|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program ML20084N3541995-03-24024 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20137B5371995-03-22022 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20081C1281995-03-0808 March 1995 Svc Water Sys Operational Performance Insp Self-Assessment Plan ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20059M2301993-11-12012 November 1993 Rev 7 to 6610-PLN-4200.01, Odcm ML20057B3781993-09-0202 September 1993 Rev 6 of Solid Waste Staging Facility Sys Description ML20045B5771993-06-0808 June 1993 Procedure Change Request 1-RC-93-0016 to Rev 4 to Procedure 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20036B4881993-05-17017 May 1993 Rev 9 to EPIP-TMI-.04, Contact/Call Out of Emergency Personnel ML20127A2181992-10-15015 October 1992 Rev 1 to 6615-PLN-4520.01, REMP - Plan ML20127A2301992-08-11011 August 1992 Rev 30 to Emergency Procedure 1202-32, Flood ML20045B5531992-01-23023 January 1992 Rev 5 to Policy & Procedure Manual 1000-PLN-4010.01, Gpu Nuclear Corp Radiation Protection Plan ML20090D4031991-10-0404 October 1991 Rev 16 to Waste Solidification Process Control Program ML20082M2991991-08-29029 August 1991 Rev 8 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20127A1511991-07-0808 July 1991 Rev 4 to 1000-PLN-4010.01, Gpu Nuclear Corp Radiation Protection Plan ML20082M2951991-06-27027 June 1991 Rev 14 to Operating Procedure 1104-28I, Waste Sodification Process Control Program ML20198B9741991-06-17017 June 1991 Rev 2 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070L3331991-03-15015 March 1991 Rev 1 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070U9241991-03-0404 March 1991 Rev 0 to 6610-PLN-4200.01, Odcm ML20059H9031990-09-0707 September 1990 Rev 0 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20059C7931990-08-23023 August 1990 Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility ML20028G8711990-08-15015 August 1990 Auxiliary Bldg Emergency Liquid Cleanup Sys (Epicor II) ML19351A4371989-11-30030 November 1989 Rev 9 to 9110.PLN-4200.02, Emergency Dose Calculation Manual ML19327B6411989-10-25025 October 1989 Rev 0 to Safety Analysis 4700-3882-89-01, SER for Use of Polar Crane Auxiliary Hook Above In-Core Instrument Seal Table to Withdraw In-Core Instrument Strings ML20248D4071989-09-27027 September 1989 Rev 8 to 9100-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20245K1211989-08-0202 August 1989 Rev 4 to SD 3184-007, Div Sys Description for Solid Waste Staging Facility ML20244C2961989-06-30030 June 1989 Rev 1 to Sys Description SD 3510-013, Div Sys Description for Reactor Bldg Sump Recirculation Sys ML20246M7931989-03-0909 March 1989 Rev 11 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154C7191988-06-0303 June 1988 Rev 10 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154Q6771988-05-27027 May 1988 Recovery Operations Plan ML20236M1621987-11-0909 November 1987 Radiological Environ Monitoring Program for TMI-1 ML20236M4281987-10-19019 October 1987 Vols 1 & 2 of 1987 TMI Annual Exercise Scenario ML20147F9331987-08-25025 August 1987 Rev 3 to Procedure 1000-ADM-1291.01, Procedure for Nuclear Safety & Environ Impact Review & Approval of Documents ML20238C6391987-08-21021 August 1987 Rev 2 to Design Criteria 3255-86-0004, TMI-2 Design Criteria for Pressurizer Defueling Sys. W/One Oversize Figure ML20236K9601987-07-24024 July 1987 Rev 3 to 3184-007, Solid Waste Staging Facility Sys Description ML20215M3261987-06-19019 June 1987 Rev 16 to Organization Plan ML20215H0301987-06-15015 June 1987 Revised Emergency Plan Implementing Procedures,Including Rev 2 to 6415-IMP-1300.06. Addl Assistance & Notification & Rev 1 to 6415-IMP-1300.16, Contaminated Injuries. Updated Table of Contents Encl ML20215M1291987-03-20020 March 1987 Corrected NCRP Commentary 4, Guidelines for Release of Waste - Water from Nuclear Facilities W/Special Ref to Public Health Significance of Proposed Release of Treated Waste Waters at Tmi ML20214S4481986-12-31031 December 1986 TMI-2 Cleanup Program,Post-Defueling Monitoring Storage ML20212N6711986-12-17017 December 1986 Rev 2 to Test Procedure SC-1302-323 Isolator - Fault Testing. Test Results Encl 1999-08-12
[Table view] |
Text
-
1004.16 Revision 2 03/08/83 g
IMPORTANT TO SAFETY g-9 O
"oa-raviao -t"Ta' taract at'^Tro
}
THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IMPLEPENTING PROCEDURE 1004.16 l
CONTAMINATED INJURIES / RADIATION OVEREXPOSURE i
Table of. Effective Pages Page Revision Page Revi sion Page Revi sion Page Revi sion 1.0 2
2.0 2
3.0 2
i.
