ML023250125
| ML023250125 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/06/2002 |
| From: | Entergy Nuclear Indian Point 3 |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| AP-18.2, Rev 10 | |
| Download: ML023250125 (23) | |
Text
26-OCT-02 Page:
DISTRIBUTION CONTROL LIST 9 .cument
.!.i Name: EMER PLAN CC-NAME NAME DEPT LOCATION 1 PLANT MANAGER'S OFFICE UNIT 3(UNIT 3/IPEC ONLY) 45-3-B
2 EP/TRAINING ADMINISTRATOR TRAINING (ALL EP'S) #48 3 RES DEPARTMENT MANAGER RES (UNIT 3/IPEC ONLY) 45-4-A 4 REFERENCE LIBRARY REC/TRN(UNT 3/IPEC ONLY) 45-3-F 9 JOINT NEWS CENTER EMER PLN (ALL EP'S) EOF 10 SHIFT MGR.(LUB-001-GEN) OPS (UNIT 3/IPEC ONLY) IP3 11 CONTROL ROOM & MASTER OPS (3PT-DO01/6 (U3/IPEC) IP3 (ONLY) 14 EOF E-PLAN (ALL EP'S) EOF 16 AEOF/A.GROSJEAN(ALL EP'S) E-PLAN (EOP'S ONLY) WPO- 12D 19 NUC ENGINEERING LIBRARY DOC (UNIT 3/IPEC ONLY) WPO/7A 21 TSC RECORDS 45-3-F 22 RESIDENT INSPECTOR US NRC(UNIT 3/IPEC ONLY) 45-2-B 23 MCNAMARA N NRC (ALL EP'S) OFFSITE 24 MCNAMARA N NRC (ALL EP'S) OFFS ITE Q5 DOfCtJMENT ?JONTROL DES K_ NRC (ALL EP'S) OFFS ITE 28-AVRAKOTOS N J A(UNIT 3/IPEC ONLY) OFFSITE 29 E-PLAN STAFF E-PLAN (ALL EP'S) EOF 30 E-PLAN STAFF E-PLAN (ALL EP'S) EOF 31 BARANSKI J(VOLUME I ONLY) ST. EMERG. MGMT. OFFICE OFFSITE 32 SUTTON A -(VOLUME I ONLY) DISASTER & EMERGENCY WESTCHESTR 33 LONGO N (VOLUME I ONLY) EMERGENCY SERVICES ROCKLAND 34 GREENE D (VOLUME I ONLY) DISASTER & CIVIL DEFENSE ORANGE 35 RAMPOLLA M(VOLUME I ONLY) OFFICE OF EMERG MANAGE PUTNAM 41 SIMULATOR TRAIN(UNIT 3/IPEC ONLY) 48-2-A 107 QA MANAGER QA (UNIT 3/IPEC) TRL #2A 319 C.STELLATO(NRQ-OPS TRN) NRQ (UNIT 3/IPEC ONLY) #48 354 L.GRANT(LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 376 E-PLAN STAFF E-PLAN (ALL EP'S) EOF 424 J.CHIUSANO(OPS INSTR) (UNIT 3/IPEC ONLY) #48 510 L.GRANT(LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 511 L.GRANT (LRQ-OPS/TRAIN) LRQ (UNIT 3/IPEC ONLY) #48 512 C.STELLATO(NRQ-OPS TRN) NRQ (UNIT 3/IPEC ONLY) #48 513 C.STELLATO(NRQ-OPS TRN) NRQ (UNIT 3/IPEC ONLY) #48 517 PLANT MANAGER'S OFFICE ADMIN/(UNIT 2/IPEC ONLY) IP2 518 TSC UNIT 2(UNIT 2/IPEC ONLY) IP2 520 CONTROL ROOM (UNIT 2) OPS (UNIT 2 & IPEC ONLY) IP2 521 SIMULATOR TRAIN (UNIT 2/IPEC ONLY) IP2 5 2 NRC RESIDENT US NRC(UNIT 2/IPEC ONLY) IP2 5 3 ROBERT VOGLE (UNIT 2) TRAIN/LIB (ALL EP'S) TODDVILLE 524 JOHN MCCANN (UNIT 2) NUC SAFETY/LIC(ALL EP'S) IP2
a; Entergy Indian Point 3 Attachment 1 AP-18,2 Page lof 1 Revision 10 CONTROLLED DOCUMENT TRANSMITTAL FORM DATE 11/6/2002 TRANSMITT'AL NO: 27419 TO: DISTRIBUTION EXTENSION: 2038 FROM:1P3 DOCUMENT CONTROL GROUP with AP-18.2, please review to The Document(s) identified below are forwarded for use. In accordance file, properly disposition verify receipt, incorporate the document(s) into your controlled document acknowledgement below within fifteen superseded, void, or inactive document(s). Sign and return the receipt (15) working days.
