ML20077E302

Rev 11 to Procedure/Work Plan 1905.001, Emergency Radiological Controls

ML20077E302
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/28/1994
From:	ENTERGY OPERATIONS, INC.
To:
References
1905.001, NUDOCS 9412120227
Download: ML20077E302 (18)

Text

. .

, ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE Arkansas Nuclear One Russellville, Arkansas Date: 941205 MEMORANDUM 200 : 103 *Please return transmittal .

CC - NRC - WASHINGTON to Document Control, 3RD floor Admin Bldg

• FROM: DOCUMENT CONTROL Ref Key: 17379

SUBJECT:

PLANT MANUAL UPDATE: NEW REVISION TO PROCEDURE PROCEDURE / FORM NUMBER: OP-1905.001 REV. # 11 TC # 0 PC # 1 PROCEDURE / FORM TITLE: EMERGENCY RAD CONTROL The following pages of the indicated rocedure(s) contains items which involve personal privacy or proprietary mater al. PLEASE REMOVE THE INDICATED MATERIAL PRIOR TO DISTRIBUTION TO PUBLIC DOCUMENT ROOMS, ETC.

PROCEDURE (S) PAGE(S)

SIGNATURE: DATE: .

UPDATED PRINT NAME  :

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FORM TITL ~ FORM NO. REV.

LIST OF AFFECTED PAGES 1000.006A 41 l

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PROCJWORK PUUd NO. PROCEDUREMORK PUW T.TLE: PAGE: 1 Of 16 j

'1906.001' EMER2ENCY RADIOLOGICAL CONTROLS M: 11 CHANOE:

/ 1.0 PURPOSE Q) -

This procedure provides guidance for the following radiological control i practic'es during emergency situations:

1.1 Personnel Monitoring.

1.2 Respiratory Protection.

1.3 Contamins*ien Control.

2.0 SCOPE 2.1 This ;: >duan La _plicable during Alert, Site Area or General Emergency wM uir .

2.2 This procedure g plies to ANO emergency support personnel and emergency response facilities within the ten mile Emergency Planning Zone.

3.1 REFERENCES

USED IN PROCEDURE PREPARATION.

3.1.1 Emergency Plan.

3.1.2 1903.043, " Duties of the Emergency Radiation Team".

O 3.1.3 1000.031, " Radiation Protection Manual".

3.1.4 1903.033, " Protective Action Guidelines For Rescue / Repair and Damage Control Teams" 3.1.5 1903.023, " Personnel Emergency" 3.1.6 1012. 019, " Radiological Work Permits" 3.1.7 Letter H-5,79-739, of May 16, 1976 from Mr. Alan Hack, LASL, Respirator Resecrch and Development Section to Mr.

John Collins, USNRC RE: Respiratory Protection at TMI.

3.1.8 10 CFR 20 ,

3.1.9 10 CFR 50 3.1.10 NRC Information Notice 90-08

3.2 REFERENCES

USED IN IMPLEMENTING THIS PROCEDURE.

3.2.1 1903.033, " Protective Action Guidelines for Rescue / Repair and Damage Control Teams" 3.2.2 1903.030, " Evacuation" 3.2.3 1601.209, "Whole Body Counting" 3.2.4 1601.201, " Issue / Control of TLD's" O}

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PROCJWORK PLAN Noi PROCEDURE / WORK PUW TITLE: PAGE: 2 of 16 EMER2ENCY RADIOLOIICAL CONTROLS RE 11 1905.001 CHANGE:

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3.3 RELATED'ANO PROCEDURES

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3.3.1 1903.066, " Emergency Response Facility - Operational Support Center (OSC)"

3.3.2 1903.067, " Emergency Response Facility - Emergency Operations Facility (EOF)"

3.4 REGULATORY CORRESPONDENCE CONTAINING NRC COMMITMENTS WHICH ARE IMPLEMENTED IN THIS PROCEDURE:

3.4.1 OCANO78609 A. Section 6.2 03.4.2 OCANO38313, Response to IR 313/8211-10; 368/t ?G9-10 A. Form 1905.001 A Section IIB 1 4.0 DEFINITIONS 4.1 Controlled Access Area - That portion of the station to which access is positively controlled for radiological protection purposes.