4.0 2
l 5.0 2
t 6.0 2
7.0 2
8.0 2
9.0 2
y 1
i !
1 v
i g
f)YW 3 $b0 Signature Date i
Signature Date O,
8303300784 830328 Mof Documert ID: 0031W PDR ADOCK 05000289 F
PDR OI NNN cy _
~-
F
1004.16 Revision 2 THREE MILE ISLAND NUCLEAR STATION 4
UNIT NO.1 ENERGENCY PLAN INLEENTING PROCEDURE 1004.16
^
CONTAMINATED INJURIES / RADIATION OVEREXPOSURE i
1.0 PURPOSE
)
To define the conditions where person (s) working at Three Mile Island and exposed to ionizing radiation greater than 25 REM (acute dose), or fil or injured and contaminated or potentially contaminated with ra oactive material will be removed from site to Milton S. Hershey M c
nter (HMC). Hershey, PA. To further define the steps invo]
tifying HMC to allow time for preparation of the Radiation y Area (REA) i to receive the injured n(s). To provide eve 1 levels of treatment based on th of the inju s) and the degree of D
exposure /contamin o
volved. The S ft rvisor/ Emergency Director is responsib1 or ementation of cedure.
i I
h NOTE $
k5ipersobs urkes or kk5ne inaradkb-logically con d area or inv radioactive :
material onsidered cont until proven e
e.
a 2.0 ATTACHMENTS 2.1 Attachment o ogical Control 1 st for Contaminated
{
Injured o
3.0 IWLEMENTATION CRI RIA t
3.1 Person (s) are injured in a radiologically controlled area and have a contaminated injury that can be treated on-site and released.-
3.2 Person (s) are injured in a radiologically controlled area and must I
be transported 'off-site for medical observation / treatment before '
being surveyed for contamination.
,^
1.0 S
e e
a e~
-m h---u.-6@4
-e.
ph g
--ee,m=,mm g
1004.16 Revision 2 i
3.3 Person (s) are injured or ill and have, or have the potential for, O
radioactive contamination on their clothing or skin and must be l
l transported'off-site for medical observation / treatment before I
l decontamination can occur.
3.4 Persor.(s) have received acute radiation dose in excess of 25 REM.
4.0 EMERGENCY ACTIONS 4.1 The Shift Supervisor / Emergency Director and Radiol ntrols l
Foreman shall be notified immediately upon disc ry the injured personnel.
NOTE:
The steps may be erfo d concurrently.
7 4.1.1 T
Sh Supervisor /E nc irector, upon notifica.
l on of injured pers n all:
Notify Site ersonnel at O.
If Site l
Medical s
1 are unavailab Shift Super.
visor cy Director s 1 first aid l
i stired to the inj r 11 personnel.
I NOTE:
ible the Shift or/ Emergency Director I
d provide the Med rst Aid personnel with s ecific ingress /egres ute for access and ient transfer. The Shift Supervisor / Emergency-Director should consult with Radiological Controls for this route if necessary.
b.
Ensure that First Aid / medical personnel evaluate the injury, to determine the need of medical treatment I
beyond that provided by on site personnel and that Radiological Controls evaluate the radiological _,
2.0 h
WM NV =* _
hg eem>M age e
+
e-e-me w
em
,,y
_m
,,--,og.,
.,.,.,,g
,,y.