EMERGENCY PROCEDURES IP3 AFFECTED DOCUMENT:
REV # TITLE INSTRUCTIONS DOC #
- FOLLOW ATTACHED INSTRUCTIONS***************
- PLEASE NOTE EFFECTIVE DATES**
I CERTIFY THAT ALL RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED.
LISTED DOCUMENT(S) IN MY POSSESSION SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE BEEN PERFORMED IN ACCORDANCE HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE ON THE DOCUMENT(S).
WITH EFECTIVE DATE(S) (IF APPLICABLE) AS SHOWN SIGNATURE DATE CC#
N-AME (PRINT)
Nuclear Regulatory Commission TO:
trpý FROM: IPEC Emergency Planning I'
SUBJECT:
Emergency Planning Document Update Date: 11/05/02 Please update your controlled copy of the documents listed below as specified with the copy(s) attached.
Please sign this memo indicating that you have completed the update as specified and return to:
Entergy Nuclear Indian Point Nuclear Generating Station Records and Documents Department Broadway & Bleakley Aves.
Buchanan, NY 10511 Attn: Document Custodian mnergency Use ot F Iodide (KI) 10 9 Replace Entire 11/5/02 11/18/97 Document IP-1040 Habitability of the Emergency 17 16 Replace Entire Response Facilities and 11/5/02 11/18/97 Document Assembly Areas IP-1063 Vehicle/Equipment 12 11 Replace Entire Radiological Check and 11/5/02 11/18/97 Document Decontamination TOC Table of Contents 11/02 8/02 Replace Entire Document Update completed as specified:
Signature of Controlled Copy Holder Date IA
VOLUME III TABLE OF CONTENTS 11/02 ENTERGY NUCLEAR NORTHEAST I INDIAN POINT NO. 3 NUCLEAR POWER PLANT EMERGENCY PLAN - VOLUME III IMPLEMENTING PROCEDURES TABLE OF CONTENTS PROCEDURE TITLE REV. DATE PROCEDURE #
Dose Assessment Determining the Magnitude of Release VOID N/A IP-1001 Replaced by IP-EP-310 Post-Accident Monitoring of Noble Gas 4 02/99 IP-1002 Concentration in Plant Vent VOID N/A IP-1003 Obtaining Meteorological Data Replaced by IP-EP-510 Midas Computer System VOID N/A IP-1004 Replaced by IP-EP-510 Environmental Monitoring Offsite Monitoring/Site Perimeter Surveys 244 05/99 IP-1011 02/99 IP-1012 Emergency Airborne Activity Determination 7 12/98 IP-1015 Post-Accident Environmental Sampling and Counting Protective Actions IP-1017 Protective Action Recommendations for VOID N/A the Offsite Population Replaced by IP-EP-410 Emergency Use of Potassiun Iodide (KI) 10 11/02 IP-1019 Personnel Inlur2X 25 06/98 IP-1021 Radiological Medical Emergency VOID N/A IP-1023 Use and Set Up of the IP3 Personnel Decon Suite Damage Assessm4ent IP-1025 Repair and Corrective Action Teams 12 12 12/98 12/97 IP-1027 Emergency Personnel Exposure 9 06/98 IP-1028 Core Damage Assessment Notification and Communication IP-1038 Offsite Emergency Notifications 264 09/01 02/01 IP-1039 Emergency Response Data System (ERDS)