(Basically, this area consists of the Reactor Buildings and portions of the Auxiliary Buildings for both units.)

4.2 Control Point - An area established on the perimeter of, and in the normal access route to/from an RCA for the purpose of controlling s

g i personnel and or material movement.

V 4.3 Radiologically Controlled Area - A Radiologically Controlled Area (RCA) is defined as an area within the plant site in which radioactive material and/or radiation may be present in quantities sufficient to require protective measures. (The Controlled Access Area, for example, is a Radiologically Controlled Axea).

4.4 Emergency Operations Facility (EOF) - A near site _ emergency response facility located approximately 0.65 miles northeast of the reactor buildings (the ANO Training Center). ,

4.5 Technical Support Center (TSC) - The location within the ANO Administration Building equipped with instrumentation and communication systems and facilities useful in monitoring the course of an accident; this center is located in the 3rd Floor Conference Room.

4.6 Dmergency Response Organization (ERO) - The organization which is composed of the Initial Response Staff (IRS), the EOF staff, the TSC staff, the OSC staff and the emergency team members. It has the capability to provide nanpower and other resources necessary for immediate and long-term response to an emergency situation.

4.7 Operational Support Center (OSC) - Emergency Response Center within the ANO maintenance facility where support is coordinated for the following functions:

4.7.1 On-site Radiological Monitoring

P'RoCJWORK PLAN NO. PROCEDURE / WORK PLAN Tm2: PAGE: 3 of 16 REV: 11 1905.001 EMER2ENCY RADIOLOGICAL CONTROLS CHANGE:

Maintenance 4 4.7.2 4.7.3 Nuclear Chemistry 4.7.4 ' Emergency Medical Support 4.7.5 Fire Fighting Support The OSC, located in the ANO maintenance facility, serves as the assembly point and briefing area for rescue / repair and-damage control teams.

4.8 HEALTH. PHYSICS NETWORK (HPN) TELEPHONE Dedicated telephone system established by the NRC during its standby or initial activation mode of operations after the licensee's TSC/ EOF has been activated and is operational. The HPN is the primary means of conuounicating radiological data (on-site and off-site measurements and dose assessment information) from the licensee to the NRC.

5.0 RESPONSIBILITIES 5.1 MANAGER, RADIATION PROTECTION AND RADWASTE 5.1.1 Responsible for the overall control and implementation of this procedure.

5.2 HEALTH PHYSICS SUPERVISOR V 5.2.1 Responsible fcr the implementation of this procedure within the ANO site boundary fence.

5.2.2 Responsible for directing on-site monitoring and assigning personnel to the on-site and off-site radiological ,

monitoring sections of the Emergency Radiation Team.

5.3 EOF HEALTH PHYSICS SUPERVISOR 5.3.1 Responsible for ensuring that the appropriate control points and radiological control measures are established and' implemented at the Emergency Operations Facility /

Alternate Emergency Operations Facility.

6.0 INSTRUCTIONS 6.1 GENERAL GUIDELINES FOR EMERGENCY RADIOLOGICAL CONTROL 6.1.1 The Health Physics Supervisor should use Form 1905.001A as a checklist for ensuring appropriate radiological controls have been implemented.

6.1.2 As manpower becomes available, the Health Physics Supervisor should assign at least one (preferably two) H.P.- ]

technician to report to the EOF to assist the EOF Health Physics Supervisor.

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PRoCJWORK PUW NO. PROCEDufuuWORK PUW M12: PAGE:

REV: 11 a 1905.001 EMERGENCY RADIOLOGICAL CONTROLS

,- CHANGE:

4 Upon receipt of survey results, the Manager, Radiation i l

L\ ,jl 6.1.3 Protection and Radwaste should check Attachment 1 to ensure appropriate emergency. response actions such as evacuation or notification are implemented. Radiological survey results-should be posted in the Technical Support Center and the operational Support Center.

i 6.1.4 Based'on reported radiological survey data and as directed by the Manager, Radiation Protection and Radwaste, the Health Physics. Supervisor shall establish Radiologically, Controlled Area Boundaries in'accordance with Health Physics procedures.

