ML20027D939

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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures IP-6 Re Activation of Technical Support Ctr & IP-10 Re Medical Emergency
ML20027D939
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 09/01/1982
From: Fortenberry R, Kitts R, Lorek M
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20027D930 List:
References
PROC-820901-01, NUDOCS 8211100410
Download: ML20027D939 (95)


Text

{{#Wiki_filter:* 4 s (N# / TT.NNESSEE VALLEY AUTHORITY IMPLEMENTING PROCEDURES DOCUMENT - SEQUOYAH NUCLEAR PLANT Inserted by: Issue Date: August 18, 1982 Date Inserted: 9 Revision Log Sheet This log sheet must be retained as the last page of the Sequoyah Nuclear Plant Implementing Procedures Document. Pages to be Removed New Pages to be Inserted Revision / Revision / Part Page Number Date Part Page Number Date Index 1 of 1 Rev. O Index 1 of 1 7/28/82 m IP-6 Cover Page Rev. 2 IP-6 Cover Page Rev. 3 1 of 3 Rev. 2 1 of 4 Rev. 3 2 of 3 Rev. 1- 2 of 4 Rev. 3 3 of 3 Rev. 1 3 of 4 Rev. 3 4 of 4 Rev. 3 Attachment 1 Attachment 1 1 of 1 Rev. I 1 of 1 Rev. 3 l Attachment 2 j 1 of 1 Rev. 3 Attachment 3 1 of 3 Rev. 3 2 of 3 Rev. 3 3 of 3 Rev. 3 IP-10 Cover Page Rev. 5 IP-10 Cover Page Rev. 6 1 of 10 Rev. 5 1 of 10- Rev. 6 2 of 10 Rev. 5 2 of 10 Rev. 6 5 of 10 Rev. 5 5 of 10 Rev. 6 6 of 10 Rev. 5 6 of.10 Rev. 6 7 of 10 Rev. 5 7 of 10 Rev. 6 9 of 10 Rev. 5 9 of 10 Rev. 6

              )                      10  of 10        Rev. 5                               10     of 10       .Rev. 6 V

Page 1 of 2 8211100410 821028 PDR ADOCK 05000327 F pop

4 s Revision Log Sheet (Continued) Issue Date: August 18, 1982 This log sheet must be retained as the last page of the Sequoyah Nuclear Plant Implementing Procedures Document. 1 Pages to be Removed New Pages to be Inserted. Revision /- Revision / Part Page Number -Date Part Page Number Date IP-10 IP-10 (Con't) (Con't) Attachment 1 Attachment 1 1 of 1 Rev. 5 1 of 1 Rev. 6 Attachmerit 2 Attachment 2 1 of 1 Rev. 5' 1 of 1 -Rev. 6 Attachment 3 Attachment 3 1 of 1 Rev. 5 1 of 1 Rev. 6 Attachment 4 Attachment 4 1 of 1 Rev. 5 1 of 1 Rev. 6 Attachment 5 Attachment 5 1 of 1 Rev. 5 1 of 1 Rev. 6 Page 2 of 2

n . - 3 s SQNP SQN-IPD p TABLE OF CONTENTS - Page 1 of 1' ( IMPLEMENTING PROCIDURES INDEX Instr. Revision Title SQN-IP-1 3 Emergency Plan Classification Logic SQN-IP-2 3 Notification of Unusual Event SQN-IP-3 3 Alert SQN-IP-4 3 Site Emergency _ SQN-IP-5 3 Emergency - General Emergency SQN-IP-6 3 Activiation of the Technical Support Center SQN-IP-7 1 Activation of the Operations Support Center SQN-IP-8 6 Personnel Accountability and Evacuation SQN-IP-9 0 Accountability and Evacuation of the Power Operation Training Center

          '\                         SQN-IP-10 6                                   Medical Emergency Procedure SQN-IP-11-3                                   Security and Access Control I

SQN-IP-13 4 Call Lists

                                  ' SQN-IP-14 7                                    Health Physics Procedure SQN-IP-15 1                                   Emergency Exposure Guidelines SQN-IP-16 0                                   Recovery Procedure              .

SQN-IP-17 5 Emergency Equipment and Supplies SQN-IP-18 3 Plant Release Rate Calcula.tions

SQN-IP-19 0 Radiological Emergency Plan Training

! SQN-IP-20 0 Environmental Monitoring During A Radiological Emergency i Revised 7/28/82

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Sequoyah Nuclear Plant DISTRIBUTION

        \-                                                        IC    81' Plant Master File
        ,/
  • IC 83 Asst'. Power. Plant Supt. (Oper.)

SQN REP - IMPLEMENTING 1C 84 Asst. Power Plant Supt. (Maint.) , PROCEDURES DOCUMENT IC 86 Maintenance Supervisor (M) IC 87 Maintenance Supervisor (E) 1C 88 Maintenance Supervisor (I) IC 89 Results Supervisor SQN, IP-6 1C 90 Operations Supervisor IC 92 Health Physics Supervisor 1C- 93 Public Safety Services Supv. ACTIVATION OF THE TECHNICAL IC 95 Outage Director SUPPORT CENTER 1C 96 Emergency Cabinet Control Room IC 97 Emergency Cabinet Communications Room-1C 98 Emergency Van 1C 100 Emergency Cabinet Meteorological Bld. 1C 102 Shift Engineer's Office Prepared By: Ron Fortenberry IC 103 Unit Control Room IC 105 Health Physics Laboratory Revised By: Michael J. Lorek 1C 106 Medical Office IC 107 Resident NRC Inspector - SNP Submitted By:- R.J. Kitts IC 108 Technical Support Center Supe rvisor IC 109 Assistant HP. Supervisor-IC 110 Plant Duty Supervisor IC 111 Asst. Power Plant Supt. (H&S) PORC Review: l [lY- di" i IC OC H&S - John Ingwersen - MS Dktel A Approved By: . .

;                                    Pwr Plt Superintendent                         ,

Date Approved: h Rev. No. Date Revised Pages Rev. No. Date Revised Paaes 0 8/5/80 ALL 1 5/13/81 ALL 1 2 12/8/81 1 3 / b ALL !' The last page of this instruction is Number 9 . I e t.. i [

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SQN-REP-IPD SQN, IP-6 f ~~g Page 2 of 4 Rev. 3 2.5 All necessary materials and equipment are located in the TSC except for hand-held calculators. Hand-held calculators should be obtained from the offices on the way to the TSC. The key to all equipment in the TSC (filing cabinet, chairs, and tables) is located in the SE key cabinet (key #152). 2.6 Unit status update sheets'(Attachment 2) should be used to keep the TSC up to date on plant conditions. The TSC supervisor will appoint a member of the TSC to complete Attachment.2. These sheets should be comple.r.ed at intervals determined by the TSC supervisor. The instruments listed below each parameter are suggested instruments for obtaining the re-quired data. These instruments should be used if possible. However, if these instruments are not available, other instruments may be subs-tituted provided the substituted instrument number and the reason for the substitution are included in the remarks section. The incore thermocouple switch numbers are listed one per quadrant. To avoid confusion, the following is a list of substitution switches for each quadrant. Table 2.6.1 Incore Thermocouple Substitution Switch Numbers (,_

 ;                               Quadrant 1       Quadrant 2               Quadrant 3   Quadrant 4 28              22                     12      .      9 24              58                      8           45 56              21                     40            .6 55              16                      4           46 29              63                      3           42 61              64                      7           36 3.0 REFERENCE MATERIALS AND EQUIPMENT 3.1 The folloiwng reference materials are provided in the TSC:

3.1.1 Sequoyah Nuclear Plant FSAR. l 3.1.2 Sequoyah Nuclear Plant Technical Specifications. 3.1.2 Sequoyah Nuclear Plant Technical Specifications. 3.1.3 Surveillance Instructions (Selected).I 3.1.4' Technical Instructions (Selected).I

            '1 Selection to be made by appropriate section supervisor and approved by assistant superintendent.

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SQN-REP-IPD SQN, IP-6 Page 3 of 4 Rev. 3 3.1.5 Radiological Control Instructions. 3.1.6 Hazard Control Instructions. 3.1.7 System Operating Instructions. 3.1.8 General Operating Instructions. 3.1.9 TVA-REP and REP Implementing Procedures Document 3.1.10 Spill Prevention Control Plan 3.1.11 Plant Functional Drawings. 3.1.12 Abnormal Operating Instructions. 3.1.13 Emergency Operating Instructions. 3.2 The following equipment is provided in the TSC. j 3.2.1 Three. plug-in PAX phones are stored in the file cabinets. The phone jacks are lo_cated_on the north wall of the TSC. The PAX ('- ' phone numbers are . To make the PAX phones operable, remove thE' phones from the filing cabinet and plug

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into one of the phone jacks. 3.2.2 Two plug-in Bell. phones with a speakerphone are stored in one of filing cabinets in the;TSC. The Bell phone jacks are located on the west wall. To make the Bell phone operable, plug the phone. connector.into the Jack and plug,the speakerphone into an AC outlet. The Bell phone numbers are'. On the side of each Bell phone jack is an exclusI3h ' switch. With the exclusion switch in the "off" position, the phone is . a party line with DPSO being the other party. With the switch in the "on" position, th'e phone "is _ a private line disconnecting DPSO.

                     ~". '                    ' The re fo re , the normal positio'n"for the exclusion switch during
                 .gd g..           _           TSC activation.would befin; thel"on" position.           .               ..y.,

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Ring-down' Phones .

                                 -3.2.3                                                _                             ,
                               . 3.2.4         An intercom is stored in one of the filing cabinets located in
                 . in;    _-                   the TSC. The , jacks,.for_theiinterc'om..are located . on the north           _
                  ,_         &                 wall. The intercom is , connected to unit l1 operator, unit 2:

operator, SE's office, " aid'ElecErical control disk'." ' To operate,

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                                             ~ pu sh the buttan momentarily to ring th. control room." Ta.ltr '

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SQN-REP-IPD SQN, IP-6 Page 4 of 4' Rev. 3 3.2.5 A microfiche reader 'is located in the TSC. The purpose is to read the FSAR which is on microfiche. 3.2.6 Located in one of'the filing cabinets is a reasonable supply of office-supplies for use in the TSC. 3.2.7 Located in the TSC is enough tables and chairs for 25 people. 3.2.8 Control room closed-circuit TV. 8 s I r

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Page 1 of 1 Attachment 1 i , Rev. 3 '

i 2
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?-  ; i j SECTION 1. a. Reactor Engineer

b. Shift Technical Advisor

> ( SECTION 2. Mechanical Test and Studies , l SECTION 3. Chemical Engineer l SECTION 4. Instrument Maintenance SECTION 5. Mechanical Maintenance ,

SECTION 6. Electrical Maintenance

I i i i 9 E L l

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4 SQN-REP-IPD SQN, IP-6' [' ')- Page 1 of 1 Rev. 3 Attachment 2 4 UNIT STATUS UPDATE Date Time- Unit

1. Condensate Storage Tank Level, ft. A B (LI-2-230A) (LI-2-233A) e
2. Steam Generator Heat Sink- Condenser. Atmosphere
3. Auxiliary Feedwater Flow Available Yes No
4. Steam Generator Level (narrow range), % 1 2 3 4__

(LI-3-39) (LI-3-52) (LI-3-94) (LI-3-107)

5. Steam Generator Level (wide range) %1 2 3 4 (LI-3-43) (LI-3-98)
6. Steam Generator Pressure, psig 1 2 3 4 (PI-1-2A) (PI-1-9A) (PI-1-20A) (PI-1-27A)
7. Source Range, eps N31 N32 (XI-92-5001B) (XI-92-5002B)
8. Intermediate Range, ma N35 , N36 (EI-92-5003B) (EI-92-5004B)
9. Pressurizer Level, %

(LI-68-335) '(LI-68-320)

10. Pressurizer Pressure, psig Wide' Range Narrow Range (PI-68-342A) (PI-68-340A)
11. Reactor Coolant Loop 4 Hot Leg Pressure, psig (PR-68-66)
12. Reactor Coolant System THot (wide range)*F 1 2- 3 4
(TR-68-1) (TR-68-43)

! 13. Reactor Coolant System TCold ("I * **"8' (TR-68-18) (TR-68-60)

14. Reactor Coolant Pumps running 1 2 3 4
15. Emergency Core Cooling System Status Standby Injection Recirculacion
16. RWST Level, %

(LI-63-50) (LI-63-51)

17. Containment Sump Level, %

(LI-63-176)

                       '18. Containment Spray Flow, gpm                                          A-A                             B-B
                                                                                                    '(FI-72-13)

(FI-72-34)

19. Containment Pressure, paid .

(PI-30-44) (PI-30-45)

20. Incot e Thermocouples , *F 1 2 3 4 (60) (54) (44) (41)

REMARKS: l~ l-I l- Data by: / , j _ _ __

k SQN-REP-IPD SQN, IP-6 Page 1 of 3 Attachment 3-Rev. 3 DIMENSION 400 PBX PHONE SYSTEM Controlled Restriction Group Activation and Cancellation Before any programming may be realized,'a handset must be plugged.into console. The shift engineer and the plant receptionist have handsets if none is available. Step One - To activate the Technical. Support Center phones

1) Press idle loop button (see dwg.; item 12)
2) Press start button - dial tone
3) Dial 121
4) Dial 0 - dial tone
5) Dial 10 - confirmation tone (3 beeps)
6) Press release button Step Two - To restrict phones by restricting the CRG-
1) Press idle loop button
2) Press start button - dial tone
3) Dial 121
4) Dial 4 - dial tone
5) Dial the appropriate Controlled Restriction Group -

confirmation tone

6) Press release button (repeat step two for each Controlled
                                                    . Restriction Group)

Step Three - To activate phones Follow same procedure as step one but use the appropriate Control Restriction Group number in step #5. Following is a list of Controlled Restriction Groups and a diagram of the console. s 1-

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o- . o SQN-REP-IPD SQN, IP Page-3 of 3 Attachment 3 Rev. 3 CONTROLLED RESTRICTION GROUPS (CRG'S) 01 (Bubble Bldg.,_PSO, Dwg. Cont.) . 02 (F1d. Sys.) , 03 (Admin. & Office Bldg.) 04 (Pwr. Stores)- 05 (HP, Rad. Chem,. 06 (Maint. Shop) .- 07 (Mgt. Sys . )-' 08 (Nurse), 09 (QA) 10

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Sequoyah Nuclear Plant -DISTRIBUTION - ( V) 1C 1C 1C 81 Plant Master File 83 Asst. Power Plant Supt. (Oper. ) 84 Asst. Power Plant Supt. (Maint.)

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SQN REP - IMPLEMENTING PROCEDURES DOCUMENT 1C 86 Maintenance Supervisor (M) IC 87 Maintenance Supervisor (E) 1C 88 Maintenance Supervisor (I) SQN, IP-10 lc 89 Results Supervisor 1C 90 Operations Supervisor 1C 92 Health Physics Supervisor . MEDICAL EMERGENCY PROCEDURE 1C 93 Public Safety Services Supv. 1C 95 Outage Director 1C 96 Emergency Cabinet Control Room IC 97 Emergency Cabinet Communications Room 1C 98 Emergency Van 1C 100 Emergency Cabinet Meteorological Bld. 1C 102 Shift Engineer's Office IC 103 Unit Control Room Prepared By: M. B. Knight IC 105 Health Physics Laboratory Revised By: R. J. Kitts 1C 106 Medical Office 1C 107 Resident NRC Inspector - SNP Submitted By: b b.///f$) IC 108 Technical Support Center Mupervisor 1C 109 Assistant HP Supervisor 1C 110 Plant Duty Supervisor m / IC 111 Asst. Power Plant Supt. (H&S , j , PORC Review: b h/h1 1C OC H&S - John Ingwersen - MS j ) .

                                   ' Date'                    "

Approved By: - _ Pwr Pft 3uperintendent Date Approved: [ ' hhM

                                             /

e l Rev. No. Date Revised Pages Rev. No. Date Revised Pages i 0 8/5/80 ALL 4 3/22/82 11 , 1 4/22/81 '11 5 5/21/82 All l 1,2,5,6,7,9,10,11, [ 2 7/15/81 11,12 6 d;l 12,13,14,15 3 10/19/81 12 The last page of this instruction is Number 16 i , v i

SQNP REP-IPD IP-10 Page 1 of 10 Rev. 6 MEDICAL EMERGENCY PROCEDURE 1.0 PURPOSE This procedure outlines the action to be followed during medical emergencies at Sequoyah Nuclear., Plant. 2.0 PROCEDURE 2.1 Initial Reporting and Response to Accident and Emergency Medical Situations 2.1.1 Anyone discovering a serious injury or other medical emergency should administer aid for any life-threatening situation.