Activation and Testing i
VOLUME III TABLE OF CONTENTS 11/02 ENTERGY NUCLEAR NORTHEAST INDIAN POINT NO. 3 NUCLEAR POWER PLANT EMERGENCY PLAN - VOLUME III IMPLEMENTING PROCEDURES TABLE OF CONTENTS PROCEDURE # PROCEDURE TITLE REV. DATE Emergency Response Facilities IP-1040 Habitability of the Emergency Response 17 11/02 Facilities and Assembly Areas IP-1041 Personnel Monitoring for EOF, TSC, OSC VOID N/A and Control Room Personnel Accountability and Evacuation IP-1050 Accountability 28 08/02 IP-1053 Evacuation of Site 13 03/02 IP-1054 Search and Rescue Teams 11 08/02 Non-Radiological Emergencies IP-1052 Hazardous Waste Emergency 8 07/02 IP-1055 Fire Emergency Response 15 04/02 IP-1056 Directing Fire Fighting Personnel in VOID N/A Controlled Area IP-1057 Natural Phenomena Emergency 8 10/01 IP-1058 Earthquake Emergency VOID N/A IP-1059 Air Raid Alert 7 05/01 H.P. Release Surveys and Decontamination IP-1060 Personnel Radiological Check and 11 02/98 Decontamination IP-1063 Vehicle/Equipment Radiological Check 12 11/02 and Decontamination Emergency Equipment and Maintenance IP-1070 Periodic Inventory of Emergency Plan 31 02/01 Equipment IP-1076 Roster Notification Methods 26 05/02 IP-1080 Conduct of Emergency Exercises and Drills VOID N/A IP-1085 Maintenance of Emergency Preparedness VOID N/A at IP-3 ii
JEnter~gy I CONTROLLED COPY #:
EMERGENCY PLAN PROCEDURES PROCEDURE NO. IP-1019 REV. 10 TITLE: EMERGENCY USE OF POTASSIUM IODINE (KI)
THIS PROCEDURE IS TSR THIS PROCEDURE IS NOT TSR tArn TrTm; THIS BY: U IS T02S //13 SIGNATURE/DATE REVIEWED BY:
T SA 1" URE/ '
APPROVED BY:
EFFECTIVE DATE:
K (ATuRf/oDATE PROCEDURE USE IS 1
I REFERENCE
VOLUME III IP-1019 Rev. 10 EMERGENCY USE OF POTASSIUM IODIDE (KI)
TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Purpose 1 2.0 Responsibilities 1 3.0 References 1 4.0 Procedure 1 5.0 Attachments 5.1 Patient Package Insert for THYRO BLOCK Potassium Iodide
VOLUME III IP-1019 Rev. 9 IP-1019 EMERGENCY USE OF POTASSIUM IODIDE (KI)
'.1 1.0 PURPOSE 1.1 This procedure provides guidance for the use of thyroid blocking potassium iodide (KI). KI is used to saturate the thyroid with stable iodine to limit the uptake of radioiodine.
2.0 RESPONSIBILITY 2.1 The Emergency Director (ED) is responsible for authorizing the IR administration of KI to Entergy employees.
2.2 The Radiological Assessment Team Leader (RATL) is responsible for:
A. Assessing the need for administering KI to Entergy employees. V B. Advising the ED on the administration of KI.
3.0 REFERENCES
3.1 EPA 400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" 3.2 National Council on Radiation Protection Report 55 4.0 PROCEDURE 4.1 The RATL takes the following steps to evaluate if the use of KI should be recommended to the ED.