6.1.5 IF an emergency condition lasts longer than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, THEN the Manager, Radiation Protection and Radwaste shall establish an Emergency Radiation Team working schedule.

6.1.6 Beta radiation from Kr-85 gas is a significant hazard in an accident involving spent fuel. Direct exposure to Kr-85 gas could result in a skin dose up to 100 times the Deep Dose equivalent dose. The half-life.of Kr-85 is 10.76 years. For these reasons, IF the accident involves spent fuel, THEN the Health Physics Supervisor shall have the affected area surveyed for beta radiation.

6.2 CONTROL POINT ESTABLISHMENT 6.2.1 IF radiation levels exceed ' 2.5 mrem /hr. ' or significant O (greater than 1 DAC particulate or iodine) airborne activity exists outside confines of Auxiliary and. Turbine buildings,' THEN control points should be established at RCA boundaries as defined by survey results.

6. 2. 2 . Once the extent of contamination, radioactive airborne concentrations and radiation exposure rate conditions are known, the control point for Emergency Team entries should be located as close to the controlled Access Area as possible without sacrificing communications and ease of-entry / exit control.

A. Radiological conditions permitting, the normal controlled access area control points in Unit One and Two Auxiliary Building (Elev. 386') should'be used as the control point for emergency response operations into the Auxiliary Building.

6.2.3 IF radiation levels exceed 2.5 mrem /hr. or significant Igreater than 1 DAC particulate or iodine) airborne activity exists at the EOF, THEN a control point should be established at the entrance to the EOF and the need for a -

contamination control point evaluated.

6.2.4 The following radiological controls should be instituted at .;

control points.

A. Personnel entry log including time in, out and-

'(

s Dosimeter reading (s) should be maintained for all  !

entries on Form 1905.001B.

PROCJWORK PUW No. PROCEDURE / WORK PLAN TITLE: PAGE: 5 of 16 E II 1905.001 EMERGENCY RADIOLOGICAL CONTROLO CHANGE:

f B. A frisking station using an RM-14/HP-210 or equivalent

('3)

' should be used to check personnel contamination for personnel exiting the radiologically controlled area.

C. Air samples should be taken every hour and shall be taken once every four hours.

D. A survey of the control point area should be conducted )

if the friskers indicate a rise in the area radiation level. IF no friskers are set up at the control point, TEEN hourly area surveys should be conducted.

Air sample and dose rate data should be maintained on appropriate forms and data reviewed periodically by the Health Physics Supervisor to determine increases l or trends. Significant changes should be reported to the Manager, Radiation Protection and Radwaste as soon I as practical. l l

l 6.3 RESPIRATORY PROTECTION l

6.3.1 Respiratory Protection Guidelines i l

A. Although doses should be maintained as low as reasonably achievable during an emergency, respirators I should not be assigned to emergency team members or l emergency response facility personnel if the use of l respirators will have an adverse affect on the timely j implementation of emergency measures and projected i 7si gd dose is less than 40 DAC-hrs / week. i B. During emergency conditions, higher uptakes may be l authorized in a manner similar to that for increased external exposure as specified in 1903.033 " Protective Action Guidelines for Rescue / Repair and Damage Control i Teams".

6.3.1 C. Protection factors for respirators are identified in f 1000.031, ' Radiation Protection Manual" and 10 CFR 20 l Appendix A. However, the Respiratory Protection Manual specifies that these protection factors are not applicable unless the respirator has been quantitatively fit tested on the wearer.

D. The Health Physics Supervisor shall ensure the following data, on personnel entering the RCA(s), is recorded on Forms 1601.209D and F or tracked on the ERIM system.

1. Occupancy time and airborne concentrations

2. DAC-Hrs (each entry, each day, and last 7 days)

3. Protection factor for the Respiratory Protection l Device Worn o

PROCEDURE / WORK PUW Tm.E: PAGE: $ of 16 PROCJWORK PLAN NO.