1004.16 Revision 2 i
condition of the victim (if injury involved radio-O active contamination). and both report their assess-ment back to him.
NOTE:
Attachment I is a checklist 'for Radiological acticns. :
c.
If off-site medical assistance is requi the Shift Supervisor / Emergency Director desig-l nee) will notify Dauphin Co. EOC d
ing 9-911 and repeat the following me THIS IS b
AT TMI NUC TION. WE REQUEST LANCE AND MEDIC RT TO TMI UNIT 1 P
ESSING CENTER. k HAVE (POTENTIALLY) CONTAMIN.
l l
ATED PERSONNEL T
OWING INJURIES:
(BRIEF DESCRIPTIO ES) REQUIRING DICAL ASSIS_
i TANCE."
Call ur at Extension 0 to inform ty of off-site me ca as istance arrival so t
ey can direc
-1 medical personnel to e injured person.
hift Supervisor / Emergency v Director shall also initiate the requirements of EPIP 1004.19 " Emergency Dosimetry / Security Badge Issuance" d.
If appropriate, declare an Unusual Event in accor-l dance with EPIP 1004.1 and perform actions as.
required in Step 4.5 below.
O 3.0
\\
, W.
1004.16 Revision 2 4.1.2 The Shift Supervisor / Emergency' Director shall direct l
personnel with minor injuries, not requiring more medical attention than site first aid, to the decon, facility for l
decontamination and treatment of the injury, per step 4.2.
4.2 The Shift Supervisor /imergency Director shall, with concur _
rence of the available site medical and radiologi controls personnel have the victim transported outside o t dio-logically controlled area. if the injury a co ination levels will allow movement, for further t and surveys.
NOTE:
To e possible s read o ntamination, the :
Shif rvisor/Emergen tor should consider contaminated pe 2 evacuation route ro ed over the pa 4.3 I
injury allows, R i al. Controls personnel shall E'
assessthe5degreeof n exposure and radioactive
~
centamination p val from si NuTE:
All ccurring in a cally contamin- :
a shall be conside inated until and cleared.
4.4 The t
pervisor/Euergency ctor, with concurrence of the avai able site medical staff, shall order the injured person (s) off_ site for more extensive medical treatment.
i l
NOTE:
If the injured person is contaminated, or potentially :
contaminated, a Radiological Controls Technician will :
i be dispatched to H.M.C. to provide Radiological Controls as needed.-
j i
I
~,i 4.0 j
i,
--@M 96h*N g
gig-p p.
,_pp,
%q
1004.16 Revision 2 7.~ement with the sii on irHerseTMedicai-i
~
O i-N61Ei 87a t
Center (HMC). Hershey, PA, all contaminated persons with injuries too severe to be handled onsite shall be sent to H.M.C. for decontamination and ' treatment. :
s 4.5 The Shift Supervisor shall perform the following steps in the event an injured and contaminated or potentially c taminated person (s) is to be transported to HMC.
4.5.1 If an emergency classification is r ady in effect, the Shift Supervisor s the duties of Emergency Director.
4.5.2 T
ency Director 1 im lement the require-s of Emergency P an lementing Procedure
.1 " Unusual f not already declared and l
request amou ice from the auphin County GU Emergency s Center, as d, for offsite assis 4.5.3 Th Director or e
nee (Shift
, Conmiunicator tc hall call the Charge
- e. Emergency Ro H
at 9 534 8333, and using e following message, alert HMC of the arrival of
(
the injured victim:
"THIS.IS (NAME/ TITLE).AT THREE MILE ISLAND ACTING AS l
(FOR) THE EMERGENCY DIRECTOR. TMI IS PREPARING T0 i
TRANSFER A (POTENTIALLY) CONTAMINATED VICTIM WITH l
INJURIES TO HERSHEY MEDICAL CENTER. THE RADIATION i
EHERGENCY AREA SHOULD BE PREPARED TO RECEIVE THIS VICTIM. PLEASE ACKNOWLEDGE AND VERIFY THIS MESSAGE
--h.
5.0 w
1004.16 Revision 2 BY CALLING 948-8069 (8070/8071) AND ASK FOR THE b
l EMERGENCY DIRECTOR."