A. IF a radiological release has occurred or is anticipated, THEN ENSURE monitoring for radioiodine is being conducted in the following areas:
- 1. Control Room (CR)
- 2. Operational Support Center (OSC) / Technical Support Center (TSC)
- 3. Emergency Operations Center (EOF)
- 4. Other locations where Entergy personnel may be exposed to radioiodine concentrations (e.g. Offsite Monitoring Teams, Repair and Corrective Action Teams and/or Security).
NOTE:
For the purpose of this procedure the term "Entergy personnel" includes all employees who respond to an emergency at Indain Point.
IP-1019 Page 1 of 3
VOLUME III IP-1019 Rev. 9 B. IF radioiodine samples indicate levels above Minimum Detectable Activity (MDA), THEN REQUEST that isotopic monitoring be c6nducted, if practical.
C. ASSESS thyroid Committed Dose Equivalent (CDE) for Entergy personnel using actual or estimated data for radioiodine concentrations and stay times.
NOTE:
The following Dose Conversion Factors should be used to determine thyroid CDE based on airborne radioiodine concentration:
MIX' DCF = 4.00E08 mRem/hr gCi/cc 1-131 DCF = 1.30E09 mRem/hr gCi/cc 1-132 DCF = 7.50E06 mRem/hr gCi/cc 1-133 DCF = 2.20E08 mRem/hr gCi/cc 1-134 DCF = 1.30E06 mRem/hr 9Ci/cc 1-135 DCF = 3.80E07 mRem/hr 9Ci/cc
'To be used for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after shutdown when the radioiodine mix is not known. The 1-131 DCF is to be used for times greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after shutdown when the radioiodine mix is not known.
4.2 IF thyroid CDE is expected to exceed 25 Rem for any Entergy personnel, IJ.
THEN the RATL should RECOMMEND to the ED that KI be issued to these individuals.
4.3 IF thyroid CDE is not expected to exceed 25 Rem for any Entergy personnel THEN, the RATL should NOT RECOMMEND that KI be issued.
4.4 Based on the recommendation from the RATL, the ED shall DETERMINE if KI will be issued to Entergy personnel.
IP-1019 Page 2 of 3
VOLUME III IP-1019 Rev. 9 4.5 IF it is determined that KI will be issued to Entergy personnel, THEN 1p, the ED should ENSURE the following guidelines are followed:
A. If practical, the individual receiving the KI should review either Attachment 5.1, "Patient Package Insert for THYRO-BLOCK Potassium Iodide" OR the actual patient insert accompanying the KI.
B. PRIOR to administering KI, ask individuals if they are allergic to iodine. (If the individual has had allergic reactions to shell fish, this probably indicates an iodine allergy).
C. Administer one tablet (130 mg) of KI for the initial dose followed by daily doses of one tablet per day for 3 to 10 days.
D. Consult with medical representatives as soon as practical after administering KI to receive guidance on total dose requirements.
Appendix 'B' in Volume II of the Emergency Plan includes the phone Indian number of a medical representative under contract with Point.
4.6 KI is kept in the following areas:
"*OSC Manager's Locker
"*CR Emergency Locker
"* EOF Health Physics Locker
"* Offsite Monitor Supply Bags JR
"* Additional supplies are available from Indian Point Medical offices.
NOTE:
DO NOT carry KI in their vehicles.
IP-2 Offsite Monitoring Team Personnel They will have to be given KI at the EOF or receive it from IP-3 Offsite Monitoring Team Personnel.