                                                                        ~

2.1.2 Summon any available personnel in the area for assistance. i 2.1.3 Notify the control room on PAX phones and state, "This is A medical emergency and not a fire," so that the control room 9, operator can initiate the appropriate response. 2.1.4 Give the control room operator your name, the location of the j emergency (including building, elevation, and column coordinates), a the type of medical emergency and the number of people involved.

                                             Also, give the PAX telephone number from which you are calling and if the emergency is in a regulated area.

2.1.5 Initate such actions as may be needed to avoid further injury - to the victim or injury to other personnel. 2.1.6 As emergency response personnel arrive', assist them as requested

                                                             ~

and give any pertinent information they require relating to the injury or illness. 2.1.7 Notify your supervisor and assist as requested in report preparation and followup. 2.2 Activation of Medical Emergency Response Team ' ~""-

                                            ^                                         '     '                '
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[' 2.2.1 'ThE controi room op'erator or the assistant Ahift engineer ,shallh

a. Initiate activation of the emergency response team, -and announce over the public address system, the location of

_ the. medica.1 emergency; _ _ . __ ._,_

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b. ~ Notify ~the shift engineer of the emergency.

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 /                                                                                IP-10
 \                                                                                Page 2 of 10 Rev. 6 2.2,2 - A roster 1.isting all names and telephone numbers of the 'indi-j                                   viduals and local agenies required to either respond to or provide support for the medical emergency wiLL be provided 'to the Plant Duty Supervisor and the Shift Engineer, 2.2.3  The shift engineer wil4 notify the' nurse on duty who, if necessary, wil4 proceed to the emergency site.

2.2,4 The shift engineer will request the necessary information from heal-th physics personnel . Medical and Puhtic Safety may he required to assist thn shift engineer in completion of Attachment 1. 2.2.5 When a patient is transported to a hospital, the shift engineer-wiIl notify the receiving facility of the patient's - condition, the estimated time of arrival, and the radiological status of the patient as determined by health physics, 2.2.6 If necessary, the shiit engineer will request that Puhtic Safety arrange for an ambulance (offsite or onsite) for trans-porting of injured personnel, I 2.3 Organization and Duties of the Medi-cal Emargency Response Team V 2.3.1 The medical emergency respons,e team consists of a health physics representative, an assistant shift engineer, public safety officer, (or individual trained in first ai<l or emergency medical response), and nurse. The team will be supported by assistant unit operators who have received supplemental first aid training. 2.3.2 Duties and responsibilities of the various members of the response team: > 2.3.2.1 Team Leader (assistant shift engineer)

a. The team 1eader wi.14 take charge and direct the total activities while consulting with_ members of the team in their area of expertise; i i
h. Lead the team in and out of the area by the most .

direct and/or appropriate route (with proper considerations of hazards to members of the team with the operational functioning of the facility). If the patient is located in a contaminated aone, a minimum number of response personnel wi4l- enter the area initially. Protective clothing wilt he

                                                                         , as a minimum (shoe covers, gloves, at the discreation 4                                                  'of health physics). Additional personnel. may Csj                                                                     he requested by team leader.

r . . i- SQNP sm ,s'

                 )                                                                                                   REP-IPD IP-10 Page 5 of 10 Rev. 6 2.4.4.         A doctor should be requested, when in the nurse's judgment (or other personnel trained in emergency medical care) further
  • professional attention is needed prior to transport such as' in a problem with extrication where the patient needs medical attention while' extrication-is being accomplished. Always .

keep in mind the goal of maximum benefit.to the patient. 2.4.5 Transport patient to the emergency treatment area or health station (or nearby TVA medical office) unless patient's s , condition is such that immediate transport to a hospital F is necessary. 4 2.4.6 If a' patient. requires. ambulance transportation to a medical : ' office or hospital, utilize the TVA ambulance before contacting a commercial' ambulance service. .When necessary, the shift. engineer will request an ambulance (onsite or offsite) from Public Safety for transporting injured personnel. 1 2.4.7 . The health physic representative (s) will actlas advisor to the emergency response team and medical personnel concerning-radiological conditions. i

2.5 Patient Care Guidelines for Special Conditions

. 2.5.1- - General Guidelines i The care and disposition of all'ill and injured persons known or suspected to be associated with radiation exposure or ' contamination will be coordinated with the health physics representative. .The essential aims of the medical-health physics team are:

1. Minimize injury and further radiation exposure to the victim.
2. Protect attending personnel from excessive and unnecessary radiation exposure.
3. Control spread of radioactivity contamination..
4. Access and document the patient's radiological exposure.
5. Immediate lifesaving and disability limiting procedures will take precedence.over noncritical decontamination
                                                                           .and dosimetry assessment procedures.

j 2.5.2 Classification and handling of. radiologically exposed or contaminated individuals. i 4

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REP-IPD 8 IP-10 Page 6 of 10

                                                                                      'Rev. 6.

2.5.2.1 Irradiated-Noncontaminated First remove the victim from further exposure providing only essential first aid.in the process, then direct' attention to medical care of other physical injuries. The patient is then transported wherever necessary~ for adequate initial care of his . illness or injuries. The health physics. technician determines and reports thef type and level of exposure and the affected, area-of the body if possible. Medical care of the radia-tion exposureLis governed by the medical status'of the patient and the findings of the health physicist. In most cases, the treatment of illness or physical

                                                           .               injury takes precedence over treatment for radiation exposure.

In general,.the' medical treatment for radiation exposure should be related to the total dose received. Therefore, several major decisions points should be looked for: 2.5.2.1.1' Individuals who have-received an acute. total body dose' of less than 5 rem usually ' require no medical examination or treatment for the radiation exposure. l 4 -2.5.2.1.2 Individuals who have received an acute total l- body dose of between 5 -and 75 rem radiation - can usually be treated as an outpatient, i. but should have hematological studies. i performed to detect chromosomal aberrations l and other changes in other blood . constituents. Attachments 2 and 3 give laboratory directions W for drawing blood samples for chromosomal and hematological studies.

      ~

_SQWP REP-IPD _ [N' IP-10 ('s s Page 7 of 10 Rev. 6 2.5.2.1.3 For individuals who have received an~ acute total body dose greater than 75 rem, evalua-tion by a nuclear medicina specialist shall ha arranged regardless of physical injurias or illnesses. This is the minimat dose that produces a recognizahla reaction in about 10 to 20 percent of the individuate exposed. Blood studies should be drawn per directions (attachments 2 and 3). If the patient is 4b ill or injured requiring attention for physical j illnesses or injurien, he should be trans-ported to Erlanger Medical- Center (see 9f Attachments 4 & 5) with the information that this patient has received an acute total hody done greater than 75 rem. It is recommended that the attending physician consult REAC/TS.- If the patient is not seriously i11 or injured enough to requiva hospitalization Jor physical illness or injury, and with the recommendation of REAC/TS, referral may he made to Oak 4p Ridge Hospitat (see attachment 6) or the [ \ United Methodist Church where the patient could ( ,/ _ he observed and treated by the physicians on the REAC/TS team. 2.5.2.1.4 If a worker's projected cumulative dose to the thyroid from inhalation- of radioactive iodine might exceed 10 rems, the Medical. Director has authorized responsible health physicists or other qualified individuals to offer the exposed person an immediate first dose of a course of potassium iodine. l The time the first dose was administered

abould be documented and the individual should be referred to the health station or l

a TVA medical office. Anyone authorized to initiate KI shall be familiar with the Food and Drug Administration approved package insert, and be rare that each proposed recipient is similarly informed.- The initial dona of KT should not he delayed and those who hagin therapy should continue the 10-day course of KT- unless their thyroid dose is determined not to have exceeded 10 rem. An adequate supply of KI is stored at each nuclear _ facility to supply any personnel exposed to radioactiva iodina. It is i es \ , supplied in bottles which contain a full l 10-day dose regimen. Follow dosage schedulas ((_,/ . as outlinad on the. package insert accompanyi-ng f each bottle of KI.- l l l t t-

j .. , , . SQNP N REP-IPD ' I IP-10

                                    .                       Page 9 of 10 1Rev. 6 2.5.2.2.1.2    In cases of less severe injuries, the patient will be sent to the personnel decontamination' room to remove as much.contam-ination as possible before he is treated.in the emergency treatment area or transferred
               *~                                                          to Erlanger Medical Center.

2.5.3 The health physicist will collect, identify, label and analyze all biological specimens as required and deemed necessary. He.will obtain the , injured person's personnel dosimetry and replace, with equivalent -dosimetry if- appropriate. 2.5.4 The health physics group will also maintain supplies _to control contamination and protect members of'the medical emergency response team during. transport within the plant and to the receiving hospital. Medical emergency response team members and medical personnel will don and maintain whatever personal protective _ equipment y the health physics representative may require. . When a contam-e inated patient is transported to a - receiving hoepitai facility Q a health physics representative should accompany the patient to the hospital and should furnish as much information as possible about the patient's dose and type of radiological contamination and/or exposure to the receiving facility _ (see attachment 1). At the hospital, a health physics representative wi31 furnish radiological services to attending physicians and hospital personnel as requested. . 2.6 Guidelines for Followup Medical Care Followup medical care of illnesses oc injuries treated in the health station or TVA medical office are usually done in the health station or y TVA medical of'fice. If the patient has been referred to a private physician or receiving hospital, followup medical care is usually done by the private physician unless the patient is released or followup medical care is requested from Medical Services by the private physician. In such instances, followup medical care will be arranged through the health stations and TVA medical offices. b  % 4- .-

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  \s_-                                                     Page 10 of Id Rev. 6        S                                         '(T-2.7 Notification Guidelines                                                                                    ,
                                                                                                                                                \

2,7,1 The area medical chief or his designee or the area nursing , supervi.sor or her designee should be notified by the plant nurse or someone designated by her/him in the following instances. 2,7.1.1 If someone is ill or injured to the extent that they  %; 5 d require amhutance transportation to a hospital . receiving facility. 2.7.1.2 If the number of injuries is above that normally expected to be handled during the. normal o[eiation s I of a health stetion. ' )i t 4g i/ 2.7.1.3 Anytime there is a situation existing in the fthility which creates a~ hazardous environment where there is an i-ncreased liklihood of radiological exposure and/oc

                  #                           contamination cue increased physical risk so that injuries are more 1ikely to occur than during normat operating conditions.
    ),/               2.7.2      If the Area Medical Chief and the Area Chief Nurse or,th ir designee cannot he contacted, then notify the Medical Director or Medical- Services Representative of CECC if activated.

4 2,7.2,1 Health Physics should notify the Area Medi. cal Chief ' ' anytime a TVA personnel receives radiation exposure in excess of the recommended TVA occupationak y [ exposure 1-imits. i N ( l N k 1 4 i

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('v) Attachment 1 - Page 1 of 1 Rev. 6 RADIATION AND/OR MEDICAL EMERGENCY NOTIFICATION REPORT To be used by' shift engineer to enter available data' for notification of a receiving hospital of the impending admission of a case involving a medical emergency ~ radiation exposure or contamination. , Nature of Accident Extent and Discription of Injuries Treatment Provided Condition: Good Fair Serious Critical Deceased

                             ' B/P                 Pulse                 Respiration Treated in Medical Office: Yes                             No                    Time:

( A. Person Making Notification: Name __ Date Time Title Telephone Plant B. Patients to be Admitted: Total Number: I Name-fif available) Injury but no Radiation Internal External -Contamina-Radiation or Exposure Contamina- Contamina- ted Wounds Contamination tion tion l l C. Will patients be: Surveyed for Contamination? Decontaminated? I y- D. Expected Time of Arrival at Erlanger Hospital: Notification Taken by: ,. -~s (v) l i i P s pa+- t-+ - -y we* -m y yv ----y y wwwr y- ,- +- v-w, -r-y-g -- g

     ,        d SQNP REP-IPD TP-10 C                                                                             Attachenent 2 Page.t of 1 Rev. 6 INSTRUCTIONS FOR. LYMPit0CYTE CUT.TURING FOR CYTOGMRTIC DOSR-4                           ESTIMATION OF LOW-LEVEL WOLK BODY ACUTE OVER EXPOSURR TO IONIZING RADIATION TVA has an agreement with the Oak Ridge Associated Univerr.ities Cytogenetics y        Laboratory (ORAU) to perform lymphocyte culturing to provide cytogenetic estimate                                           -

of radiation dose. Upon the order of a responsihte physician and after arrangements have been coordinated with ORAU/RRAC/TS, concerning the transport and arrival time of the specimen, the following procedure should be followad: The blood should he collected in a red top vacutainer (Cat No. 2-657-3, Bd No. 4671) to which has been added 0.1 mL of sodiiun heparin (Upjohn 1000 units). Mix by inversion 30 times in 30 seconds immediately a f ter collection. Blood samples must he kept cook- (not frozen) during shipping and storage. The vacutainers should be packed in Styrofoam chips, packing straw, etc. Surround packing material with a coolant and ship in a wen-insulated container. Do not put the tubes directly on any coolant that may freeze the samples. 7 Identify the samples with the patient's name, hirthdate, social security numbar, date and location, Samples should be shipped by the fastest available carrier, suyh as TVA courier, air, or coaunercial carrier to: ORAU/REAC/TS Cyto Genetics Laboratory Attn: Gayle Littlefield or Gene Joiner

                            . Medical and Health Sciences Divison Oak Ridan Tennessee 37830 r

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                                                                                                                   -Page 1 of 1
                                                                                                                     .Rev. 6 y                                                                                         LYMPHOCYTE CULTURING Collection Method:                                                                                       Type Container:

Blood - Red top vacutainer #4671 to which has been added 0.1 ml-Serum of sodiuin heparin (Upjohn 1000 units). Plasma Urine Sputum Other~ Wen: Upon order of responsible TVA M.D. in coordination with REAC/TS, after confirmed exposure exceeding 5 rem of total body ionizing radiation. Frequency: Once, unless otherwise directed by responsible medical authority. [ Special Instructions: Refrigerate,.but do_not freeze in shipping. containers

  .g                                                                     ~ provided' for this' purpose. See attached memorandum.

Were Sent: ORAU/REAC/TS Cytogenetics Laboratory ~ Attention: Gayle Littlefield or Gene Joiner Medical and Health Sciences Division Oak Ridge,. Tennessee' 37830 _~

                        -Special Notice: ~ Notify Earl-Jordan!at;                             Oyjg extension N g , Chattanooga      .

g Report Results to: 1RobertL.Crhig,'(M.D. . a Medical Director.: +. n

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SECONDARY ROUTE g - - . ' m . ALTERNATE ROUTE 4 n [, _ Primary Route is as Follows: ua.s...,u Leave Sequoyah Nuclear Plant via Sequoyah Road to - m ,,,, (7 Highway 27 (6.3 miles) Highway 27 to Highway 153 C (6.6 miles) Highway 153 to C. B. Robinson Connecto Road (4.2 miles) C. B. Robinson Connector Road t ""#*"*"" Amnicola Highway (2.5 miles) Amnicola Highway a Riverside Drive (2.6 miles) (See Locality Map - f W.(for the following) Riverside Drive to 3rd Street Exit (1.5 miles) 3rd Street Exit to 4th # NkykE5 Street via Mabel Street (0.1 mile) 4th Strgt rO ,

                                                                                                                                            **8g4 to Erlanger Hospital via Lansing Street O                               -                #,                                             e ~ jf       y 503rdStreet(0.6 mile).                                                                                                  "                  P, 0
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                      .                   CHATTAN000A-.                                                                                                            

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4 6 ... , (h k l v TENNESSEE VALLEY AUTHORITY MUSCLE SHOALS EMERGENCY CONTROL CENTER - IMPLEMENTING PROCEDURES DOCUMENT REVISION LOG SHEET Issue Date: September 1, 1982 ~ This log sheet must be retained as the last page of the Muscle Shoals Emergency Control Center Implementing Procedures Document. Inserted by: Date Inserted:

                                                                                  ~

Pages to be Removed New Pages to be Inserted Revision / Revision / Part Page Number Date Part Page Number Date r IP-2 Cover Page Rev. 1 IP-2 Cover Page Rev. 2 3 of 4 Rev. 1 3 of 4 Rev. 2 4 of 4 Rev. 1 4 of 4 Rev. 2. IP-5 Cover Page Rev. 1 IP-5 Cover Pag ~e Rev. 2 1 of 9 Rev. 0 1 of 10 Rev. 2 2 of 9 Rev. 0 2 of 10 Rev. 2-3 of 9 Rev. 0 3 of 10 Rev. 2 4 of 9 Rev. 0 4 of 10 Rev. 2 5 of 9 Rev. 0 5 of 10 - Rev. 2 6 of 9 Rev. 0 6 of 10 Rev. 2 7 of 9 Rev. 1 7 of 10 Rev. 2 8 of 9 Rev. 0 8 of 10 Rev. 9 of 9 Rev. 0 9 of 10 Rev. 2 1- 10 of 10 Rev. 2 IP-7 Cover Page Rev. 1 IP-7 Cover Page Rev. 2' I of 11 Rev. I 1 of 11 Rev. 2 2 of 11 Rev. I 2 of 11 Rev. 2 3 of 11 Rev. 1 3 of 11 Rev. 2 4 of 11 Rev. 1 4 of 11 Rev. 2 5 of 11 Rev. 1 5 of 11 Rev. 2 j l 6 of 11 Rev. 0 6 of 11 Rev. 2 U

w'  ;> - MUSCLE SHOALS EMERGENCY CONTROL CENTER i IMPLEMENTING-PROCEDURES DOCUMENT REVISION LOG SHEET Issue Date: ~ Septemb'er 1, .1982 Pages'to be' Removed New Pages to'be Inserted' Revision /- . Revision / Part Page Number Date Part Paae Number Date IP-7 (cont'd) IP-7 7 of-11 Rev. 0 7 of 11 Rev. 2. 8 of 11 Rev. 0 8 of 11 Rev.'2' 9 of 11 Rev. 0 9 of 11 Rev. 2' 10 of 11' Rev. 0 10 of'11 Rev. 2 11 of 11' Rev. 0 11 of 11 Rev. 2 IP-8 Cover Page Rev. 0~ IP-8 Cover Page Rev. 1-IP-10 Cover Page Rev. 2 IP-10. Cover Page .Rev. 3 Attachment 1 Atttchment 1-17 of 69 Rev.L2' 17 of 69 Rev. 3 18 of 69- Rev. 2 18 of 69 Rev.-3 19 of 69 Rev. 2 19 of 69 Rev.-3' 29 of 69 Rev. 2 29 of 69 Rev. 3 30 of 69 Rev.' 2 '30 of.69 Rev.:3 46 of 69 Rev. 2 46 of-69 Rev. 3~ 47 of 69 Rev. 2 47 of 69 Rev. 3. 48 of 69 Rev. 2 48 of 69 Rev. 3 57 of 69 Rev. 2 57 of 69 - Rev. 3-i 58 of 69 Rev. 2 58 of 69. Rev. 3 59 of 69 Rev. 2 59 of 69 Rev. 3' 64 of 69 Rev. 2 64 of 69 Rev. 3 l- 65 of 69 Rev. 2 65~of 69 .Rev. 3 Attachment 2 Attachment 2 i 29 of 31 Rev. 2 29 of 31 Revi 3 30'of 31 Rev. 2 30-of 31 Rev. 3 l^ i l

e ,:. i

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REP-IPD/EC-IPD Cover Page REP-IPD

 '                                                                                                                                                                   MSECC, IP  .

Site Emergency,'or General Emergency MSECC Director Prepared By: 2 ) W s t.sy _, Approved'By: -

                                                               =Date:                                                    9/25/81 Rev. No.                                 Date                         Revised Pages                                     Rev. No.           'Date Revised Pages 0                       9/25/81                                      All 1                    ~2/17/82                                     All 9/1/82
                                                                                                                                                              ~

2 3&4 The last page of this procedure is Number :6 . 1

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

3  :,.

                                                                                                                                  -Pagi 3 of_4 MSEC-IPD
  • IP-2 Rev.' 2 v

6.3.2- Emergency Worker Support 6.3.2.1 Continuous Operation for Long Period of Time (By Materials Support)- 1 The MSEC Material Support Coordinator schedules manpower,.

  • supplies, food, etc. , to ' sustain the operations . if the' MSEC or . *-

field teams are staffed for long periods of time. Personnel are scheduled for 24-hour operation until the' emergency is termi- , nated. The shifts for the MSEC Director Environs Assessment

  • Supervisor, and Dose Assessment Supervisor are scheduled so that-at least one-hour overlap is provided. All other personnel
;                              require at least 30-minute overlap. Work schedules will be                                                                 *-

submitted to the appropriate supervisor to be approved. -*

6.3.2.2 The Field Coordinator ensures through the Material Support j Coordinator that manpower, equipment, food, etc. , are provided; for field personnel including screening teams, terrestrial and aquatic monitoring teams and couriers who are on duty for' long-periods of time. The shifts for the Field Coordinator require a 1-hour overlap. All other field personnel require a 30-minute overlap. The Field Coordinator will provide a list of people *-

for the Material Support Coordinator to call.

  • 6.3.3 Recommendations for Protective Actions (By Dose Assessment Supervisor)
     \.j                                                                                                                        ~

In the early stages of any accident the Shift Engineer at the plant is prepared and trained to initially recommend protective actions to State and local officials. i When the MSEC is properly staffed, the MSEC Director takes *

over the responsibility to recommend protective actions to the CECC I!ealth and Safety representative, or in his absence, the -

CEC (, Director. The CECC Director is notified of this chang'e.in ! responsibility by the MSEC Director.

  • i

, 6.3.4 Communications with State Agencies l 6.3.4.1 The Dose Assessment Supervisor has the. responsibility to keep the State agencies informed of any change in plant status and/or release rate. Hourly 'or as appropriate, he will provide the I State with the information specified in MSEC IP-10,' Attachment 3.

  • 6.3.4.2 The Field Coordinator is in touch with the coordinator of the l State environmental monitoring teams. He is responsible for ensuring that the State Coordinator is aware of TVA team l positions and for forwarding requests from the State to the
MSEC. He is also responsible for providing field. data to the *-
l. MSEC.
  • t I

I -_ _ _ . _ - - _ _ . _ _ . . _ - . _ . . _ _ _ _ __ _ _ _ , _ _ . . - . . . . . - . _ . . _ _ _ _ _ . , _ _ . . , - - . . - -

 -,         a Pegn 4 of 4 MSEC-IPD
  • IP-2 i r""N Rev.-2 6.4 The MSEC Director decides if it is necessary to request
  • communications assistance from NASA. If the van is needed see the TVA Radiological Emergency Notification Directory for phone numbers.

6.5 Shutdown of the MSEC Upon Accident Termination 4 6.5.1 The MSEC is shut down on mutual agreement between the MSEC

  • Director and the CECC Director. In general,-this should not be considered until (1) all issues of environmental contamination are cleared up and it is known that no further public exposure is occurring, and (2) all abnormal inplant radiation protection problems are under control.

6.5.2 After the MSEC is shutdown, ensure that:

  • 6.5.2.1 All personal logs are placed in lifetime storage.

6.5.2.2 All tapes are placed in lifetime storage. 6.5.2.3 A detailed, written summary of the accident is prepared and forwarded to the State. 7.0 MSEC Director Checklist

  • A checklist is provided in attachment 2 for quick reference by the MSEC Director. This procedure shall be well understood
  • before use of the checklist.

i i i O

              ._ - ._             ....        . ..             .                            __             _ . _ _ - _                     _       . _     _        ._- _           _ .... . . . ~. __..                  _ .
                      .o REP-IPD/EC-IPD. Cover Page 4

REP-IPD. MSECC, IP-5 1 Training Procedures ' Prepared By: , tw % %-

                                                                                                                                                                                                                                  ~

Approved By: ) ' ' f. Date: 9/25/81 Rev. No. Date Revised Pages Rev. No. Date- Revised Pages 0 9/25/81 All . l 1 12/31/81' 7

2 9/1/82 All' The last page of this procedure.is Number - 10 .

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sl .u ~. MSEC-IPD

                                                                                                                                                           'IP-5 Page 1 of 10 Rev. 2
,V.                                                                            -

TRAINING PROCEDURES' , 1.0 PURPOSE These procedures specify the' training provided emergency control ~ center and offsite, support.' agency personnel and delegates the responsibility.for providing-the training. 2.0 SCOPE

- The procedures cover the training' of CECC, DNPEC, KEC, and MSEC-staff, and offsite support services; defines responsibility for providing and for ensuring training is provided; and describes i' the training documentation.

t

3.0 REFERENCES

BFN Radiological Emergency Plan A

4.0 ABBREVIATIONS AND DEFINITIONS None 5.0 RESPONSIBILITIES The Division 'of Occupational Health and Safety. (OCH&S) is respon-r sible for training -the MSEC staff and coordinating the' training among the CECC, DNPEC, KEC, and MSEC staffs. OCH&S is respon-l sible for approving lesson plans for training given the CECC, DNPEC, and KECC staffs. OCH&S-is responsible for training desig-- nated offsite support agencies, l 1. 6.0 PROCEDURE REQUIREMENT 6.1 Training Lessons The lesson plans for all training are reviewed by OCH&S to assure compatibility among divisions and with the BFN-REP.' l l 6.2 Training Records Records ^ for training . include the lesson plan, class duration, persons attending, and'date. These records'are maintained by l- OCH&S. l l l l .

      .,,,,...._...-..m_.....--.           . . . . . _ . .. .                ,     . . - . _ . . - _ _ . , _ _ _ . . . - _         _ - - - _ , _ _ _ . -   .  ,.._..--,J.-.~.--..-g  _ _ . . . . . .

MSEC-IPD IP-5 _s Page 2 of 10

              \                                                                                                                Rev. 2 6 ~. 3  Specific Training Requirements 6.3.1
                                                                                                          ~

Emergency Control Center Training-4

                                            -The staffs of the~CECC,-DNPEC, KEC, and MSEC are trained annually on: scope of operations, functicas of the various emergency centers, lines of authority, and communications. The overview for this training is prepared by OCH&S and the training administered by the responsible divisions.

6.3.2 MSEC Director

 +

The MSEC Director and alternates are trained at yearly intervals in order to ensure appropriate coordination and response of.the MSEC. The training includes the following:

1. Notification and emergency activation.
2. Probable input information. l-i
3. Protective action options under various circumstances.

N

4. Communications.
5. Coordination of support personnel.
6. Interagency coordination of response.

6.3.3 MSEC Material Support Coordinator The MSEC Manpower Coordinator and' alternates are trained at yearly intervals to ensure proper scheduling of and supplies to manpower during an emergency. l The training includes the following:

1. Notification and Emergency activation.
2. Scheduling requirements of appropriate personnel, i
3. Supply needs of emergency personnel.
4. Resources available to meet supply needs, manpower, and
supplies.

l I m s

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i

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

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                                                                                                   . MSEC-IPD IP-5 Page 3 of 10 -
     '"'j                                                                                           Rev. 2 6.3.4     Dose Assessors The Dose Assessors are. trained at semiannual' intervals in order
                                     'to ensure 'each member is capable of estimating doses..to the public via the liquid and gaseous pathways.

The training includes the following:

1. Notification and emergency activation.

i

2. Dose procedures for liquid releases,. including Water Systems Development Branch capabilities.
3. Dose procedures for releases to the atmosphere, including input.
4. Review of data notebooks - use of Air Resources Program (ARP) input.
5. Example scenarios.

1 6.3.5 Environs Coordinator The Environs Coordinator and alternates are trained at yearly intervals in order to coordinate collection of environs data by TVA and State or DOE teams: The training includes the following: i 1. Notification and Emergency activation.

2. Communications capability.

l 3. Monitoring team equipment. } 4. Manpower resources.

                                      .5.      Map reading.

4 6.3.6 Laboratory Supervisor The Laboratory Supervisor and alternates are trained at yearly intervals in order to ensure proper coordination of-laboratory analyses, i The training includes the following:

1. Anticipated kinds of environmental samples.
2. Needed results of analysis, including identification and quantification of important radionuclides.

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MSEC-IPD IP-5 Page 4 of 10

                /           h                                                                                                                           Rev. 2
3. Sample turh-around time requirements.
4. ' Manpower resources.
5. Coordination of sample collection and delivery.

6.3.7 Dosimetry Supervisor The Dosimetry Supervisor and alternates are trained at yearly intervals in order to ensure proper coordination of dosimetric analyses. The training includes the following:

1. Review monitoring locations.
2. Review collection of and readout turn-around times.
3. Manpower and dosimetry resources.

6.3.8 Environs SITE Coordinator The Environs SITE Coordinator and alternates are trained at yearly intervals to ensure proper staffing and coordination of a monitoring teams.

               \

! The training includes the following:

1. Notification and emergency activation.
2. Communications.
3. Transportation needs and options.
4. Monitoring team equipment.

. 5. Manpower resources.

6. Map reading.

6.3.9 Health Physics Group Supervisor The Health Physics Group Supervisor and alternates are trained at yearly intervals to ensure proper response by plant health physics personnel. The training includes the following: ? k 4

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

i .- MSEC-IPD' IP-5 Page 5 of 10 Rev. 2

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1. Notification and Emergency activation.
2. Manpower resources.
3. Anticipated manpower requirements for environmental ' survey teams.
4. Coordination. of inplant and environmental monitoring.
5. Communications.

J ! 6. Monitoring equipment. 4 6.3.10 CRT Operators Cathode ray terminal operators are trained at yearly int'ervals to ensure proper communication of data. The training includes the following:

1. Notification and emergency activation
2. Use of high speed fascimile machines 1 3. Use of CRT terminals
4. Use of printers
5. Information flow within the MSEC 6.3.11 Communications Coordinator-The communications coordinator ensures that all channels of communication operate properly in-the' MSEC.

The training includes the following: 4

1. Notification and emergency activation
2. Use of the 40 channel recorder
3. The Horizon phone system-
4. The electronic blackboard
5. The emergency communications data system
6. Repair contacts
7. Information flow within the center MSEC-IPD IP-5 Page 6~of 10 Rev. 2'
   \

6.3.12 Clerical Support 4 The. clerical support are trained at yearly intervals to ensure proper recording of events. The training includes the following: 1

1. Notification and Emergency activation.
2. Recording equipment operation and use.
3. Staffs requiring clerical support.
4. Communications. systems operation and use.
5. Use of maps and status boards.

6.3.13 Telephone Operators The operators who may have to make notifications are.t'ained r initially and on a quarterly basis. . Training will include .tenni-nology to be used and notification procedures.

        -%s        6.3.14   Division of Water Resources (s_            6.3.14.1 MSEC Representatives The MSEC representative and alternates of the Divisions of Water Resources (W-RES) and Natural Resource Operations (NR ops) are trained at yearly intervals to. ensure proper coordination of matters related to water resources.

The training includes the following:

1. Notification and emergency activation.
2. Communications.
3. Familiarity with specific reservoirs around the plants.

. 4. Dispersion mo'dels. ) 6.3.14.2 Reservoir Operations Branch (ROB) The Reservoir O'perations Branch will provide support. data to W RES as needed for calculations. Training will be provided as other special data needs arise. d 4

MSEC-IPD:

                                                                                                                                         'IP-5 Page 7 of 10 1

('~' Rev. 2 6.3.14.3 Water' Systems Development Branch (WSDB) The WSDB personnel. responsible for radiological emergency re-4 sponse are trained at yearly intervals to ensure that appropriate estimates of liquid dispersion are provided to dose assessment personnel at the MSECC. 4 The training covers the following areas:

1. Dispersien models and procedures.
2. Communications.
3. Notification and emergency activation.

1

4. Needed input data and. contacts.

6.3.14.4 Water Quality Branch-The Water Quality' Branch staff are trained at yearly intervals in order to ensure that staff members can supply appropriate advice to Field Operations and the Water Resources Coordinator regarding the effects of radiological contamination of water systems. They

               -s                                      are trained in the following areas:

(, 1. Communications.

2. Manpower resources.
6.3.14.5 Fisheries and' Aquatic Ecology Branch The Fisheries and Aquatic Ecology. Branch staff are trained at-yearly intervals in order to ensure that staff members can supply approprite advice to Field Operations ~and the Water Resources Coordinator regarding the effects of radiological' contaminants on

! aquatic biota. They are trained in the effects of radiological ( contaminants on aquatic biota and communications. 6.3.14.6 Field Operations (FO) The Field Operations staff are trained at yearly intervals in order to ensure that water samples are taken at the appropriate location in the appropriate manner, verifying travel time calcu-lations, and effects of radiological contaminants.

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          ;,:n-MSEC-IPD 11P-5 Page 8 of 10 '

t j T 'Rev. 2-

                                    .They are trained'in the following areas:
1. Radiological movement.- surface water and ground water
                                          . quality and' aquatic biota.
2. Communications.
3. Sampling procedures.

6.3.15 Air Resources' Program 6.3.15.1 -Weather Corporation of America (WCA) WCA provides forecasts in support of the REP. . Forecasts are issued daily for each nuclear plant in' order to maintain forecast skill. WCA participates in drills and exercises at least annually to ensure familiarity with forecast format and procedures. 6.3.15.2 Air Resources Assessment Section (ARAS) The Air Resources Assessment Section staff are trained at yearly intervals in order to ensure that each staff member is capable of realistically representing the dispersion of gaseous radiological effluents. The training includes the'following:

1. Data.needs on meteorological conditions and forecast to the MSEC.
2. Supplying advice regarding gaseous radiological effluent dispersion and transport based on meteorological data.