4.5.4 The Emergency Director, or his designer, shall then:
- briefly describe the injury (s)
- give the name of the victim (s)
- report levels of contamination, if kn
- request special equipment required
- estimate time of arrival at HMC
- describe method of transpor expected dose r ard to HMC Staff el based on dos aken 12 inches above victim record the n a
le of the person receiving A
the notifi
, and the ti otified L) 4.5.5
- Person (s) d ted shall recei body count-l ing in acc with RCP 1612 n 628.
4.6 The Emerge r
r shall requi a portation of per-son (s) radiation e s
excess of 25 REM whol HMC. In this c victim (s) can be trans-ported a conventional manner and will not require activa-tion of the Emergency Plan.
4.7 The Emergency Director and/or RAC may request assistance in evalua-tion of extreme radiation overexposure (i.e. 25 REM or more) from various kadiological Health Specialists (Porter Consultants, l
Radiation Management Corporation, etc' )
6.0
= = = = " _
,,,e y..,p,e
,p g,
~
1004.16 Revision 2 4.8 The Emergency Director and Radiological Assessment Coordinator i
shall restrict personnel who have received internal contamination of greater than 50 Percent of the Derived Investigatio'n level, as stated in RCP 1628.1, from further work in Airborne Radioactivity Areas, until evaluation is made. Complete and direct the personnel for whole body counting, in accordance with RCP 1612 valua-tion of Body Burdens.
5.0 FINAL CONDITION 5.1 The person (s) has been decontaminated, tre injury and released for wor Site Medical Sta f.
5.2 The person (s entered into th ssay program for whole body cou i RCP 1612 and RC 1 8.
5.3 The vi s) has been transpo HMC and has been admitted or
! h releasedadal)radioac
/used protecti clothing has oeen removed to TMI.
5.4 The R,adiological C n U echnician(s) w anied the vic-tin (s) to HMC h rdinated the radi i ety actions at the emergency.r hospital heal ic st has relieved the Radiolog rols Technician (s 5.5 The Radiatio Emergency Area and ambulance (s) used for transporta-tion of the victim (s) has been surveyed and cleared or decontamin-dted and cleared by the TMI Radiological Controls Technician (s).
5.6 The Unusual Event has been closed out by the Emergency Director.
\\
7.0 N
~
-. ~ ~,. -.
-7 9
1004.16 Revision 2 Attachment I Radiological Controls Checklist for Contaminated Injured Persons 6
..________.._____m_____.._____
NOTE:
The following actions should be performed or con-sidered while handling a contaminated injured person. :
These actions must not interfere with proper medical treatment of the person.
Check i.
Prevent contamination spread from the injured pe er persons / areas by: lining the stretcher, wrap ictim with a olanket, providing P
.s to stretcher bear
,c ring the trans-fer path, etc.
2.
Limit contam the ambulance an w by lining the ambu-Tance wi p
and providin P.
o the crew.
3.
The tec an that accompan victim to the hospital should have a radiation survey risker and an lance kit (located at Rad Con i Site Ambulanc 4.
If possible, verif ation and rad o
els enroute to the hospital.
5.
If ava11abl s
nd Rad Con Tec ho be sent to follow the ambulance hospital to assist monitoring and decontami.
nation as needed.
~
6.
Upon arrival at the hospital, and subsequently, the Rad con Tech should periodically update the Control Room with current status.
/ &
8.0
. W lm '
1004.16 Revision 2 Attachment I (Cont'd) '
Check 7.
If possible, have the ambulance crew standby in the ambulance until both are surveyed and released or with the Emergency Director's permission, have the ambulance return to TMI for survey and decon-tamination as necessary. Informi the Control Room of status of the ambulance.
6.
Rao Con Technician (s) at the hospital should co in t the Radia-tion Safety actions in the Emergency Room w t tending physician.
p.
When possible, tu ver Radiation Sa e ponsibilities to the Hospital He sicist. Remai t
hospital until the indivi s
itted or rele 10.
Survey th ath. traveled b lance personn 1 and the indi-vidual.
11.
Before leaving the
, ensure that al ctive trash and used P.C.s have c
ected and tha o gh survey of the nospital ene and adjacen a
applicable has been complete 12.
Ensure that Control Room is informed of the status.
t t
i
/
9.0 b
..W._