait 2 minutes for response).

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Contact nissing person's home for information on chereabout s.

/. Dispatch Search and Rescue taam, including Radiological Controls Technician and medical personnel, as appropriate.

/ EPIP-7 initiated for injured person.

Terminate Search and Rescue Operations when:

l i / All missing persons are accounted for.

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/ All injursd/ disabled persons are receiving medical care in accordt. ice with EPIP-7.

/ All trapped persons have been rescued.

/ Search and Rescue teams returned to duty stations.

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