S

3. Assisting in trajectory analysis of effluent' transport.
4. Communicating meteorological information to involved State Health Departments.

t 6.3.16 Data Service Branch / Environmental Data Station The Environmental Data Station staff are trained at yearly inter-i vals in order to ensure that each staff member is aware of needed i onsite meteorological data provided to the MFC and can assure , timely procurement. , 6.3.17 Agreement Hospital Personnel at agreement hospitals are trained annually. The 4 hospital administrator, in consultation with the proper OCH&S l representative, determines the site, time, date, and personnel to be trained.

m;.

MSEC-IPD [3 IP-5 . ..

     $f
     ?y" Page 9 of 10 Rev. 2!                    )

(I D Training includes the following:

1. ' Radiation fundamentals.
2. Biological effects of Radiation.
3. Portable radiation detection instrumentation. .
4. Handling of contaminated patients.
                                                                   ~

6.'3.18 Agreement Ambulance Service and Rescue Squads Appropriate personnel of -ambulance service and rescue squad are trained annually. The ambulance service manager or rescue a gaad chief, in consultation with the proper RHB representative, deter-- minen the site, time, and'date of training and personnel to be - trained. The training includes the following: ,

1. Radiation fundamentals.
2. Portable radiatica detection instrumentation.
3. Transportation accidents. involving radioactive material.
4. Handling of contaminated patients.

. 5. Medical facilities which accept radiation accident patients.

6 . 3. ~19 Environs Emergency Teams f

' Each environs emergency team member are trained'at yearly I intervals. The training includes the following:

1. Radiation fundamentals
2. Portable radiaton detection instrumentation-
3. Er.vironmental sampling
4. Emergency kit contents and usage
5. Communications
6. Map reading
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(,; - :, .  ; x- MSEC-IPD: Q 1- IP-5 '! [. g' Page 10 of 10

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                                                                                                                         .Rev. 2-                           . .

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             .6.4         -New Procedures                                                                                                                       ,

When new procedures are issued or-changes are made to existing

  • procedures, each member of the MSEC needing to know the infor- ' .:

mation receives a copy of the change or procedure. - t I

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4 1 1-i i s REP-IPD/EC-IPD Cover Page REP-IPD i MSECC, IP-7 Air Resources Program Procedures  !

  • Muscle Shoals Emergency center .

Prepared By: ,ym . Approved By: .. - Date: 9/25/81 I i Rev. No. Date Revised Pages Rev. No. Date Revised Pages 1 0 9/25/81 All M 1 12/31/81 1,2,3,4,5 2 9/1/82 All i The last page of this procedure is Number 11 . l r

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MSEC-IPD IP-7

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Page 1 of 11 6"Ng Rev. 2 I 3 AIR RESOURCES PROGRAM PROCEDURES

                                 . MUSCLE SHOALS EMERGENCY CENTER 1.0 PURPOSE These procedures are designed to direct the activities of the Weather Corporation of America and the Assessment Section personnel during a radiological emergency to provide a timely response, consistent and accurate meteorological data, and assessment advice in the event of a nuclear accident.

2.0 SCOPE These procedures cover anticipated requirements for meteoro-logical support during emergency conditions. The procedures do-not cover additional actions to be taken prior and subsequent to an emergency or drill or to maintain response capabilities routinely.

3.0 REFERENCES

None l , 4.0 ABBREVIATIONS AND DEFINITIONS l 4.1 ARP - Air Resources Program 4.2 WCA - Weather Corporation of America 4.3 AS - Assessment Section of the ARP 4.4 MSEC - Muscle Shoals Emergency Center 4.5 NRC - Nuclear Regulatory Commission 4.6 EDS - Environmental Data Station (at each nuclear plant site) 4.7 F0 - Field Operations (NR OPS) 5.0 RESPONSIBILITIES 5.1 Upon notification by the MSEC that an emergency condition exists, the AS Meteorologist notifies individuals and organizations specified in section 6.1 (Initial Notification) of this procedure. In addition, he performs.the duties of his position as described in the procedures O provided in this document. WCA begins issuing forecasts for the affected plant as described in these procedures. MSEC-IPD-

                                                                                                                                                            - IP-7 Page 2 of 11
                                                                                                                                                           - Rev. 2 j                                     -5.2              WCA and AS emergency personnel are meteorological' forecasters and dispersion assessment meteorologists, respectively.                                                                                         ;

5.2.1 WCA. responsibilities. include preparation of forecasts of wind' speed and direction, stability class, and precipitation type and intensity. WCA is also responsible for applying backup procedures for the replacement of missing or garbled data. 1

 ~

5.2.2 AS responsibilities include transferring real time and forecast meteorological data to the MSEC staff; providing expert advice on combinations of individual measurements (wind speed, wind direction, and stability class interval heights) that' most realistically represent dispersion and transport of radiological effluent in the ' atmosphere, without being nonconservative;- and performing trajectory analysis of effluent transport. The AS , will advise the MSEC staff whenever backup procedures are in use - in lieu of real time data, and will indicate the level of con- - 4 fidence in the procedures being used. Also included are responses to questions from appropriate State officials and maintaining a logbook for recording emergency (or drill) contacts l and activities of the AS. 5.2.3 -F0 is responsible for operation and maintenance of EDS and asso-ciated monitoring systems.

                       )

6.0 PROCEDURE REQUIREMENTS 6.1 Initial Notification The WCA Duty Forecaster and a member of the AS emergency team of meteorologists are notified according to the Radiological Emer-gency Notification Directory. 6.1.1 The AS Meteorologist responding to the. emergency notification by ' the MSEC notifies the AS Supervisor as soon as possible and notifies (directly or by message) the Chief of the ARP- or the , person acting in his behalf. ! 6.1.2 The notification time, time of arrival at the MSEC, and name of the plant experiencing the emergency are entered in the AS j ' logbook by the AS Meteorologist as soon after arrival as possible. Y r l s

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MSEC-IPD IP-7 Page 3 of 11 6.2 AS Recordkeeping 6.2.1 , A logbook is maintained in which the AS meteorologists record pertinent information regarding WCA and AS response and support to the MSEC and communications between AS meteorologists and appropriate State officials. ' 6.2.2 Pertinent meteorological data are recorded on four forms. The plant and time of the emergency, the release geometry, and plume transport and dispersion information are entered on the Coversheet for Radiological Emergency (form 2a). This form also provides space for updating such information. Real time 15-minute averages of meteorological data from the plant site are entered on the Report of Raw Meteorological Data and Conversions for Radiological Emergency (form 2b). Hourly average data are also entered on form 2b. The Meteorological Information (form 3) provides the MSEC staff with information for dispersion calcul-ations. Form 4, Meteorological Data for Trajectory Analysis is an optional form consolidating four hours of data for estimating effluent transport. Cop'ies of these forms are placed in a three-ring binder as the

   ,_,              information dissemination is completed. The binder is kept at
 /      j           the AS meteorologist station during an emergency or drill, and in (v/                the AS office otherwise.

6.3 Meteorological Data Communications Equipment 6.3.1 Communications equipment consists of an Alden weather facsimile recorder and teletypewriter terminals which receive real-time meteorological data via dedicated telephone lines (one each for Browns Ferry, Sequoyah, and Watts Bar to date) from the onsite environmental data stations (EDS). Real time meteorological data are provided to the MSEC and WCA via an interrogable remote access system. 6.3.2 Equipment repair in case of malfunction is effected by contacting TVA or private contract repairmen for NWS data equipment, and NUC PR for the real time data transmission system. Onsite data can be obtained by telephone from the EDS, if necessary. 6.3.3 A portable generator for backup power capability allows the restoration of power if regular power is lost. 6.4 Basic Procedures of Operation 6.4.1 All communications, including entries in logbooks and on forms, use Central time (eitbar Daylight Savings Time or Standard Time, as applicable). n I \

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l MSEC-IPD IP-7 Page 4 of 11 Rev. 2 4 6.4.2- Within 30 minutes of notification, WCA will prepare an initial forecast'for 1 and 2 hours in the future. .The forecast param-eters are wind speed and direction for'three onsite tower levels, stability class for two layers, and precipitation type and intensity. The forecast data will be transmitted ~via the remote access system. Backup transmission will be by telecopier or by1 voice. An example of.the forecast format is given on page 6.

                                                                                                                         ~

The information sheet on page 7 provides basic .information for-use in forecast preparation. 6.4.3 The AS Meteorologist will report to the MSEC as soon as possible after being notified (within 15 minutes during work hours). He-will complete form 2a, ' extract wind and- stability data ifrom the most recent 15-minute averages from the plant site, and enter the-data and conversions on form 2b. The forecast- data (form'1) and converted real time data (form 2b).are entered on form 3. Copies of form 3 are provided to the MSEC staff every 15 minutes. Pertinent information is entered on the weather status board in the MSEC. 6.4.4 Within one hour after notification, the WCA Forecaster will prepare an updated and expanded forecast for the same parameters and levels as the initial forecast. Th' forecast will be for 1, 2, 4, 6, and 8 hours in the future. These forecasts will be updated each hour until the end of the emergency, or upon re-quest. An outlook for hours 9 through 24 in the future will also

     ,,/

be provided in the hourly updates. The outlook will indicate either persistence or change for each parameter (wind direction, wind speed, stability,~and precipitation). The approximate time-of change (s) and the approximate magnitude of the change (s) will be given. 6.4.5 The AS Meteorologist provides 15-minute average meteorological data for every 15-minute period (form 3) to the MSEC. Hourly average data, converted for MSEC use (form 2b), are also entered on form 3 and provided for every hour, beginning with the first hour received after provision of the first set of 15-minute averages. 6.4.6 The AS Meteorologist or AS Supervisor plots 15-minute vector-sequence trajectories, on the appropriate site map at the MSEC. 6.4.7 The AS Meteorologist responds to questions from State officials concerning meteorological information. 6.4.8 As meteorological conditions change or are projected to change, the AS Meteorologist provides recommendations for altering the-

                                                                     ~

combination of parameter levels being used for atmospheric dis- < persion and transport calculations to reflect the new conditions.

      ~
       .,      , _ . - , - - . , , - + - - , , , , _ ,                 , - . , , -
                                                                                   -v.-- . . _ , . ,-_y-. - -    ,         ,     _ _ , , - -e   m.

I

                                                                                        ~ MSEC-IPD:

IP-7 Page 5 of 11 Rev. 2

                 ~6 . 4 '. 9      The AS Meteorologist documents decisions, recommendations, and pertinent communications in the AS Logbook and inserts all com-pleted copies of forms 2a through 4 in the AS ring binder.

6.4.10 If the real time wind speed, wind direction, or stability class

                                 'used for dose calculations are missing or garbled, WCA or the AS -

meteorologist will apply backup procedures provided by TVA or approved by TVA to determine estimated values for the missing ' variables. The estimated values will be entered into the remote adcess system within five minutes of the observation time, as feasible. 6.5 Requirements for Shift Relief 6.5.1 WCA maintains a forecast staff on duty 24 hours a day. Addi-- tional forecasters are called in if needed. 6.5.2 The AS Meteorologist will normally work a 9-hour shift, with a one-hour overlap between shift periods. In addition, a second AS Meteorologist (not notified initially) is available to assist, if necessary. l

z. -- - - . - . . - -_- - .-,.-,-_-.-.;.._-_.-. _- -__ _ _ - . _ - _ _

s MSEC-IPD TP-7 Page 6 of 11 N . , Rev'. 2 .

           \
     \                                                                                                                         i
               ** TITLE **    1                           MET DATA REPORT           29-JAN-82          07:17:14                                                     ;
               **PAGE NUMBER        1       29-JAN-82              07:17:14 CDT**       SEQ. NO.                 5             OUTBOUND s

1 MET DATA REPORT WEATHER CORPORATION OF AMERICA O (- ' SPECIAL RADIOLOGICAL EMERGENCY METEOROLOGICAL FORECAST , s ( BROWNS FERRY DATE : 29-JAN-82 LEVELS: UPPER-U INTERMEDAITE-I LOWER-L  ; , s .  ; BASE TIME OF FORCAST i0700 , ( /' STABILITY WIND DIRECTION ANS SPEED (M/S) CLASS PRECIPITATION i TIME U I L U-I/I-L (RATE CATEGORY) %

  • 3 0700 114/ 6.4 92/ 4.0 75/ 1.6 F/E NONE 0800 120/ 6.2 100/ 4.3 90/ 1.9 E/D NONE q 0900 115/ 6.5 105/ 4.4 100/ 2.2 D/D , NONE 1100 137/ 5.3 120/ 4.9 D/D NONE fs
     \            1300 147/

5.6 135/ 7.2 145/ 6.7 130/ 6.5 D/D NONE s 1500 157/ 7.7-155/ 7.1'140/ 7.0 D/D NONE e

                **PAGE NUMBER        2      29-JAN-82              07:17:14 CDT**         SED. NO.                3            OUTBOUND 1                      MET DATA REPORT D/D                          LR 1900 167/ 10.1 165/ 6.8 150/ 5.4                                                                LR.

2300 172/ 10.8 170/ 7.3 155/ 5.9 D/D . D/D LR 0300 192/ 9.3 190/ 6.3 175/ 4.9 0700 207/ 10.8 205/ 7 3>190/ 5.9 D/D LP'

  • COMMENTS -

l AIR FLOW TO CONTINUE TO CH4NGE THRU THE S0llTHEAST AS CENTER OF HIGH PRESSURE MOVES FROM THE APPALACHIAN RIDGES TO THE EAST COAST TODAY. INCREASINGLY MOIST s AIR TO LEAD TO RAIN SHOWER DEVELOPMENT LATER TODAY, *

                                                                                                                                               \

BUT THE PEAK RAINS ARE FORECAST FOR SATURDAY. , GG/PL 0717 CST END

                 .STOP.                                                \                                                             1 l                                                                                                                                  .

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                                                                                          -    --.-n,         ,  p.. p                 y                               -        ,

MSEC-IPD IP-7 Page 7 of 11 s Rev. 2

                            \

t INSTRUCTION SHEET FOR SPECIAL RADIOLOGICAL EMERGENCY METEOROLOGICAL FORECAST Pasquill Stability Index

                                   \
                                ;           -Pasquill Categories                       Temperatute Channe with Heiaht (*C/100m)

( A AT/AZ { -1.9 B -1.9 ( AT/AZ { -1.7

                                                                                             -1.7 ( AT/AZ { -1.5 C

D -1.5 ( AT/AZ { -0.5 E -0.5 ( AT/AZ { -1.5 F 1.5 ( AT/AZ { 4.0 G 4.0 ( AT/AZ Sensor Heiahts (Meters) Browns Ferry Sequoyah Watts Bar U I L U I L U I L i j,

  • Wind Direction 92.6 45.7 10.4 91.4 46.6 9.7 91.5 46.4 9.7 and Speed ,

i Temperature 89.6 45.3 10.0 90.8 46.0 9.3 91.2 45.6 9.5 l Class Limits

Precipitation None, LR (0.3 - 2.5 mm/hr)

HR (2.8 - 7.6 mm/hr) HR (>7.6 mm/hr) s' i. Comments l Used to qualify precipitation as follows: Continuous (Intensity changes gradually, if at all); Intermittent (Intensity changes gradually, if at all, but precipitation stops and starts at least once per hour); Showery (Precipitation changes intensity or starts and stops abruptly). Other comments and qualifiers may be added as necessary. Comments pertaining to wind direction variability and assessments of forecast confidence will be especially valuable. - l.