5.0 ATTACHMENTS 5.1 Patient Package Insert for THYRO BLOCK Potassium Iodide END OF TEXT IP-1019 Page 3 of 3
VOLUME III IP-1019 Rev. 10 Page 1 of 1 ATTACHMENT 5.1 PATIENT PACKAGE INSERT FOR THYRO-BLOCK POTASSIUM IODIDE THYRO-BLOCK HOW POTASSIUM IODIDE WORKS TABLETS Certain forms of iodine help your thyroid gland work right. Most (POTASSIUM IODIDE TABLETS, USP) people get the iodine they need from foods, like iodized salt or (pronounced poe-TASS-e-um EYE-oh-dyed) fish. The thyroid can "store" or hold only a certain amount of (abbreviated KI) iodine.
In a radiation emergency, radioactive iodine may be released in the air. This material may be breathed or swallowed. It may enter the thyroid gland and damage it. The damage vWould pro TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC bably not show itself for years. Children are most hkely to have HEALTH OFFICIALS TELL YOU. IN A RADIATION thyroid damage.
EMERGENCY. RADIOACTIVE IODINE COULD BE If you take potassium iodide, it will fill up your thyroid gland.
RELEASED INTO THE AIR. POTASSIUM IODIDE (A This reduces the chance that harmful radioactive iodine will FORM OF IODINE) CAN HELP PROTECT YOU. enter the thyroid gland.
IF YOU ARE TOLD TO TAKE THIS MEDICINE. TAKE IT WHO SHOULD NOT TAKE POTASSIUM IODIDE ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE The only people who should not take potassium iodide are people OFTEN. MORE WILL NOT HELP YOU AND MAY IN who know they are allergic to iodide. You may take potassium CREASE THE RISK OF SIDE EFFECTS. DO NOT TAKE iodide even if you are taking medicines for a thyroid problem (for THIS DRUG IF YOU KNOW YOU ARE ALLERGIC TO example, a thyroid hormone or antithyroid drug). Pregnant and IODIDE. (SEE SIDE EFFECTS BELOW.) nursing women and babies and children may also take this drug.
HOW AND WHEN TO TAKE POTASSIUM IODIDE Potassium Iodide should be taken as soon as possible after public health officials tell you. You should take one dose every 24 INDICATIONS hours. More will not help you because the thyroid can "hold" on THYROID BLOCKING IN A RADIATION EMERGENCY ly limited amounts of iodine. Larger doses will increase the risk ONLY. of side effects. You will probably be told not to take the drug for
<- more than 10 days.
DIRECTIONS FOR USE Use only as directed by State or local public health authorities in SIDE EFFECTS the event of a radiation emergency. Usually, side effects of potassium iodide happen when people take higher doses for a long time. You should be careful not to DOSE take more than the recommended dose or take it for longer than Tablets: ADULTS AND CHILDREN 1 YEAR OF you are told. Side effects are unlikely because ofthe low dose and AGE OR OLDER- One (11 tablet once a the short time you will be taking the drug.
day. Crush for small children.
Possible side effects include skin rashes, swelling of the salivary BABIES UNDER I YEAR OF AGE:
glands, and "iodism" (metallic taste, burning mouth and throat.
One-half (1/2) tablet once a day. Crush first.
sore teeth and gums, symptoms of a head cold, and sometimes stomach upset and diarrhea).
Take for 10 days unless directed otherwise by State or local A few people have an allergic reaction with more serious symp public health authorities. toms. These could be fever and joint pains, or swelling of parts of the face and body and at times severe shortness of breath requir.
Store at controlled room temperature between 150 and 30°C (59° ing immediate medical attention to 86°F). Keep container tightly closed and protect from light.
Taking iodide may rarely cause overactivity of the thyroid gland. underactivity of the thyroid gland, or enlargement of the WARNING thyroid gland (goiter).
Potassium iodide should not be used by people allergic to iodide.