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M '11 1906.001 EMERGENCY RADIOLOGICAL CONTROLS CHANGE:

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All individuals entering radiologically controlled

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areas shall have whole body counts or bioassays performed, as soon as practical, if their exposure to radioactive airborne concentration exceed 4 DAC-HRS per day or 12 DAC-HRS /wk or 40 DAC hours since last whole body count.

6.4 IODINE CANISTER USE 6.4.1 NUREG-0041 and Regulatory Guide 8.15 do not provide a .

protection factor for iodine canisters for routine use because of difficulties ensuring continued protection. As a result, the only respirators which are suitable in iodine atmospheres are air supplied devices, such as SCBA and air line masks. (NUREG-0041 prohibits the use of air line masks in rescue operations). However, in addition to airborne radioactivity, the areas in which the respirators are likely to be used may also be.affected by high dose rates. Since mobility is reduced when wearing SCBAs, it may be more conducive to overall dose reduction to use iodine canisters in lieu of SCBAs. For these reasons, the Manager, Radiation Protection and Radwaste or the Health Physics Supervisor may direct that iodine canisters be used in emergency conditions.

6.4.2 The filter canister authorized is the MSA GMR-I charcoal canister.

D \ 6.4.3 The protection factor is 1 for iodine.

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l 6.4.4 The respirator shall not be used in iodine atmospheres I greater than 100 times the 10 CFR 20 value for the specific iodine nuclide. For Iodine-131, this is 2 E-6 pCi/cc.

(Assumes stay-time control).

6.4.5 The stay-time in affected areas shall not exceed 40 DAC-hours in any seven consecutive days. (This provides j for additional subsequent dose).

6.4.6 Appropriate representative air sampling shall be performed.

6.4.7 Suitable DAC-hour records shall be kept in accordance with Section 6.3.l(D).

6.4.8 Personnel exposure to iodine atmospheres with iodine canisters shall be monitored as follows:

1 A. At least weekly whole body counting while exposures l continue.

B. Ir results of whole body counting indicate an iodine l uptake in excess of 70 nci, THEN that individual (s) (

shall be restricted from further entry to iodine atmospheres pending evaluation by the Manager-Radiation Protection and Radwaste.

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PROCJWORK PLAN NO. PROCEDUREJWOF.K PLAN TME: PAGE: 7Of16 EME RSENCY RADIOLOGICAL CONTROLS M: 11 1905.001 CHANGE.

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t, j 6.5 PERSONNEL MONITORING s<

6.5.1 Assignment of Dosimetry A. Personnel radiation exposure shall be monitored by regulation if 10% of the applicable limit could be received; or they will be entering a High Radiation Area or a Very High Radiation Area.

B. IF a significant release of radioactivity occurs such that an individual would receive a dose in exces: of 2.5 mrem in any one hour, THEN t' is inrea shall be designated as radiologically centrolled area and Dosimetry shall be worn in affected areas.

C. Emergency response personnel shall wear a TLD badge at all times while on site during the emergency.

D. When an emergency involves a site evacuation, final personnel dosimetry issue and collection operations should be relocated to the EOF or an alternate low back-ground area designated by the Manager, Radiation Protection and Radwaste.

6.5.2 Assignment of Dosimetry to Emergency Teams NOTE Personnel should be cautioned to check dosimeter frequently f

(5 - 10 minutes) as conditions may change rapidly. Under no

(- circumstances should the dosimeter be allowed to exceed 3/4 scale. Personnel with dosimetry at or above 3/4 should exit immediately unless such action would endanger the plant or another person. Additional or more restrictive dosimetry may be assigned as required by the Health Physics Supervisor or Manager Radiation Protection and Radwaste.

NOTE During a " Personnel Emergency" the Emergency Medical Team may go into Radiologically controlled Areas without SRDs/ Alarming Dosimeters as long as an HP Technician is acting as the RWP; and is monitoring dose rates and time in the area. Prompt medical attention shall take precedence over HP procedures when an individual is seriously injured.

A. Personnel requiring entry into a Radiologically Controlled Area where expected dose rates will not exceed 1000 mrem /hr or when accumulated TEDE dose is not expected to exceed 10CFR 20 limits shall require the following dosimetry as a minimum.