MSEC-IFD

                                                                 -       IP-7 Page 8 of 11 Rev. 2 pq Actual / Simulated                   Form 2a Coversheet for Radiological Emergency Nuclear Plant                                            Date Time of Emergency                                        Preparer Instrument Levels: U         M        L Release Point                               Release Time Release Geometry Level of Transport Wind Measurement:                 Meters U M L Level of Wind Speed for Dispersion:                   Meters U M L Stability Layer for Dispersion:             to        Meters U-L U-M M-L Update Time:                                             Preparer Release Geometry Level of Transport Wind Measurement:                  Meters U M L Level of Wind Speed for Dispersion:                   Meters U M L Stability Layer for Dispersion:             to        Meters U-L U-M M-L

! Update Time: Preparer Release Geometry Level of Transport Wind Measurement: Meters U M L Level of Wind Speed for Dispersion: Meters U M L Stability Layer for Dispersion: to Meters U-L U-M M-L h J F-MSEC-IPD IP-7 Page 9 of 11 Rev. 2 Form 2b

                 ' Report of Raw Meteorological Data and Conversions for Radiological Emergency j              Date                            Nuclear Plant                      Preparer Level of Transport Wind           Level of Wind Speed:

, Measurement: U I L U I L Stability Layer: U-L, U-I, I-L 15-Minute Observation Trajectory dd Plume dir b Qi8Persion ff TT 15 min Travel ff AT/AZ j Time" Level (dea) (m/s) (*C) (den / sect) (miles) (m/s) (*C/100m) Stab l 14 U U-L I U-I' L I-L' 29 U U-L I U-I . n L I-L

    /

44 U U-L . I U-I L I-L l 59 'U U-L I U-I L I-L Hourly Observation dd Pers ff TT Plume dir 1 Hr Travel

  • ff* AT/AZ Time Level (deg) (Pet) (m/s) (*C) (des / sect) (miles) (m/s) (*C/100m) Stab' 00 U- U-L I U-I L- I-L Sol Rad Rnf (mm)
a. Observed data are 15 minute averages ending at the time indicated,
b. Equals wind speed (m/s) x 0.559 mi s/m.

di Observed data are 1 hr averages ending at the time indicated.

c. Equals wind speed (m/s) x 2.236 mi s/m.
                                                                                                                                     ~
       %                                                            %                                                  [~'N            .
              )

s O> . Form 3 Meteorological Information Distribution: MSECC Director NRC Dose Assessment Environs Assessment Date: Release geometry: Person transmitting data: Level of transport wind direction'j ^ Person receiving data: Level of wind speed for dispersion : Nuclear Plant: Stability layer for dispersion *: to Observed .Datab (15-minute averages) Forecast Data Central Time Plume Dispersion for which Plume Dispersion Central Direction Wind Speed Stability Forecast Direction Wind Speed Stability Time (22.5* Sector) (m/s) Class is made (22.5' Sector) (m/s) Class Precip., Observed Datab (1-hour average) Plume Dispersion Outlook for hours 9 through 24 in the future: Central Direction Wind Speed Stability Plume Time (22.5* Sector) (m/s) Class Precip." Direction Dispersion Stability Valid (22.5* Sector) Wind Speed Class Precip.c Comments: I

a. Indicate' as upper, middle, or lower.
b. Conditions for period ending at indicated time.
c. Light rain' (TR), moderate rain (MR), and heavy rain (ER);hourlyvaluefor0.01in{LR{0.10in; {[yl for MR, 0.11 in { MR { 0.30 in; and for HR)0.30 in. . m -a p
                                                                                                                            "# 5   4 o

m

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

 ,                                                                                                                                                                                                           MSEC-IPD IP-7 Page 11 of 11 Rev. 2 Form 4

! Meteoroloaical Data for Trajectory " Analysis - Radioloaical Emeraency Drill Date Preparer Plant 1^ Release Point Release Time Level of wind measurement meters Plume 15-minute

  • direction travel T_ime_ (dearees) (miles) t i

i 1 4 1

                                                                                                                                                                                                                                                                    +

d s i l l l l i 1 l l \ l l l l

  • Equals wind speed (mph) + 4 or wind speed (m/s) 0.559.  !

1-l i

                                                                                                                                  . _ , . - . , , , , . _ _ . - , ,    , - - , - - - , , - _..            .,        ..__.,.__ __......_, ,,              __r. . ..

r

 =   ..

REP-IPD/EC-IPD Cover Page REP-IPD MSECC, IP-8 WATER RESOURCES RADIOLOGICAL EMERGENCY PROCEDURES Prepared By: R. D. Urban 9.D b

  • Prepared By: A. H. Smalley N s#ms
  • Approved By: R. H. Brooks
  • Approved By: M. G, Maarsa L d, LWp V

Date: September 29, 1981 Rev. No. Date Revised Pages Rev. No. Date Revised Panes-0 11/13/81 All 1 09/01/82 , Cover Page The last page of this procedure is Number 21. O

                               .~ . -.             -             - _ - .          .   ..      .-         ..     ..       . .
                                                  ~ REP-IPD/EC-IPD Cover Page REP-IPD MSECC, IP-10 Dose Assessment Staff Activities During Nuclear Plant Radiological Emergencies 2

fs

                                                                                                                     ~

Prepared by: j th /- i[. Approved by: -- 7 i Date: .4/29/82 Rev. No. _Date Revised.Pages Rev. No. Date Revised Pages 0 9/25/81 All 1 3/02/82 Add 56 __ 2 4/29/82 All

                                              ~31-33,43,44, 3               9/1/82    60-62,71-73,.

78,79,117,118 The last page of this procedure is Number 125 , l I

                                                            '                                                                                                   PJge 17 of'69 MSEC -IPD IP-10
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                                 ...          t                                                                                 MSEC -IPD IP-10
                                              '!                           Table 1S Attachment 1

[(/]) i i l D*U/0 Values * - Table 1S Rev. 3 Type I Releases

                             ?

l; Stacks Total Body Doses I_,,.___..__... . 8 i Ait1I.I i Y ! ,1 M if. f: Is E l' fi 1 [ 8. I ' A B 4.12E-10 d.14E-lO 4.14F-10 .t .1 1E- 10

              ...            4.49F-10   'i.99E-10        4.?5E-10                                                                    4.15E-10 4.30E-10              4.07E-10         1 . 1 1.L - 1 0    4.15F-10
               >...            3.05C-10   6 12E-10 4.o'E-10        4.08E-10 '4.13E 10                    4.lHE-10 2 12E-10   G.84E-LO          4.48E-10                                                                   4.21E-10 4.70E-10             3.95E-10         4.04E-10 4.11 E- i O
                   .a          1.S3E-10   5.46E-10 3.99E-10 4.07E-10                     4.18E-10 9.9             1 31E-10   4.81E-10          4.92E-10             3.88E-10 3.82E-10         3 94E-10 4.04E-10                    4.15E-10 10             1.18E-10   4.23E-10          S.13E-10                                                                    4.04E-10 4.5'7E-10           3 48E-10         3.66E-10 3.84E-10 1.G            8 52E-11   2.07E-10 3.37E-10 3 42F-10                     3.VSE-10 2.0             6.78E-11    1.09E-10          3.6VE-10            3.25E-10 3.81E-10 7.31E-11
                                                     ~

2.99E-10 3.19E-10 3.12E-10 3.40E-10 25 5 48E-11 2 89E-10 3.19 E - 2 0 3.68E-10 4.90E-11 6 24E-11 '2. 4 6 E--10 3.30E-10 3.0 2 00E-10 3 04E-10' '? . 7.2 E - 10 2.98E-10 4.51E-10

                 *s . 3        4.31E-ti    5.48E-11                                                                  2.80E-10            4.34E-10 4.0           3 85E-11    4 90E-11            1.70E-10          2 81E-10         2 38E-10 2 47E-10            2 66E-10          3.24E-10 4.S            3 49E-11   4.44E-11            1.46E-10           2.63E-10 1.27E-10           2.47E-10         2.37F 10           2. 'i3E- 10       3 13E.10 5.0            3.20E-11   4.07E-11 2.33E-10          2.95F-10 6.0            2.74E-11   3 49E-11            1.00E-10           2.22E-10         2.21E-10 8.20E-11           2.03E-10         2.08E-10           2 17E-10           .?.81E-10

[m] 7.0 8.6 2.41E-11 2.16E-11 3.07E-11 2.74E-11 6.76E-11 1.82E-10 1.94E-10 2.00E- t o  ?.61E-10 S.69E-11 1.64E-10 'i.83E-10 1.86F-10 7.44E-10 1.95E-11 2.47E-11 1.74E-10 7 30E-10 2.24E-11 4.88E-11 1.50E-10 1.73E-10 Q'90 14.'

                  ..h 0        1 79E-11
                                't.53E-11 1.35E-L1 1.93E-11 1.70E-11 3.74E-11 3.01E-11
1. *? 8 E - 10 1.10F-10 1.58E-10 1.43E-10 1.55E-10 1.40F-10 1.20E-10 2.0 /E-10 1.89F-10 L.74E-10 1.21E-11 1.52E-11 *2 . 51 E- 11 9.64E-11 1. 31 E- 1.0 16.9 1.1.9 F- 10 1.6?F 1 09E-11 1.38E-11 2.14E-11 8.54F-11 1.21F-10 t0.0
1. 27 E-- 11 1 85E-11 7.67E-11 1.12F-10 1.10E-10 1 521-10' 20.o L.00E-11 9.53E-11 1.32E-lo 8.33E-12 1.06E-11 1.43E-11 6.04E-11 9.57E-11
               '5.0                                                                                                    H . 4 9E--11       1.1 F:E- 10 9.16E-12            1 23E-11           4.91E-11         8 . 32,E- 11 30.'              7.19E-12                                                            1.40E-11          7 . 4 9 E-- 1 1    I.07E    .0 3' . . o          6.35E-12   8.090--1?           1.08E-11           4.11E-11 7.06F-11           9.Rir t 1 3.53E-11         A . 401'- 11
               .t o . .          5.70E-12   7.26E-1? ' 9.61E-12                                     6.10E-11           6.66F- 11          Y.17E L1 4 'i . s       5.19E-12   6.63E-12 '8.71F-1?                     3 . 09 E- 1.1 5.61E-11           4.36E-11           H.62E-11 50 0              4.77E-12   6.12E-12 ~7.98E-12                     2.73E-11
                    *D U/Q ( rem /h)/(pCi/m)

D rem /h li m/s y nGI/es t .

i h)
                                                                                      ,f.,                       *Revi' sed Complete Page 1                                                .

Pcgs 47 of 69

                                                                                     . MSEC -IPD.
  -                                                                                   -IP-10.                     ,

O Tabla 2S . Attachment-1 Table 2S. D.U/Q ' Values * --

                                            - Inhalation of Iodine-131                             ,

Stack Stability Class Miles A B C D- E F --- C 09 1.30E-0". 1.35E-05 8.32E-07. 0.0 0. 0 : 0.0 . 0.0 0.6 7.82E-06 1.65E-05 2.86E-06 ,1.14E-to 0.0 0 . 0. 0.0 0.7 4.79E-06 1'.67E-05 S.64E-06 '1.91E-09 0.0 0.0 -0.0 0.8 3.34E-06 1.53E-05' 8.29E 1.31E 0.0 0.0 0.0 0.9 2.94E-06 1.34E-05 1.04E-05 5.30E-08 2 .' 09 E- 1 1 0 .'O

                                                              ~

0.0-1.0 2.67E-06 1.14E-05 1.19E-05 1.53E-07 2 0'7E-10' -0.0 0.0 1.5 1.88E-06 4.93E-06' 1.32E-05 .2.55E-06 9. 7.9E-0 8 ; . 0. 0 00 2.0 1'.47E-06 2.37E-06 1.05E-05 6.11E-06' 8.40E-07. 1.51'E-10 0.0 2.5 1.22E-06 1.59E'06 8 .~ 04 E-06 : ./.67E-04^ .I.70F-06 1.95E-09 0.0 3.0 t.05E-06 1.35E 6.32E-06 8.31E-06 2.5HE-04 .1~. 03E -08 J 0.0 3.5 9.16E-07 1.18E-04 5.18E-06 8.95E 4.02E-04 5.19E-0:1 ' O.0 4.0 3.14E-07 1.06E-06 4.30F-06 8.85E-06. 5.0 4E -06 1.34E-07 0.0-4.5 7.37E-07 ?.57E-07 3.63E-06 8.44E-06 5.67E-06 2.46E 1 04E-1L 5.0 4.73E-07 8.75E-07 3.11E-06 7.99E-06 4.1MF-04 4.01E-07.. 5 22E-lt' 4.0 5.77E-07 7.45E-07 2.36E 7.19E-04 6.85E-04 8.51E-07 '6.74F-10 7.0 5.09E-07 6.51E-07 1.88E-04 7.06E-06 9.50F-06 3 . 63 E--0 6 - 5.86E-03 8.0 4.SoE-07 5.79E-07 1.54E-06 6.70E 1.17E-05 1.03E-05 1.51E 9.0' 4,13E-07 5.23E-07 1.28E 5.90E-06 1.10E-05 1.20E-05 2.99E-06' 10.C 3.78E-07 ~ 4.78E-07 1.09E-06 -5.24E 1.04E-05 1.34E-05' 5.0'6E 12.0 3.24E-07 4.09E-07 -8.20E-07 4.24E-06 9.18E-06 .1.54E 1.10E-05 14.0 2.85E-07 3.40E 6.47E-07 3.51E-06 8.18E-06 '1.65E-05 E1 84E-05 16.0 2.55E-07 3 23E-07 5.32E-07 -2'98E-06 . 7.37E-06 1.69E-05 2 .' 65E-0 5 - 18.0 2.31E-07 2.94E-07 4.48E-07 2.57E-04 6.66E-06 1.68E-05. 1.31E-05 20.0 2.12E-07 2.70E-07 3.84E-07. 2.24E-04 6.04E-06.~t.62E-05 3.74E-05' 25.0 1.76E-07 2.25E-07 3.03E-07 1.'7E-06 4 4.78E-06= 1.38E-05'.3.69E-05' 30.0 1.52E-07 1.94E-07 2.60F-07 1.30E 06 3.90E-06 1.13E -05 3.07E-05: 35.0 1.34E-07 1.71E-07 2.28t .1.05E-06 3.28E-06 9.62E-04 2 42F 40.0 1. 21 E-0~7 1.54E-07 2.04E-07 8.79E-07 2 83E-06 8.42E-04.12.31E-05 45.0 L.LOE-07 1.'40E-07 1~.85E-07 7.55E-07 2.49E-06 7.54E-06 2.08E-05 50.-0 1.01E-07 1.30E-07 1.69E-07 6.59E-07' 2.21E-06 6.83E-06. 1 89F-05

               *D.U/Q ( rem /h)/(DCi/m)
                .D  rem /h U m/s Q pC1/s
  • Revised Complete Page A)
.(J Pigs 48 of 69' MSEC -IPD Table'3S                                        IP-10'

{g , Attachment 1. - D.U/Q' Values * - Table 3S. . Drinking Cow Milk h .

                                                                           '                                Rev. 3-
                                                                                                                ~

Stack _, . 1

                                                                                      ^

Stability Class Miles A B C D E F G 0.3 9.86E-03 '1.02E-02 6.20E-04 6.64E-10 0.0_ 0.0- 0.0' . 0.6 5.40E-03 1.25E-02 2.16E-03. 8 61E-08 0.0 0.0 00 0.7- 3.62E-03 1.26E-02 4.26E-03 1.44E-06 0.0 0.0 0.0 i IO.8 2.52E-03 1.16E-02 .6.26E-03 ~ 9.93F-06 .3.57E-10 0.0 0.0 0.1 2.22E-03 1.01E-02 7.87E-03 -4.00E-05 L.58E-08 0 . 0' 0.0 1.0 2.02E-03. 8.61E-03 9.01E-03 L.16E-04 1 57E-07 0.0' O.0

                 .t.5    1 42E-03 3.72E-03      9.94E-03 1.92E-03 7.'40E-05 0.0 _.                               0.0 2.0     1.11E-03      1.79E-03 7.91E-03 4.61E-03 6.34E-04 1'.14E-07                             0.0 2.3 9.22E-04          1.20E-03  6.08E-03 5.80E-03 1 28E-03 1.47E-06                             0.0 3.0 7.90E-04          1.02E-03  4.78E-03 6.28E-03 1.95E-03 '7.79E-06 0.0-3.5 6.92E-04 8'.92E-04          3.91E-03 6.76E-03. 3.04E-03 3.92E-05 0.0 4.0 6.16E-04 7.98E-04           3.20E-03 6.68E-03 3.81E-G3 1.01E-04 1.96E-10 4.5 5.56E-04 7.23E-04           2.74E-03 6.37E-03 4.2GE-03 1.86E-04 -7 89E i                 5.0 5 03E-04 6.61E-04          2 35E-03 6.03E-03 4'.64E-03 d.03E 04' 3.94E-08 6.0 4.36E-04 5.63E-04            1.78E-03 5.43E-03 5.17E-03 6.43E-04 5.09E-07 7.0     3.34E-04 4.92E-04        1.4?E-03 5 . 33F--03 7.18E-03 2.74E-03 4.43E-05                          -

i J.0 3.44E-04 4.37E-04 l.16E-03 5.06E-03 3 82E-03 7.75E-03 ' 1 ~.14 E--0 3 g 3.0 3.12E 3.95E-04 9.n7E-04 4.46E-03 8.33E-03 9.05E-03 ?.26E-03 110.0 2.84E-04 T.e1E-Oa 8.22E-04 3 96E-03 7.83E-03 1.01E-02 3.82E-03 . d 12.0  ?.45E-04 3.09E-04 14.0 2.15E-04 2.72E-04 A.20E-04 3.20E-03 6.93E-03 '1.16E-02 8.33E-03. 4.89E-04 2.65E-03 -6.18E-03 1.25E-02 1.41E-02 16.0 1.93E-04 2.44E-04 4.02E-04 '2.25E-03 5.57E-03 1.28E-02 2.00E-02 L8.0 1.75E-04 2.22E-04 3.3HE 1.94E-03 5.03E 1.27E-02 2.50E 20.0 1.60E-04 2.04E-04 2.90E-04 1 70E 4 56E 1 23E-02 2.83E-02 25.0 1.33E-04 1.70E-04 2.29E-04 1.26E-03 3.61E-03. 1.04E-02 2.79E-02 30.0 1 15E-04 1.46E-04 1.96E-04 9.79E-04 2 95E-03 8.57F-03. 2 . 3 2 E-- 0 2.. 35.0 1.01E-04 1.29E-04 1.72E-04 7.92E-04~ 2.4nE 7.27E-03' 1.9RE-02 10.0 9.12E-05 1.16E-04 1.54E-04 6.64E-04 0.14E-03 6.36E-03 1.74E-07 !~ 45.0 8.31E-05 1.06E-04 1. 4 0E -0 4 5.70E-04 1.88E-03 5.70E-03 1. 37 E--02 50.0 7.64E-05 9.79E-05 1.28E-04 4.98E-04 1.47E-03 S.16E-03 1.43E-02

                 *D.U/Q ( rea/h)/(pci/m)

D rem /h U m/s Q pC1/s '38 1 release rate , g

  • Revised Complete Page V '

t .: l ... 1..