Keep out of the reach of children. In case of overdose or allergic WHAT TO DO IF SIDE EFFECTS OCCUR reaction, contact a physician or the public health authority. If the side effects are severe or if you have an allergic reaction, stop taking potassium iodide. Then. if possible, call a doctor or public health authority for instructions DESCRIPTION Each THYRO-BLOCK TABLET contains 130 mg of HOW SUPPLIED potassium iodide. Other ingredients- magnesium stearate, THYRO-BLOCK TABLETS (Potassium Iodide Tablets, USP}
microcrystalline cellulose, silica gel, sodium thiosulfate. bottles of 14 tablets (NDC 0037-0472-20 ). Each white, round, scored table" contains 130 mg potassium iodide
J2ff;n tý CONTROLLED COPY #:
EMERGENCY PLAN PROCEDURES PROCEDURE NO. IP-1040 REV. 17 TITLE: HABITABILITY OF THE EMERGENCY RESPONSE FACILITIES AND ASSEMBLY AREAS THIS PROCEDURE IS TSR THIS PROCEDURE IS NOT TSR WRITTEN BY: I,/31oý_
&ex SINATURDATE 1 13 REVIEWED BY: Q'Ar Av 0ViWI APPROVED BY:
V,..fSIGNA72U/,/DATE
ý-)-d I/u/
- l DATE EFFECTIVE DATE:
PROCEDURE USE IS REFERENCE
Volume III IP-1040 Rev. 17 HABITABILITY OF THE EMERGENCY RESPONSE FACILITIES AND ASSEMBLY AREAS TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Purpose 1 2.0 Responsibilities 1 3.0 References 1 4.0 Procedure 2 5.0 Attachments 4 None
Volume III IP-1040 Rev. 17
.- ABITABILITY OF THE EMERGENCY RESPONSE FACILITIES AND ASSEMBLY AREAS 1.0 PURPOSE 1.1 This procedure provides guidance for determining the radiological habitability in the Emergency Response Facilities (ERFs) and Assembly Areas in order to maintain personnel exposure as low as reasonably achievable (ALARA).
2.0 RESPONSIBILITY 2.1 The Emergency Director (ED) is responsible for determining if relocation of an ERF or the evacuation of an Assembly Area is warranted.
2.2 The Radiological Assessment Team Leader (RATL) has the overall responsibility to determine radiological habitability in all ERFs and Assembly Areas and shall ensure that adequate radiological monitoring is being performed in the Emergency Operations Facility (EOF).
2.3 The Operational Support Center (OSC) Health Physics (HP) Team Leader will ensure that adequate radiological monitoring is performed in the OSC, Technical Support Center (TSC), Control Room (CR) and Assembly Areas.
2.4 The facility managers of the ERFs are responsible for ensuring this procedure is followed within their facility.
3.0 REFERENCES
3.1 EPA 400, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents".
3.2 10CFR20, "Standards for Protection Against Radiation".
3.3 IP-2002, "CR Health Physics Technician" 3.4 IP-2209, "OSC HP Technician" 3.5 IP-1027, "Emergency Personnel Exposure".
3.6 IP-1050, "Accountability" 3.7 IP3-RES-93-427, Memorandum from Dauer to Mayer, "PAG Source Terms".
IP-1040 Page 1 of 4
Volume III IP-1040 Rev. 17 4.0 PROCEDURE 4.1 ERF and Assembly Area Radiological Monitoring:
A. Radiological monitoring of the ERFs and Assembly Areas is covered by the following procedures:
Control Room: IP-2002, "CR Health Physics Technician" OSC/TSC: IP-2209, "OSC HP Technician" Assembly Areas: IP-1050, "Accountability" B. IF conditions warrant, THEN the OSC HP Team Leader will send HP Technicians to the Assembly Areas to perform additional radiological monitoring.
4.2 Guidelines for eating, drinking and smoking during a Radiological Release:
NOTE:
Overheated individuals SHALL NOT be denied fluids due to the radiological conditions in the ERF.
A. IF a radiological release is occurring or has occurred, THEN eating, drinking or smoking should not be allowed in Assembly Areas unless authorized by the OSC HP Team Leader following the establishment of appropriate radiological monitoring.