1. 0 - 200 mR or 0 - 1.5 R SRD as directed by OMS / RPM

2. Whole Body TLD D

PRoCJWORK PLAN NO. PROCEDURE / WORK PLAN TITLE: PAGE: $ Of 16

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REV: 11 1905.001 EMERGENCY RADIOLOGICAL CONTROLS l CHANGE: l

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V B. Members of rescue / repair and damage control teams requiring access to high dose rate (greater than 1000 mrem /hr) areas for the purpose of performing radiological surveys, rescue, repairs, or damage control require the following dosimetry as a minimum.

1. TLD

2. 0 - 500 mR or 0-1.5 R Pocket Dosimeter as directed by OMS / RPM

3. 0 - 1.5 R or 0 - 5 R Pocket Dosimeter as directed by OMS / RPM

4. Extremity TLDs for each hand / forearm as directed by OMS / RPM

5. Extremity TLDs for each ankle / leg as directed by OMS / RPM C. In the event major fuel damage is sustained or suspected, use of 0-200 R dosimeters should be considered in high dose rate areas.

fs t'-.) D. The Health Physics Supervisor and the Manager, Radiation Protection and Radwaste shall ensure the following data are maintained for emergency team members on Form 1905.001B.

1. Entry and Exit times

2. Pocket Dosimeter Readings for each entry

3. Cumulative Personnel Exposures 6.5.3 Assignment of dosimetry to offsite emergency organizations called upon to provide assistance in the event of an emergency.

A. Offsite personnel called upon to provide assistance within the ANO Protected Area should be issued an unassigned whole body TLD

1. TLD issue log should include:

- individual's last name

- TLD number

2. The TLD issue process shall not delay the response of organizations such as Pope County Emergency Medical Services (PCEMS) or Russellville Fire Department (RFD) that are f Y responding to protect life or plant equipment necessary for protection of the public.

1

Mt0CJWORK PLAN No. PROCEDURENWORK PUW Tm.E: PAGE: 9 of 16 1905.001 EMERGENCY RADIOLOGICAL CONTROLS RR 11 CHANGE:

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B. At the termination of the emergency, Security shall

. notify the dosimetry department of the issue of unassigned TLDs.

C. On the following day Security shall forward the badge issue log or a copy of the log to the Emergency Planning Supervisor.

1. The Emergency Planning Supervisor shall review the log and provide the following information to the dosimetry department.

a. Individual's full name and social security number

b. Individual's address

c. Employer's name D. As directed by the Radiation Protection Manager, the individuals that have been issued unassigned TLDs should have a whole body count as soon as practical following the emergency.

6.5.4 Accelerated TLD Processing A. More frequent readings of TLD's should be performed during the emergency and, initially, during recovery operations until such time as exposure trends have

,. been identified and exposure control methods l established by the Manager, Radiation Protection and i Radwaste.

B. In the event of an accidental exposure, or an approved planned emergency exposure, the TLDs of the individuals involved shall be processed as soon as practicable following exposure. Further exposure should not be allowed until the results of their TLD badge readings are available and have been evaluated.

C. TLD's left on the badge racks and the associated control badges shall be read as soon as possible following exposure, in order that the personnel exposure prior to the accident may be evaluated to provide a basis- for subsequent exposure.

6.5.5 Recording of Personnel Exposures i

A. Personnel radiation exposures monitored by pocket  !

dosimeter for the Emergency Radiation Team and other )

emergency response personnel shall be recorded on Foca 1905.001B, " Access and Exposure Control Log" or equivalent ERIM system programs. Form 1905.001B shall l be kept by the Health Physics Supervisor for the purpose of interim exposure tracking control over I individuals perforudng emergency activities. l l

B. Personnel radiation doses monitored by a TLD shall be l

/N recorded in accordance with procedure 1601.201,

(,,) " Issue / Control of TLD's". l

PAoc; work PUW NO. PROCEDUREMORK PLAN TITLE: PAGE: 10 of 16 1905.001 EMERGENCY RADIOLOGICAL CONTROLS " 11 CHANGE:

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\ 6.6 DECONTAMINATION OF EVACUEES 6.6.1 During plant evacuation, the Health Physics personnel stationed at the portal monitors should segregate any contaminated individuals until an evaluation /de-contamination can be performed.