                                                                    ,-                                                                                                                      t i

r Page 57'of 69 : ' '*' l

                                                                                                                                   - MSEC -IPD                             L*-
                                                                                                                                   ' IP-10
                                                                                                                                   ~ Attachment 1                                      L,I I,

f, G s Cover Page __

                                                                                                                                   . Tables'.7G-10~

Rev. 3. . f Il . s e i l i

                                                                                                                   -x U/Q                                                              -l   :
                                                                                                                                                                                       .'I l

), Plume Width .l Multiplication Factors: l tj Limits'of Detection'. t i

                                                                                                                                                                                            +

t

                                                                                                                                                                                       .. ;l
                                                                                                                                                                                       ~,

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                                                                                                                                                                                                                                                                                                             ~    !

e E P 4

Paga 58 of 69 -

  • r
  • MSEC -IPD e j 'IP-10 Attachment 1 N- Table 7G 4 L .

Rev.3 1 Table 7C . 2

                                                                        -y*U/Q Value d
;                                                                         Cround Level                                                         ,

a Stability Class Milec A, B- C D E F C O.5- 5.65E-06 2 56E-05 ~6.15E-05 1 61E-04 2.74E-04 4.82E-04 .8.10E-04

                  ~0.6 .3.12E-06' 1.76E-05 4.'48E-05'. 1.26E-04            2.17E-04,14.08E-04      -

6.91E-04 L 0.7 -1.83E-06 1.26E-05. 3.43E-05 -1 01E-04 1 77E-04 3.48E-04 -6.21E-04: 2 0.8 1'.33E-06 9.24E-06 2.72E-05 8 34E-05' 1.48E-04 3.00E-04: 5.62E-04

                      ~                                                                     '

I

                 - 0 .~ 9 '1.13E-06 ~ 7 00E 2.23E-05 7.01E-05 1 26E-04 2.42E-04 5.12E-04
. 1.0 1.02E-06 5.45E-06 1.86E-05. 5.99E-05 1.09E-04 2.30E-04 ' 4.'66E-04 '

i 1.5- 7 19E-07 1.96E 9.18E-04 3 27E-05 6.23E-05 1.38E-04 3.15E-04

2.0 5.63E-07 9.11E 5.59E-06 2 12E-05 4.18E-OS 9.55E-05 -2.31E-04

! .2.5 4.66E-07 6.06E 3.86E-06 1.53E-05 '3.10E-05 7.24E-05 1.79E-04'

3.0 3 99E-07 5.14E-07 2.86E-06. 1.17E-05 2.43E-05 5.77E 1.46E-04 3.5- 3.49E-07 -4.50E-07 2.23E-06 9 38E-06' 1. 99E-05 ' 4. 82E 1.~23E-04
             .      4.0 3 11E-07 4 02E-07                         1.80E-061 7.76E-06 1.68E-05 4.14E-05 .1.06E-04 4.5 2.81E-07 3.64E-07 1.49E-06 6.57E-06 1.45E-05 3.42E-05 .9 34E-05' 5.0 2.56E-07 3 33E-07.-1.26E-06 5.67E-06 1~.27E-05 3 21E-05 8.30E-05 6.0 2 20E-07 2.84E-07 9.37E-07' 4.39E 1.01E-05' 2.40E-05 6.74E-05                                                     E-7.0 1.93E-07 2.47E-07 ~ 7.30E-07 3 55E 8.31E-06' 2 17E-05 S.64E-05' 4

80 -1.73E-07 2.19E-07 5.88E-07 2 95E 7.03E-06 '1.85E-05 4.83E-05 9.0 1 56E-07 1.98E-07 4.89E-07 2.51E-06' 4.07E-06 1.62E-05 '4.22E-05 . . -10.0 1.43E-07 1.81E-07 4.14E-07' 2 17E-06 5.33E-06. 1.~43E-05 3.73E-05 j- 12.0 ~ '1 23E-07 1.55E-07 3.11E-07 1.69E-06 4.25E-06, 1.'16E 3.03E-05 . 14.0 1.08E-07 1 36E-07 .2.45E-07 1.37E 3 51E-04 -9.76E-06 -2.54E-05 l 16.0 9 64E-08 1.22E-07 2.01E-07 1.15E-06 3.01E-06 8.43E 2.20E-05 [ 18.0 '8.74E-08 1 11E-07 1.69E-07 9.80E-07 '2.63E-06 7.41E 06 1.95E-05 20.0 '8 00E-08. 1.02E-07 1.45E-07 8.51E 2.33E-06 '6 40E-06 ~ -1.74E-05 I 25.0: 6.66E-08 8.48E-08 1.14E-07 4.28E-07' 1.80E-06 5 18E-06 1.38E-05 30.0 5.74E-08 7.31E-08 9.80E-08 4 89E-07 1.47E-06' 4.26E-06 1.'15E-05 35.0 5'.07E-08 6.44E-08 8.60E-08 3.96E-07 1.24E'06 3.62E-06 9.81E-06'

40.0 4.56E-08 5.80E-08 7.69E-08 3.32E-07 1.07E-06 3 17E-06 8.65E-06 45.0 4 15E-08 5 30E-08 6.97E-08 2 85E-07 9,37E 2.84E-06 7.78E-06 50.0 3.82E-00 4 89E-08 6.39E-08 2.49E-07 8.35E-07 2.57E-06 7.09E-06 i

l y.U/Q (m *) I x pC1/m 3 t U m/s ' Q 11Ci/s h, t-

         .-.            -,-.a-.--.        , . - - - . . - . . . . - - . _ , , -.:,...-                                                           -

l i 'e.. < Pega 59 cf 69 l MSEC'-IPD Attachment 1' l

        ,                                                                           Table 7S                                                         Table 7S y.U/Q Values 1                                                         Rev. 3
     /

Stack

                                                               ,g Stability Class

- ,M,1,t e s A B C D E F G 0.5 ~4.97E-06 'i . 09 E 3 14E-07 00 0.0 0.0 0.0 0.6 2.95E-06 6.24E-06 1.0HE-04 4.30E-11 0.0 0.0 0.0 +

0. 7. 1.81E-06 6. 29 E--06' 2.13E-04 7.21E-10 0.0' -0.0 0 . 0..

0.8 1.26E-06 5.79E-06 3.13 E0 - 6 4.96E-09 0.0 0.0 00 0.9 1.11E-06 5.05E-06~ 3.93E-06' 2.00E-08 0.0 _ 0.0 0.0 l 1.0 1.~ 01 E-06 4.30E-06 4.50E-06 5.78E-08 7.83E-11: 0.0 0.0

                     .1.5        .7.11E-07      't.86E-06             4.97E-06 9.62E-07                              3.70E-08                 0.0.        2 0 '. 0 -

2.0 5.56E-07 8.94E-07 3.95E -04 2.31E-06 3.17E-07 S.69E-11 0.0 i 2.5 4.60E-07 5 99E-07 3.04E-06 2.90E-06 4.40E-07 7.35E-10 0.0-3.0 3.94E.07 5.08E-07 2.39E-06 3.14E-06 9.74E-07 3. 89E- 09 0.0 3.5 3.46E-07 4.46E-07 1.95E-06 3.38E-06 1.52E-06 1.96E-OA 0.0 1.90E-06 M.06E-08 0.0

                                                                       ~

^ 4.0 3.08E-07 3.98E-07 1.62E 3.34E-06 4.5 2 78E-07 3.41E-07 1.37E-06 3.1HE-06 2.l4E-06 9.29E-00 0.0-5.0 2.54E-07 3.30E-07 1.17E-04' 3.01E-04 2.32E-04 1.51E -07 : 1 ~. 9 7 E - 1 I 6.0 2.18E-07 2.81E-07 8.90E-07.- 2.71E-06 ? 59E-06 3.71E 2.54E-to- . 7.0 1.92E-07 2.46E-07' 7.09E-07 2.66E 3.59E-06 1.37E-06 2.21E-OH ! 8.0' 1.72E-07 2.19E-07 5.80E-07 2.53E 4.41E-06' 3 87E-06. 3.70Ea07- ,

          'N            ?.0       1.56E-07 1.97E-07 4.83E-07 2.23E-06 4.16E-06 4.52E-06 1'1'>E-06                                                             .

1.43E-07. 1.80E-07 4.10E-07 1.98E-06 3.91E-06 5.04E ~t.91E-06, t i 10.0 d 1.22E-07 1.55E- 07 3.10E-07 1.60E-04 3.46E-06 . 5.81 E -06. 4'.16E-0 6 - 12.0 14.0 1.08E 1.36E-07 2.44E-07 1.33E-06 '3.09E 6.23E-06 7.03E-06 16.0 9.63E-08 1.22E-07 2.01E-07 1.12E 2;78E-06 6.39E-06 1.00E 18.0 8.73E-08 1.11E-07 1.69E-07 9.70E-07 2.51E-06 -6.33E-06 1.25E-05 8.00E-08 1.02E-07 1.45E-07 :8.47E-07 2.28E-06 '6.13E-06 1.41E-0G 20.0 25.0- 6.66E-08 8.49E-08 1.14E-07 6.29E-07 .1.81E-06' 5.20E-06 1.39F 30.0 5.74E-08 7.31E-08 .9.80E-08 4.89E-07 1.47E-06 4.28E-06 1.16E-05 35.0 5.07E-08 6.44E-08 8.60E-08 3.96E-07L 1.24E-06 3.63E-06 9.88E-04 4 40.0 4.55E-08 5 80E-08 7.69E-08 3.32E-07 1.07E-06 3.18E-06 ;8.70E-06 45.0 l4.15E-08 54.89E-08 30E-08 6.97E-00 .2 85E-07 9.30E 9.85E-0A 7'.83E-06 30.0 3.82E-08 6.39E-08 2.49E-07 8 34E-07 2.5HE-06 7.13E-06 1 X*U/g (m'8) s 3 X UCi/m 11 m/s y DCi/s

  • Revised Complete Page
     .f)

(V. 4

                . ~ . -.             -       -      . ._          - _    _,          . _ - _ , . . . _ . - , - _                  . _ _ . , -         __             ,
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9

;                                                                                                     IN?tTT DATA SHEET A                              -

1 tieteoroloaical Information j Date: Release geometry: Person transmitting data: Level of transport wind direction": Person receiving data: Level of wind speed for dispersion *: Nuclear Plant: Stability layer for dispersion *: to ) Observed Data (15-minute averates) Forecast Data Central Time Plume Dispersion . for which Plume Dispersion Central Direction Wind Speed Stability' Forecast Direction Wind Speed- Stability Time (22.5* Sector) (m/s) Class is made ' (22.5 Sector) (m/s) Class Precip." t i 4 I 5 w

,             00

! 8 Observed Datab (1.-hour averate) Plume. Dispersion Outloolt for hours 9 through 24 in the futurer Central Direction Wind Speed Stability- Plume Time (22.5 Sector) (m/s) Class Precip." Direction Dispersion Stability - Valid (45' Sector) Wind Speed Class" Precir.* t .

                  ,    Comments     _

I ! W t tD ' 4 ' N 90 l' H 4 a. Indicate as upper. middle, or lower. d. -VL - Very Light (0-1.5 m/s), L - Light (1.6-3.5 m/s). O b. Conditions for period ending at indicated time. M - Moderate-(3.6-5.3 m/s), S_- Strong (5.6-8.0 m/s). H - High . [g c. Light rain (LR), moderate rain (MR), and heavy rain (HR); (8.1-11.0 m/s), VM - Very High (>11.0 m/s).

               *O           hourly value for 0.01 in e LR e 0.10 in; for MR,                                              e.      U - Unstable (A, B C). N - Meutral (D), S - Stable (E. F. C) 7 n

0.11 in e Ist e 0.30 in; and for HR>0.30 in. (D O W H > H X 'D ft D n . 'O u3 l

                 *ti                                                                                                                                                                                     4 'O n I rul Go j                 m                                                                                                                                                                                           C 12 HO8 ao                                                                                                                                                                                            nao H

O, S a nD OO l 9n en - l. l-tn W t> J* @ -. I s (D n

                                   /- /           I               Woax Suttr A atto:

01r'

            'i= =                      :-                    Release                 Data-           ~Pege e3;i69~

MSEC -IPD * (central time) IP-10 Attachment 1 . Work Sheet A Rev. 3' i A. Release Point B. Radioactivity Released i

1. Continuous Release Time (central time)

Release Rates Noble ges pCi/s ,

                                                                  ' I-131                             pCi/s i
                                                                                                  ,   pCi/s                    t
2. Puff Release 1

Time started (central time)  : i Time stopped (central time) Total Release Noble gas pCi j I-131 pCi  ;. UCi , t C. Supplemental Information (release geometry, system (s) affected, antici-pated end or changes in releases, flow rates, effluent concentrations, comments, etc.). l I I l l D'

e! .. Pags 29.of 31 i MSEC -IPD IP-10. Attachment 2 4 O Table 7 Rev. 3

                                                                                 . Table 7 i                                                                                         .                        .

Nominal Limits of Detectior and Concentration Limite

                                                                     . Detection Limit
  • NPC Value Nuclide (pCi/1)- (pCi/1) chrominum-51 90 2,000,000 manganese-54 10 100,000 i

l cobalt-58 10 100,000 cobalt-60 10 50,000

.                        zinc-65                                                    20                                                      10,000 zirconium-95                                              20                                                   600,000 niobium-95                                                10                                                   100,000
           }              ruthenium-106                                             80                                                   100,000 iodine-131                                                20                                                         300 cesium-134                                                50                                                       9,000 cesium-137                                                10                                                      20,000 l                        barium-140                                                50                                                      30,000
                        -1snthanum-140                                              10                                                      20,000 i

i

a. Emergency laboratory' analysis procedures (3.52 sample).
b. 10CFR20 limits for average annual concentrations of radioactivity in

, undiluted releases of water to unrestricted areas (for reference purpoges only). Approximate dose ccomitment rate is 1.4 mres/d. Multiply

by 10 8 to obtain equivalent pCi/m2.
                                                                                 -117-

I Paga 30 of 31 MSEC -IPD IP-10 )

                                                                                                                                                  -Attachment 2       j Worksheet A        l

! Rev. 3

            ~                                                                                                                                                         l
                                                                                                                                                                  -l Worksheet A Date:                  /                           /'
                                 -Time:

(central time) RELEASE DATA 4 WATER A. Short-Term Release (duration <24 hours) Time started: (central time) t Time stopped: (central time) Volume released: ft8 (if terminated) ft 8/s (if continuing, see note) i Note: If of undetermined duration, assume 1 hour. The g resulting dose will be rem per hour of release.