B. IF a radiological release is occurring or has occurred, and the radiological conditions within an ERF are not known, THEN eating, drinking or smoking should not be allowed.
C. IF a radiological release is occurring or has occurred, and the radiological conditions within an ERF are known, and the total airborne radioactivity concentration (excluding noble gasses) exceeds 1 DAC (Derived Air Concentration defined in Reference 3.1), THEN eating, drinking or smoking should not be allowed.
D. All consumable items (eg: food, water, cigarettes) which may have become radiologically contaminated shall be monitored by Health Physics prior to consumption.
IP-1040 Page 2 of 4
Volume III IP-1040 Rev. 17 4.3 Guidelines for Relocation ERFs:
NOTE:
The following Dose Conversion Factors should be used to determine Committed Effective Dose Equivalent (CEDE) and thyroid Committed Dose Equivalent (CDE) based on airborne concentrations:
Particulate DCF = 2.66E07 mRem/hr iCi/cc MIX1 DCF = 4.00E08 mRem/hr iCi/cc 1-131 DCF = 1.30E09 mRem/hr iCi/cc 1-132 DCF = 7.50E06 mRem/hr iCi/cc 1-133 DCF = 2.20E08 mRem/hr iCi/cc 1-134 DCF = 1.30E06 mRem/hr lCi/cc 1-135 DCF = 3.80E07 mRem/hr iCi/cc To be used for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after shutdown when the radioiodine mix is not known. The 1-131 DCF is to be used for times greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after shutdown when the radioiodine mix is not known.
IP-1040 Page 3 of 4
Volume III IP-1040 Rev. 17 A. Relocation of an ERF should not be considered if the expected total accumulated dose equivalent to the staff in the ERF will be less than 500 mRem TEDE (Total Effective Dose Equivalent as defined in Reference 3.2) or 5 Rem Thyroid TODE (Total Organ Dose Equivalent as defined in Reference 3.2). However, transfer of the EOF to the Alternate EOF (AEOF) location may be performed due to expected doses below these levels provided such a transfer is performed without adversely impacting the function of the EOF.
B. IF the total expected dose equivalent in an ERF is expected to exceed 500 mRem TEDE or 5 Rem Thyroid TODE, THEN consideration should be given to relocate the ERF based on the following:
- 1. Total expected dose equivalent.
- 2. The effect relocating the ERF will have on the accident mitigation effort.
- 3. The exposures of individuals in the ERFs.
C. IF the 10CFR20 exposure limits are expected to be exceeded for individuals in the ERF, THEN relocation of the ERF should occur unless one of the following exists:
- 1. Relocation would result in the ERF staff receiving a greater dose than the dose received by staying in the ERF.
- 2. The ED has determined that the ERF staff are performing a function which meets the criteria for receiving Emergency Worker Dose Limits as defined in IP-1027, "Emergency Personnel Exposure" 5.0 ATTACHMENTS None END OF TEXT IP-1040 Page 4 of 4
124ntffgy CONTROLLED COPY #:
EMERGENCY PLAN PROCEDURES PROCEDURE NO. IP-1063 REV. 12 TITLE: VEHICLE/EOUIPMENT RADIOLOGICAL CHECK AND DECONTAMINATION THIS PROCEDURE IS TSR THIS PROCEDURE IS NOT TSR WRITTEN BY: 9,ý
- * " ll" 111310 1
SIGNATURE/DATE REVIEWED BY:
""*" (d,,fc/o SIGN TURE/DATE APPROVED BY: LtL k,,
S MDATE EFFECTIVE DATE:
PROCEDURE USE IS f
1 REFERENCE
VOLUME III IP-1063 Rev. 12 VEHICLE/EQUIPMENT RADIOLOGICAL CHECK AND DECONTAMINATION TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Purpose 1 2.0 Responsibilities 1 3.0 References 1 4.0 Procedure 2 5.0 Attachments 3 IK 5.1 IPEC Service Center Layout
VOLUME III IP-1063 Rev. 12 IP-1063 VEHICLE/EQUIPMENT RADIOLOGICAL CHECK AND DECONTAMINATION 1.0 PURPOSE This procedure describes the methods of checking vehicles and equipment for contamination and their subsequent decontamination at the Indian Point Energy Center(IPEC) Service Center when required.