7.0 ATTACHMENTS AND FORMS 7.1 ATTACHMENTS 7.1.1 Attachment 1

• Emergency Radiological Conditions Action Levels" 7.2 FORMS 7.2.1 1905.001A, ' Health Physics Supervisor Checklist".

7.2.2 1905.001B, ' Access and Exposure Control Log" 7.2.3 1905.001C, " Kit TLD Request" i

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l l

l l

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Phoc; work PLAN NO. PROCEDURFJWORK PLAN TRLE: PAGE: 11 of 16

• RW: 11 1906.001- EMERHENCY RADIOLOGICAL CONTROLS CHANGE:

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ATTACHMENT-1

.t\ j Page 1 of 2

. EMERGENCY BADIOLOGICAL CONDITIONS ACTION LEVELS

.A. Emergency Classifications Emergency Initiating condition- Classification

1. Two or more ARMS in Rx. Bldg. increase by greater Alert than 2000 mR/hr. due to severe degradation in the control of radioactive material.

2. Two or more ARMS in Aux. Bldg. or Fuel Handling Area Alert increase by greater than 100 mR/hr. due to severe degradation in the control of radioactive materials.

3. Greater than 50 mrem /hr TEDE at site boundary. Site Area Emergency

4. Greater than 150 mrem /hr child Thyroid at site Site Area Emergency boundary.

5. Greater than 250 mrem /hr TEDE at site boundary. General Emergency

6. Greater than 500 mrem /hr Child Thyroid at site General Emergency boundary.

B. Evacuation Action

[V Initiating Condition

1. Greater than 2.5 mrem /hr outside CAA . Notify Shift Superintendent /

TSC Director

2. Greater than 9E-10 pCi/cc outside CAA Notify Shift (un-evaluated) Superintendent /

TSC Director

3. Greater than 2.5 mrem /hr. radiation levels at TSC,

• Notify Shift OSC, or remainder of the Administration Building. Superintendent /

TSC Director

4. Greater than 9E-10 pCi/cc in the TSC, OSC, or

• Notify Shift remainder of the Administration Building Superintendent /

(unevaluated). TSC Director

5. Iodine Airborne levels greater than Keep Occupancy Log 2.7E-9 pCi/cc. for Affected Area l

6. Iodine Airborne levels greater than 4 DAC Evacuate Affected.

(8.0E-8 pC1/cc). Area or Use Respiratory Protection in Affected Area I

1

PROCEDUREMORK PLAN MM:

PAGE: 12of16 PROCJWORK PLAN No.-

' E 11 1905.001 - EMERGENCY RADIOLOGICAL CONTROLS CHANGE:

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\,j ATTACHMENT 1 Page 2 of 2 Initiating Condition Action

7. Radiation levels greater than 100 mrem /hr but Evacuate if deter-less than 1 Rem /hr at TSC, OSC, or remainder of mined to be a long the Administration Building. term condition. If determined to be a short-term condition evaluate the projected personnel accumulated dose.

8. Radiation levels greater than 1 Rem /hr. at TSC, OSC, Evacuate or remainder of the Administration Building. Immediately

• 0n-site radiological monitoring section should:

1. Increase surveillance of airborne radioactivity to once per hour.

2. Determine the dose rates in the area every 15 minutes.

3. Evaluate projected personnel accumulated doses and establish appropriate stay times.

4. Post radiological survey results in the TSC and in the OSC.

O

Page 13 of16 HEALTH PHYSICS SUPERVISOR CHECKLIST NOTE:

This checklist is to be used in conjunction with the Health Physics Supervisor's Position Guide in Procedure 1903.066,

" Emergency Response Facility- Operational Support Center (OSC)"

INITIALS I. If not already accomplished, contact should be attempted with ERT members either by the plant paging system or by telephone.

Request the TSC Support Superintendent to call an assistant for you (if desired). This assistant may be another HP Supervisor or someone from the HP Technical Assistant list in the Emergency Telephone Directory.