  • 1 d B. Long-Term Release (duration >24 hours)

Time started: (central time) Time stopped: (cential time) 8 Release rate: ft /s C. Release path to the river: D. Source Term Release Concentration Nuclide (pCi/ml) e d

                                                                                                          -118-
i
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                                    \
                               $                                                       TENNESSEE VALLEY AUTHORITY IMPLEMENTING PROCEDURES DOCUMENT - SEQUOYAH NUCLEAR PLANT Inserted by:                                                                                                          Issue Date:         July 21, 1982 Date Inserted:

Revision Log Sheet This log sheet must be retained as the last page of the Sequoyah Nuclear Plant Implementing Procedures Document. 4-

                      '    Pages to be Removed                                                                              New Pages to be Inserted

, Revision / . Revision / i Part Page Number Date Part Page Number Date IP-7 Cover Page Rev. O IP-7 Cover Page Rev. I s 1 of 1 Rev. 0 1 of 1 Rev. 1 , IP-10 Cover Page Rev. 4 IP-10 Cover Page Rev. 5 l 1 of 10 Rev. 0 1 of 10 Rev. 5 2 of 10 Rev. 0 2 of 10 Rev. 5' 3 of 10 Rev. 0 3 of 10 Rev. 5 4 of 10 Rev. 0 4 of 10 Rev. 5 5 of 10 Rev. 0 5 of 10 Rev. 5 ~ 6 of 10 Rev. 0 6 of 10 Rev. 5 7 of 10 Rev. 0 7 of 10 Rev. 5 8 of 10 Rev. 0 8 of 10 Rev. 5 9 of 10 Rev. 0 9 of 10 Rev. 5 10 of 10 Rev. 0 10 of 10 Rev. 5 Attachment 1 Attachment 1 1 of 2 Rev. 4 1 of 1. Rev. 5

                                                                                                       ~

2 of 2 Rev. 3 - Attachment 2 Attachment 2 1 of 1 Rev. 0 1 of 1 Rev. 5 Attachment 3 Attachment 3 1 of 1 Rev. 0 1 of 1 Rev. 5 l 0 . l l l l

       , ,          r   --    - - .   ~ , > - ,              . - - - - - , - - - . - -        . - , . . - , . . --.-- ~ .              --- - -          ,    . - - - - , ,

Revision _ Log Sheet (Cont inucil) This log sheet must be retained as the last page of.the Sequoyah Nuclear Plant Implementing Procedures Document.

 ,                        Pages to be Removed                                              New Pages to be Inserted Revision /                                                                                          Revision /

Part Page Number Date Part Page Number Date IP-10 Attachment 4 Attachment 4 1 of 1 Rev. 0 1 of 1 Rev. 5 Attahement 5 Attachment 5 1 of 1 Rev. 0 1 of 1 Rev. 5 Attachment 6 Attachment 6 1 of 1 Rev. 0 1 of 1, Rev. 5 IP-14. Cover Page Rev. 6 Cover Page Rev. 7 3 of 5 Rev. 0 3 of 5 - Rev.- 7 4 of 5 Rev. 5 4 of 5 Rev. 5 i l 1 I l l l \ i.-..___..-...-_.,_.. . _ - . _ . . - _ _ -

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                                    -Sequoyah Nuclear Plant                                                                  DISTRIBITTION
  'l O                                                                                              IC              81 Plant Master File jI                                                                                                   1C-             83 Asst. Power Plant Sept. (Oper.;

l SQN REP - IMPLEMENTING 1C 84 Asst. Power Plant Supt. (Maint.) PROCEDURES DOCUMENT 1C 86 Maintenance Supervisor (M) i 1.;n

                             -                                                                           IC             87 Maintenance Supervisor (E) 1C             88 Maintenance Supervisor (I) l 

3 1C 89 Results Supervisor SQN, IP-7 1C 90 Operations Supervisor j IC 92 Health Physics Supervisor I 1C. 93 Public Safety Services Supv.

    !                                                                                                    IC             95 Outage Director 1C             96 Emergency Cabinet Control Room ACTIVATION OF THE OPERATIONS                                          1C             97 Emergency Cabinet Communicaticas Room =

SUPPORT CENTER 1C 98 Emergency Van . g 100 Emergency Cabinet Meteorological Bld. 1C ! .lC ~102 Shift Engineer's Office'- j Prepared By: J.R. Walker 1C 103 Unit Control Room 4 i- 1C 105 Health Physics Laborat'ory Revised By: L.M. Nobles 1C 106 Medical Office IC 107 Resident NRC Inspector-- SNP mA7 Submitted By: 72 1C 108 Tuhaical Support Center ~ VIupervisor- IC 109 Assistant HP Supervisor l' IC 110 Plant Duty Supervisor 1 lc 111' Asst. Power Plant Supt. (H&S) PORC Review: N IV IC OC H&S - John Ingwersen - MS Date, Approved By: k. " Pwr Plt Superintendent Date Approved: [V

                                                                                     'l 8

Rev. No. Date Revised Pages Rev. No. Date Revised Pares 0 8/5/80 ALL 1 gMjJ o Revised 1 l~ The last page of this instruction is Number 1 . l l l ., _ ___. _ _ . _ . _ -,_ _- _ . _ _ __ _ _. . . . _ _ . . .

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, 's .,; SQNP REP-IPD SQN, IP-7 Page 1 of 1 Rev. 1 ACTIVATION OF THE OPERATIONS SUPPORT CENTER 1.0 PURPOSE ' The purpose of this procedure is to outline the requirements related to .4cti-vating the Operations Support Center (OSC). The OSC is activated during an Alert, Site Emergency or General Emergency. 2.0 INSTRUCTION 2.1 Alert j The public address system is utilized as directed by the shift engineer i to request all operations personnel not assinged to the control room to secure the operation in which they are engaged and proceed to the OSC for further instructions. 2.2 Site Emersency and General Emergency ,. s Upon hearing the emergency sirens, all operations personnelInot assigned ' I to the control room secure the operation in which they are engaged and s_,/ proceed to the OSC for further instructions.

2.3 The Site Emergency Director may request additional plant personnel to report to the OSC.

ah 3.0 RESPONSIBILITIES f 3.1 The common ASE is responsible for keeping personnel in the OSC briefed

         &                   on plant status.                                                        .                ,

p 3.2 The shift engineer will keep the common ASE briefed on plant status. j 4+ 3.3 The shift engineer will assign a team leader each time' personnel. from , (? the OSC are dispatched into the plant. .The entire team will be je briefed' on the assigned task prior to leaving the control building.

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DISTRIBUTION Sequoyah Nuclear Plant 1C 81 Plant Master. File IC 83 Asst. Power Plant Sept. (Oper.') IC 84 Asst. Power Plant Supt. (Maint.) SQN REP - IMPLEMENTING . PROCEDURES DOCUMENT 1C 86 Maintenance Supervisor (M) IC 87 Maintenance Supervisor (E) IC 88 Maintenance Supervisor (I) SQN, IP-10 IC 89 Results Supervisor . 1C 90 Operations Supervisor 1C 92 Health Physics Supervisor MEDICAL EMERGENCY PROCEDURE IC 93 Public Safety Services Supv. 1C 95 Outage Director 1C 96 Emergency Cabinei. Control Room IC 97 Emergency Cabinet Ccanunications 3.som IC 98 Emergency Van 1C 100 Emergency Cabinet Meteorological Eld. 1C 102 Shif t Engineer's Office IC 103 Unit Control Room - Prepared By: M. B. Knight 1C 105 Health Physics Laboratory Revised By: J. R. Everett 1C 106 Medical Office IC 107 Resident NRC Inspector - SNP Submitted By: I . O.7j ;//jffj) 1C 108 Technical Support Center (Sp'pe'rvisor 1C 109 Assistant HP Supervisor 1C 110 Plant Duty Supervisor " IC 111 Asst. Power Plant Sept. (y&S) (~'x PORC Review: [b//7W

                                       / Date' 1C    OC H&S - John Ingwersen - MS j (V   )                                                                                                 .

i

              ~ Approved By:                      og
  • wr Plt'Sup'erintendent' l

Date Approved: ((>v/P

                                               /

W Rev. No. Date Revised Pages Rev. No. Date Revised Pages_ 0 8/5I80 ALL h 3I22I82 11 1 h/22/81 11 5 5fJlfd.'L All 2 7/15/_81 11,12 3 10I19/81 12 I The~1ast page of this instruction is Number 16 U . l I l

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IZI-IPD v '/ IP-10 ', 3 I:2ge 1 of 10 hev. 5 .

                                                   "EDICAL EMERGENCY PROCEDURE                  . - - -

1.0 PURPOSE , a,.ra que

                                                                     .\

This procedure outlines the action to de followed durifi[ N dical emergencies ' at Sequoyah Nuclear Plant.

                                                                                        , , m, y 3 2.0 PROCEDURE-              ' -                                              : 4 W ; .,w -
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2.1 Initial Reporting and Response to Accident and' Emergency Medical Situations s.

                                                                                            . y,; ..m                                                             3 2.1.1       Anyone discovering a sericus injuryj orj othN medical emergency should administer aid for any life-threagning situation.

i 2.1.2 Sununon any available personnel in the area for asdistance. 0 , 'a i

           !      2.1.3       Notify.the control room on PAX phone                              #

ind sta'te, "This is A medical emergency and not fire," so that th'eNcontrol room , operator can initiate appropriate responce. 2.1.4 Give the control room operator yoar name, the location of the emergency (including building, elevation, and column coordinates), the type of medical emergency and the number of people involved. Also, give the PAX telephone' number from which you are calling and if the emergency is in a regulated area. 2.1.5 Initate such actions as may be needed to avoid further injury to the victim or injurysto other personnel. 2.1.6 As emergency response personnel arrive, assist them as requested and give any pertinent information they require relating'to the injury or illness. i 2.1.7 Notify your supervisor and assist as requested in report u preparation and followup. , 2.2 Activation of Medical Emergency Response Team ' j 2.2.1 The control room operator or the assistant shift engineer shall:

a. In , tate activation of the emergency response team, and a r. unee over the public address system, the location of ardical emergency;
b. Notify the shift engineer of the emergency. '

3 S e

1

.  ; .?
   't SQNP
                                                            . REP-IPD IP-10' Page 2'of 10 4                                                             Rev. 5 4

2.2.2 A roster listing all names and telephone numbers of the indi-viduals and local agenies required to either respond to provide support for the medical emergency will be provided to the Plant Duty Supervisor and the Shift Engineer. 2.2.3 The shift engineer will notify the nurse on duty who, if necessary, will proceed to the emergency site. 2.2.4 The shift engineer will request the necessary information from health physics personnel. Medical and Public Safety may be required to assist the shift engineer in completion of Attachment 1. 2.2.5 When a patient is transported to a hospital, the shift. engineer will notify the receiving facility of the patient's condition, the estimated time. of arrival, and the radiological status of the patient as determined by health physics. 2.2.6 If necessary, the shift engineer will request that Public Safety arrange for an ambulance (offsite or onsite) .for trans- i r cting of injured personnel. 2.3. Organization and Duties of the Medical Emergency Response Team 2.3.1 The medical emergency response team consists of a health physics representative, an assistant shift engineer, public safety officer, (or individual trained in first aid or emergency medical response), and nurse. The. team will be supported by assistant unit operators who have received supplemental first aid training.

  -(,                      2.3.2      Duties and responsibilities of the various members of the response team:

.2-2.3.2.1 Team Leader (assistant shift engineer) 1

a. The team leader will take charge and direct the

(" total activities while consulting with members. of the team in their area of expertise; iL*

b. Lead the team in and out of the area by the most direct and/or appropriate route (with proper considerations of hazards to members of the team with the operational functioning of the facility).

If the patient is located in a' contaminated zone, a minimum number of response personnel.will enter 4 the area initially. Protective clothing will be a minimum (shoe covers, gloves at the discreation of health physics). Additional personnel may ' .be requested by team leader- .

                                                                    .g

SQNP REP-IPD m- ) IP-10 Page 3 of 10 Rev. 5

c. Assist and consult with the nurse, individuals trained in emergency medical response, and the health physics representative when needed and aid in extrication and/or transportion of patient to the health station, medical office, or ambulance as appropriate.
d. Maintain communication with the shift engineer and keep him advised of situations, needs, and
  '                             progress of team; request that the shift engineer contact the appropriate hospital or a receiving facility when patient transportation is necessary.
e. Upon advice from Medical or other appropriate personnel, notify control room that an. ambulance
                 >              is needed, i

2.3.2.2 Public Safety Officer (or individual trained in emergency medical response).

a. Proceed to the emergency with a medical' kit.

b. fh d Administer medical treatment.

c. Perform crowd control upon instruction of team leader.
d. Provide information to the shift engineer to complete Attachment 6.
e. Provide escort-for nurse if requsted to report to emergency scene.

2.3.2.4 Health Physics Representative will:

a. Proceed to the emergency
b. Monitor environment and patient as needed,
c. Advise team members concerning proper protective -

clothing, equipment and occupancy time needed for their protection.

d. Advise team concerning protective measures and decontamination needed for patient.

m_ -

SQNP REP-IPD IP-10

         /                                                                          Page 4 of 10 Rev. 5
e. Be available to answer questions concerning radiation exposure and/or contamination of the patient asked by the nurse, shift engineer, and receiving facility (see' Attachment 1).
                                                                        .f. Advise the shift' engineer and medical of all radiological conditions and any possible exposure of personnel as appropriate.
g. Assist in patient care when'not otherwise occupied with radiation concerns and responsibilities.

2.3.2.5 Nurse will:

a. Proceed to the emergency if determination made that he/she is needed at scene.
b. Administer emergency care as required.
c. Will make a followup phone call to hospital outlining additional information concerning patient's condition.
d. Provide information to shift engineer for

( completion of Attachment 1. 2.4 General Patient Care Guidelines i 2.4.1 First aid and emergency medical care should be provided_for onsite personnel at the facility to preserve life and to minimize injury _ and suffering. 2.4.2 The medical emergency response team will check the patient's condition and take appropriate medical action as directed by the nurse, or other team member trained in emergency medical care. 2.4.3 The medical emergency response team shall assist the nurse or other team member trained in emergency care and at'his/her direction, evaluate, stabilize, and transport any seriously ill or acutely injured person to the nearest health station, r TVA medical office, or hospital receiving facility as appropriate.

                          .._,_,..--,,,,,~w_.__,._.                 ,g,               , _ , . , _ , _ , , , . , ,     , _ , _ , . . . _ . _ _ .,       _, _ _ , , ,. ,

e SQNP x- REP-IPD IP-10 Page 5 of 10 E

  • Rev. 5 1

A doctor should be requested, when in the nurse's judgment 2.4.4 (or other personnel-trained in emergency medical care) further professional attention.is needed prior to transport such 'as-in a problem with extrication where the patient needs medical . attention while extrication is being accomplished. .Always keep in mind the goal of maximum benefit to the patient. ( 2.4.5 Transport patient to the emergency treatment area or health station (or nearby TVA medical office) unless patient's l condition is such that he needs immediate transport to a-I hospital. 2.4.6 If a patient requires ambulance transportation to'a medical

office or hospital, utilize the TVA ambulance before contacting

' a commercial ambulance service. When necessary, the shift f i engineer will request an ambulance (onsite'or offsite) from l {

                                 - Public Safety for transporting injured personnel.

2.4.7 The health physic representative (s) will act as advisor to the . emergency response team and medical personnel concerning radiological conditions. 2.5 Patient Care Guidelines for Special~ Conditions ! 2.5.1 General Guidelines l The care and disposition of all ill and injured persons known - ! or suspected to be associated with radiation exposure or-contamination will be coordinated with the health physics representative. The essential aims of the medical-health physics team are:

1. Minimize injury and further radiation exposure to the victim.
2. Protect attending personnel from excessive and unnecessary radiation exposure.
l. Control spread of radioactivity contamination, I 3.
4. Accessfand document the patient's radiological exposure.

j- Immediate lifesaving and disability limiting procedures 5. will take precedence over noncritical decontamination and dosimetry assessment procedures. 2.5.2 Classification and handling of radiologically exposed or  ; contaminated individuals. i

      . ..         l     .~

SQNP REP-IPD O IP-10 Page 6 of 10 Rev. 5 2.5.2.1 Irradiated-Noncontaminated First remove the victim from further exposure providing only' essential first aid in the process, then direct attention to medical care.of other physical injuries. The patient is then transported wherever necessary for adequate initial care of his illness or injuries. The health physics technician determines and reports-the type and level of exposure and the affected area of the body if possible. Medical care of the radia- .. tion exposure is governed by the medical status.of the patient and the findings 'of the health physicist. In most cases, the. treatment of illness or physical injury takes precedence over treatment for radiation , exposure.

                                                                                                                                                                           ?