2.0 RESPONSIBILITIES 2.1 The Radiological Assessment Team Leader (RATL) is responsible for ensuring this procedure is followed.
or 2.2 The Emergency Director (ED) is responsible for authorizing vehicles equipment to leave the site with measurable contamination or without being radiologically monitored when otherwise required.
is 2.3 The Operations Support Center (OSC) Health Physics (HP) Team Leader responsible for dispatching HP technicians to perform radiological monitoring if requested by the Emergency Operations Facility (EOF).
3.0 REFERENCES
3.1 EP-Form #16 "Vehicle Contamination Check" 3.2 EP-Form #17 "Equipment Contamination Check" IP-1063 Page 1 of 3
VOLUME III IP-1063 Rev. 12 NOTE:
For this procedure, measurable contamination is defined as > 100 CPM above background using a frisker.
4.0 PROCEDURE 4.1 IF a radiological release is occurring or has occurred, THEN the RATL shall determine if vehicles and equipment require radiological monitoring or decontamination prior to leaving the site using the following guidelines:
A. Radiological and decontamination of vehicles and equipment leaving the site should NOT be performed IF:
- 1. There is known or expected measurable contamination immediately offsite.
- 2. The radiological monitoring or decontamination effort will lead to personnel evacuating the site receiving excess radiation exposure due to increased time spent in the plume.
- 3. Results of site surveys indicate that no measurable contamination is present.
B. Radiological monitoring may be ended if no measurable contamination is found on a representative amount of equipment or vehicles.
4.2 Upon request from the RATL, the OSC HPTL shall dispatch Health Physics technicians to perform site surveys and radiological monitoring of vehicles and equipment.
4.3 Radiological monitoring of vehicles and equipment should be performed as follows:
A. Take large area wipes of vehicles or equipment and count wipe with a frisker.
B. IF large area wipes show measurable contamination, THEN use paper smears to attempt to isolate the location of the contamination.
C. Take direct readings with a frisker to spot check vehicle and equipment for fixed contamination.
4.4 IF the vehicle or equipment is contaminated, THEN perform the IP-1063 Page 2 of 3
VOLUME III IP-1063 Rev. 12 following:
A. Have the vehicle or equipment moved to the decontamination location in the northeast corner of the IPEC Service Center (see Attachment 5.1, "IPEC Service Center Layout").
B. Position the vehicle or equipment close to the corner water run-off opening. This will allow contamination to run off into a small land depression where it will be contained and concentrated by the contour.
C. Isolate and post the run off area, as necessary.
a D. Using hoses hooked up to the nearest fire hydrant or utilizing Fire Department pumper, decontaminate the vehicle or equipment.
E. IF the vehicle or equipment is still contaminated, THEN continue the decontamination effort.
4.5 Record all required data on EP-Form #16, "Vehicle Contamination Return these Check" or EP-Form #17, "Equipment Contamination Check".
forms to the RATL or HPTL.
the 4.6 IF it is necessary to have a vehicle or piece of equipment leave site either with measurable contamination or without being monitored THEN the ED shall authorize such action.
5.0 ATTACHMENTS 5.1 IPEC Service Center Layout V
END OF TEXT IP-1063 Page 3 of 3
VOLUME III IP-1063 Rev. 12 Page 1 of 1 ATTACHMENT 5.1 IPEC SERVICE CENTER LAYOUT VR S
E W E-4N --W N
0