II. Assign the on-site Radiological Monitoring Section A. Assign at least one (1) H.P. for monitoring the affected unit's Control Room.

B. Assign HP coverage for the TSC and the OSC C. Establish communications:

1. Assign OSC base radio operator.

q

2. Assign HPH telephone communicator.

D. Emergency equipment inspected and made operational.

E. RCA boundaries established.

F. Contamination control point established.

G. Control point logs established.

H. Personnel decontamination sites designated.

I. Emergency dosimetry / respiratory equipment requirements established for ERT members and TSC/OSC staff.

J. TLD/ Badge racks relocated as necessary.

K. Determine immediate response needs:

1. On-site surveys, samples required, etc.

2. Initial re-entries by other emergency teams.

3. Obtain equipment from routine stock as I k needed.

FORM NO. REV.

FORM TITLE:

EMERGENCY RADIOLOGICAL CONTROLS CHECKLIST 1905.001 A 11

Pag 314 cd 14 Page 2 of 2 A i INITIALS t

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4. Plant Evacuation- one HP technician shall be stationed at the portal monitors at each guard station. Ensure HP_rersonnel have obtained portable radiological monitoring equipment.

5. Medical Emergencies- provide assistance to medical personnel in accordance with procedure 1903.023.

6. PASS Sample- provide assistance to Nuclear Chemistry personnel in accordance with procedure 1905.003.

7. Survey affected area for beta radiation if the accident involves spent fuel.

III. Assign the Off-site Radiological Monitoring Team (include appointment of section leaders as necessary).

A. Establish 2 to 4 Off-site Monitoring Teams, each team composed of at least 2 members; have the teams obtain vehicle keys and gas pump keys. The teams are to proceed to the j- EOF, obtain and inspect field monitoring kits, and report to the off-site Monitoring Super-(^~

visor in Room 264 at the EOF.

B. Select one HP technician to report to the-Off-site Monitoring Supervisor in Room 264 at the EOF as the Off-site Monitoring team Base Radio Operator.

C. Select one HP technician to report to the Dose Assessment Supervisor in Room 262 at the EOF as the HPN telephone communicator.

D. Instruct at least 2 H. P. technicians to report to the EOF HP Supervisor at the EOF.

E. After immediate needs are addressed, establish ERT schedule for an extended event.

F. Contact the Support Manager in the EOF if additional manpower is required.

G. Provide periodic updates to team personnel and the OSC Director.

Completed by:

Reviewed by:

j g Health Physics Supervisor Foam 1905.00LA for records retention.

FORM TITLE: FORM NO. REV.

EMERGENCY RADIOLOGICAL CONTROLS CHECKLIST 1905.001 A 11

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i e Name Keycard RWP Date

> N PURPOSE OF ENTRY O Routine maint. O Survey equip. O Spedal maint. O Inspedion O Rescue ,

Planned time of entry Entry approved by TLD S/N 0-200mR 0-500mR 0-1.5R 0-5R 0-200R Dos S/N Readin0 Alarm Dos Dos S/N Reading ,

NEUTRON O O O O O .O O  ;

25 TRUNK (FRONT) O O O O O O O

-1 TRUNK (BACK) O O O O O O O 5 HEAD 0 0 0 O O O O 8

@ GONAD D 0 0 0 0 0 0 ,

-4 R. ARM / HAND 0 0 0 0 0 0 0 L ARM / HAND 0 0 0 0 0 0 0 I

L. LEG / ANKLE O O O O O O O DOSIMETRY REQUESTED BY REQUESTED RECElVED BY DOSIMETRY ..

DATE TIME INIT. DOSIMETRY KIT NUMBER 4 [

TLD and SRD serial numbers will be added by dosimetry on lines next to requested block. 1 Kit Assembled Assioned in ERIMS

.,, DATE TIME INIT. DATE TIME ' INIT.

SRD Readings Entered Kit Pulled in ERIMS j$

• DATE TIME INIT. DATE- TIME INIT.

.8 8 Reviewed by Dosimetry Supervisor .

7 ,

A Form 1905.001C to be retained in personnel files {.

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.a k '

2

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