In general, the medical treatment for radiation exposure should be related to the total. dose received. Therefore, several major decisions . points should be looked for: 2.5.2.1.1 Individuals who have received an acute total body dose.of less than 5 rem usually require 5 s, no medical examination or treatment for- ' the radiation exposure. 2.5.2.1.2 Individuals who have received an acuate total body dose of between 5 and 75 rem radiation I can usually be treated as an outpatient, but should have hematological-studies performed to detect chromosomal aberrations and other changes in other blood constituents. Attachments 2 and 5 give laboratory directions for drawing-blood samples for chromosomal and hematological studies. s i-., - - - - _ , - . . . . . . - . . . . . - . _ . . _ . . . _ . _. . _ . . _ - _ - . - _ . . - . . . - . _ _ _ . - . - - .-! ,- . , - - . - -_-. ---

                     ~

SQNP REP-IPD-

    / ~~g'                                IP-10 Page'7 of.10 Rev.-5 2.5.2.1.3 For individuals who have received an acute-total body dose greater than 75 rem, Levalua-
                                         -tion by a nuclear medicine specialist shall be arranged regardless of physical injuries-or illnesses. This is the-minimal dose'that-produces a recognizable reaction-in about 10 to 20 percent of the individuals exposed.

i Blood studies should be drawn per' directions (attachments 2 and 4). If the patient is ill or injured requiring attention for physical-11nesses or injuries, he should be trans-ported to Erlanger. Medical Center (see i Attachment 4) with the information that this patient has received an acute total body . + dose greater than 75 ' rem. It is recommended that the attending physician consult REAC/TS. l  ;

                       '                  If the patient is not seriously ill or injured -

enough to require hospitalization for physical illness or-injury, and with: the recommendation . p of REAC/TS, referral may be made to 0ak Ridge Hospital (see attachment 5) or the l Unit Methodist Church.where the patient could 7s be observed and treated by the physicians f ( l on the REAC/TS team. l. 2.5.2.1.4 If a worker's projected cumulative dose .to the thyroid from inhalation of radioactive iodine might exceed 10 rems, the Medical Director has authorized responsible health

                                         -physicists or other. qualified individuals to offer the exposed person an immediate first dose of a course of potassium iodine.      -

The time the first dose was administered should be documented'and the individual should be referred to the health station or-a TVA medical office. Anyone authorized to initiate KI shall be familiar with the Food. l and Drug Administration approved package l- insert, and bd sure that each proposed l recipient is similarly informed. The initial dose of KI should not be delayed and those who begin therapy should continue the 10-day course of KI unless their thyroid dose is determined not to have exceeded 10 rem. An adequate supply of KI is stored at each nuclear facility to supply any personnel exposed to radioactive iodine. It is supplied in bottles which contain a full 10-day dose regimen. Follow dosage schedules as outlined on the package insert accompanying each bottle of KI. l l-

r

                                                                               .SQNP-REP-IPD
           )                                                                     IP-10 Page 8 of 10 Rev.'5
                                                                   -2.5.2.1.5 Any personnel known or suspected ofireceiving' radiation exposure in excess of the TVA' occupationalEdose limits should be reported.

to TVA medical-and.the area medical chief-as soon as possible. -Health physics should document the amount and. type of radiation and assist MED SV in followup by supplying them with this information.

2.5.2.2 . Contaminated Patients t

2.5.2.2.1 The patient should be identified,.given initial first. aid and transported by.the medical-emergency. response team. All decontamination that the medical status of-the patient will - allow should be accomplished. The appropriate ' sequence of care must be determined on an individual basis by the medical-health physics; team. The injured person may be decontaminathd on the spot by. removal of contaminated clothing' if possible, or.may be removed to the. personnel decontamination facility in the. service building where contaminated clothing and skin transferrable contamination may; be removed. At that point, the. injured l person will.be transported and-treated in one of two ways. 2.5.2.2.1.1 If the person is severely

injured, they say be-trans-I ported directly to-Erlanger-Medical Center provided that every reasonable effort has been made to reduce the radio-active contamination level to less than .5 R per hour at
one foot. If clothing and j- contamination cannot be safely removed, spread of contamination may be minimized by removing the patient's excess clothing and wrapping him in a sheet, as '

his injuries permit. 9 I-i I

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g 7 SQNP

                                                                                      . REP-IPD IP-10 (s.~/                                                                            lPage 9 of 10:

Rev. 5 2.5.2.2.1.2 :In cases of less severe injuries, the patient will be 'sent_to-the personnel. decontamination room to remove as much-contam-ination as possible before he is treated in the emergency

                                                                                                              . treatment' area of transferred to Erlanger Medical Center.

2.5.3 . The health physicist will collect, identify, label and analyze all biological specimens as required and deemed necessary. He will obtain the injured person's personnel dosimetry and replace,- with equivalent dosimetry if appropriate. 2.5.4 The health physics group will also maintain supplies to control contamination and protect members of the medical emergencyL ,

                   !                               response team during transport within the. plant and to the receiving hospital.

Medical emergency. response team members and medical personnel will don and maintain whatever personal protective equpment the health physics representative should accompany the patient. g) to the hospital and should furnish as much information as possible about the patient's dose and type of radiological contamination and/or exposure to the receiving facility (see attachment 1). At the hospital, a health physics representative will furnish radiological services to attending i physicians and hospital personnel as requested. I 2.6 Guidelines for Followup Medical Care Followup medical care of illnesses or injuries treated in the health station or TVA medical office are usually done in the health station or TVA medical office. If the patient has been referred to a provide physician or receiving hospital, followup medical care is usually-done by the private physician unless the patient is released or. followup medical care is requested from Medical Services by ~ the private physician. In such instances, followup medical' care will be arranged through the health stations and TVA medical offices. N

   ..              .s
s. .

SQNP REP-IPD IP-10 s,,j/ Page 10 of 10 Rev. 5 2.7 Notification Guidelines 2.7.1 The area medical chief or his designee or.the area nursing supervisor or her designee should be notified by the plant nurse or someone designated by her/him in the following instances. 2.7.1.1 'If some is ill or injured to the extent-that they require ambulance transportation to a hospital receiving facility. 2.7.'1.2 If the number of injuries is above that normally expected to be handled during the normal operation of a health station. 2.7.1.3 Anytime there is a situation existing in the facility which creates a hazardous environment where there is an increases liklihood of radiological exposure and/or contamination or increased physical risk so that injuries are more likely to occur than'during normal operating conditions. 2.7.2 If the Area Medical Chief and the Area Chief Nurse or their designee cannot be contacted, then notify the Medical Director [ or Medical Services Representative to CECC if activated. ( 2.7.2.1 Health Physics should notify the Area Medical Chief anytime any TVA occupational exposure limits. 1 1

                                                              /
           . .i SQNP REP-IPD' s\                                             'IP     [\s,,/J                                             Attachment 1 Page 1 of 1 Rev. 5 RADIATION'AND/OR MEDICAL EMERGENCY NOTIFICATION REPORT To be used.by shift engineer to. enter available data for notification of a receiving hospital of 'the impending admission of a case involving a' medi(il emergency radiation exposure or contamination, Nature of Accident Extent and Discription of Injuries Treatment Provided i

Condition: Good Fair Serious Critical Deceased B/P Pulse Respiration Treated in Medical Office: Yes No Time: A. Persca Making Notification:

               Name                                               Date-            Time Title'                                             Telephone Plant B. Patients to be Admitted:                         Total Number:

Name (if available) Injury but no Radiation Internal External. Contamina-Radiation or Exposure Contamina- Contamina- ted Wounds Contamination tian tion C. Will patients be: Surveyed for Contamination? Decontaminated? D. Expected Time or Arrival at Erlanger Hospital: ? Notification Taken by:

SQNP REP-IPD IP-10 1,. Attachment 2 Page.1 of 1 Rev. 5

                                                                            ~

INSTRUCTIONS FOR LYMPHOCYTE CULTURING FOR CYT0 GENETIC DOSE ESTIMATION OF LOW LEVEL WHOLE BODY ACUTE OVER EXPOSUPI TO IONIZING RADIATION TVA has an agreement with the Oak' Ridge Associated Universities Cytogenetics Laboratory (ORAU) to perfo?m lympocyte culturing to provide cytogenetic estimate

                     'of' radiation dose.

Upon the ' order of a responsible physician and after arrangements have been coordinated with ORAU/REAC/TS, concerning the transport and arrival time of the specimen, the following procedure should be followed: The blood should-be collected in a red top vacutainer (Cat No. 2-657-3, Bd No. 4671) to which has been added 0.1 al of sodium heparin (Upjohn 1000 units). Mix-by inversion 30 times in 30 seconds immediately after collection. Blood samples must be kept cool-(not frozen) during shipping and [torage. The vacutainers should be packed in Styrofoam chips, packing straw, etc. Surround packing material with a coolant and ship in a well-insulated container. Do not put the~ tubes directly on any coolant that may freeze the samples. Identify the samples with the patient's name, birthdate, social security number, date and location.

   .\
       ~~

Samples should be shipped by the fastest available carrier, such as' TVA churier, air, or commercial carrier to: ORAU/REAC/TS Cyto Genetics . Laboratory Atta: Gayle Littlefield or Gene Joiner Medical and Health Sciences Divison Oak Didaa. Tennessee 37830 su - . .

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                                                            - - -            REP-IPD IP-10 Attach.:ent 3 PaEe 1 of 1                           -
                                                                            -Rev. 5 r, -                          , _     ._ .._ _                     .
                                                                                                      ~ ' "                                      " ~~

LYPHOC TE CULTURING -

                                                                                                                          ~

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                                                                                                            ;pj % }j3 -

C- Type ~ Container: J m,G LZ Collection Method: 40-~ 3,q%R g . , Blood . . , Red top vacutainer #4671 to which has been added 0.1 mlc e Serum - -

                                                       --M - v
                                                        .                     of sodium heparin (Upjohn:; m .. g ;.
                                                                                             ~

I - -.m- M.:W ' 1000" units). - _1 Z 1, , - - s -

                                                            '                                                                         ~~

Plasms. -

                                                       - ,                       . .'     ~'.,               . . -        ;.

Urine-Sputum Other - t ~ When: Uponorderof'responsibleTVA'M.D'.'iIcoordinationwithREAC/TS,after' confirmed exposure exceeding 5 rem of total body ionizing radiation. Frequency: Once, unless otherwise directed by responsible medical authority. Special Instructions: Refrigerate, but do not freeze in ' shipping containers

                                                                                           ~

provided for this. purpose.~ See~ attached memorandum. Where Sent: ORAU/REAC/TS Cytogenetics Laboratory Attention: Gayle Littlefield or Gene Joiner. Medical and Health Sciences Division Oak Ridge, Tennessee 37830 Special Notice: Notify Earl Jordan at extension , Chattanooga Report Results to: Robert L. Craig, M.D., Medical Director Medical Director 320 Edney Building Chattanooga, TN 37401 Phone: Label Information: Yes SS Number Name - SS Number Birthdate Race Sex Loc No. Time Code No LYMPH 0CYTE CULTURING N~. I l [( ,,JRI!!ARY ROUTE Atta 9 ' --e + on,, f se,oug PUWT

                                                                                        @                                                                                                                   ?      .

u%, , SECO1DARY ROUTE ,, , 8 ALTERflATE' ROUTE 4 g _

                                                                                                                                         "                                                  I Primary Route is as Follows:                                                                    , , , , .

Leave Sequoyah {uclear Plant via Sequoyah Road to - m ,,,, 0 Highway 27-(6.3 miles) Highway 27 to Highway 153 4 (6.6 miles) Highway 153 to C. B. Robinson Conniecto Road (4.2 miles) C. B. Robinson Connector Road to *'"*" (2.5 miles-) Amnicola Highway to

  • Amnicola Riverside Drive Highway (2.6 mi.les) (See locality ftap ,
                      #2 for the following) Riverside Drive to 3rd                                                                                                 ,

Street Exit (1.5 miles) 3rd Street Exit to 4th ,,ky!c, 3a Street via Mabel Street (0.1 mile) 4th Strgt O , t E to Erlanger Hospital via Lansing Street "

                                                                                                                                                                                               **854 50 3rd Street (0.6 mile).
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Sequoyah Nuclear Plant DISTRIBUTION D IC 81 Plant Master File ~ g IC 83 Asst. Power Plant Supt. (Oper. ) IC 84 Asst. Power Plant Supt. (Maint.). SQN REP - IMPLEMENTING PROCEDURES DOCUMENT 1C 86 Maintenance Supervisor (M) 1C 87 Maintenance Supervisor (E) SQN, IP-14 1C 88 Maintenance Supervisor (I) t 1C 89 Results Supervisor HEALTH PHYSICS PROCEDURE -1C - 90 Operations Supervisor 1C 92 Health Physics Supervisor 1C 93 Public Safety Services Supv. 1C 95 Outage Director 1C 96 Emergency Cabinet Control Room 1C 97 Emergency Cabinet Communications ?com 1C 98 Emergency Van _ _1C 100 Emergency Cabinet Meteorological 31d. 1C 102 Shift Engineer's Office Prepa ed By: R.J. Prince 1C 105 Health Physics Laboratory Revised By: Stephen P. Holdefer 1C 106 Medical Office 1C 107 Resident NRC Inspector SNP Submitted By: h.  ; 1C 108 Technical Support Center ( ()Su'pervisor' 1C 109 Assistant HP Supervisor 1C 110 Plant Duty Supervisor (Q PORC Review: }7 1C 1C 111 Asst. Power Plant Supt. (H&S) OC H&S - John Ingwersen - MS IDat4 Approved By:

  • Pwr Plt Superintendent Date Approved:

N IV

                                                 /

Rev. No. Date Revised Pages Rev. No. Date Revised Pages 1 j 0 8/5/80 All 4 12/15/81 Revise SA, Add 53.5C l 1 -2/11/81 1 5 2/5/82 2,4,5,5A,5B,5C l 2 8/3/81 6 6 3/22/82 6 3 12/1/81 Revise 5, Add 5A 7 .27' Revised 3 l ( n , The last page of this instruction is Number 10 . G

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4,,,., .. . . SQNP ' I Page 3 of 5 REP-IPD SQN, IP-14 < Rev. 7 5.5 As reports become evailable' regarding the details of the emergency, Health : Physics personnel shall prepare all necessary equipment needed during - recovery and ready a survey team (s) for entry into the affected area (s). , i 5.6 Upon notification from the HP representative in the control. center,:the survey team may proceed to the specified area. It should be noted that-depending on the type of accident, this initial survey cay not be performed until hours or perhaps even days after the event. In this case, procedures-may be developed describing the re-entry steps to be followed. Other essential personnel may be required to assist. in re-catry _ surveys. 5.7 A site boundary survey may be-required. This survey should not be done '

                                                                                                                                                        ~

, without prior consultation with the Site Emergency Director. 5.8 The emergency van will be utilized during site boundary surveys. The. van ,. is equipped with numerous supplies; however, the equipment listed in attachment I should be transported to the van.

                            -5.9      When instructed to do so, travel to the site boundary in the down wind direction and measure the dose rate with an ionization chamber or similar survey instrument.                                    If possible, air sampling should also be performed i

4 at the same time. If weather conditions exist which may result in the j air sampling apparatus being exposed to moisture, the samples shall be t taken in an area which minimizes this exposure. 5.10 Precautions must be taken to prevent overexposure if there are high  ; concentrations of radioactive particulates or radioiodine being released (see section 7.0). 5.11 Record all survey results. All findings shall be reported to the emer- ~ gency control center. If results indicate offsite contamination, the survey areas may need to be extended. Obtain further instructions and perform required surveillance.

5.12 Arrangements have been made for manpower support and equipment for' offsite surveys from the WBNP should it be needed until the environs survey teams arrive from MSECC.

i 6.0 GENERAL EMERGENCY I 4 g 4 1

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                                                        .,       SQNP.    .

Page 4 of 5.. .

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( SQN, IP-14 Rev. 5 - 4 6.1 During a general-emergency, there may_be radiation releases to the environment requiring Health' Physics response. These releases may require evacuation procedures to be implented. 6.2 An extensive Health Physics response will probably be required during a general emergency. 6.3 The actions descirbed under site emergency (paragraphs .5.3 to'5.ll) will be applicable to a general ~ emergency condition'as well. 6.4 During a_ general emergency (and perhaps'during a site emergency), condi-tions in the Health Physics laboratory may be such that evacuation is warranted. If this situation develops, a Health Physics laboratory would i need to be established within the technical support center. This lab would be equipeed with wil necessary supplies and instrumentation needed te perform minimum radiological surveys and analyses required during an

                            ! emergency.

I 6.'5 If it is necessary to evacuate the HP lab, then the HP technicians stationed in the lab will secure the equipment listed in attachment 2. This equipment will be brought to the technical support center by Health Physics. This list is a minimum and if time permits and. manpower allows

             -t               then efforts should be made to trasnport additional equipment and supplies to the technical support center.. The. Site Emergenet Director -hall be-k_/

s informed when it becomes necessary to evacuate the HP' lab. t 6

                        '.6   All su'bsequent offsite activities must be coordinated with all offsite support agency survey teams. Make the best use of available' manpower.

Report all survey results as soon as possible to the emergency center so they can make recommendations to the proper agencies to initiate any required protective actions. 7.0 ISSUANCE OF POTASSIUM IODIDE (KI) 7.1 If a responsible health physicist or other knowledgeable individual has reason to believe that a person's projected cumulative dose to the thyroid from inhalation of radioactive iodine might exceed 10 rems, the exposed , person should be started immediately on a dose regimen of potassium iodide (KI). Anyone authorized to initiate KI shall be familiar with the Food and Drug Administration approved package insert and be sure that each proposed recipient is similarly informed. The initial dose of KI should not be delayed and those who begin therapy should continue the

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