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 DISTRIBUTION CONTROL LIST 9
.cument Name:
EMER PLAN
.!.i CC-NAME NAME 1 PLANT MANAGER'S OFFICE
2 EP/TRAINING ADMINISTRATOR 3 RES DEPARTMENT MANAGER 4 REFERENCE LIBRARY 9 JOINT NEWS CENTER 10 SHIFT MGR.(LUB-001-GEN) 11 CONTROL ROOM & MASTER 14 EOF 16 AEOF/A.GROSJEAN(ALL EP'S) 19 NUC ENGINEERING LIBRARY 21 TSC 22 RESIDENT INSPECTOR 23 MCNAMARA N 24 MCNAMARA N Q5 DOfCtJMENT ?JONTROL DES K_
28-AVRAKOTOS N 29 E-PLAN STAFF 30 E-PLAN STAFF 31 BARANSKI J(VOLUME I ONLY) 32 SUTTON A -(VOLUME I ONLY) 33 LONGO N (VOLUME I ONLY) 34 GREENE D (VOLUME I ONLY) 35 RAMPOLLA M(VOLUME I ONLY) 41 SIMULATOR 107 QA MANAGER 319 C.STELLATO(NRQ-OPS TRN) 354 L.GRANT(LRQ-OPS/TRAIN) 376 E-PLAN STAFF 424 J.CHIUSANO(OPS INSTR) 510 L.GRANT(LRQ-OPS/TRAIN) 511 L.GRANT (LRQ-OPS/TRAIN) 512 C.STELLATO(NRQ-OPS TRN) 513 C.STELLATO(NRQ-OPS TRN) 517 PLANT MANAGER'S OFFICE 518 TSC 520 CONTROL ROOM (UNIT 2) 521 SIMULATOR 5 2 NRC RESIDENT 5 3 ROBERT VOGLE (UNIT 2) 524 JOHN MCCANN (UNIT 2)
DEPT UNIT 3(UNIT 3/IPEC ONLY)
TRAINING (ALL EP'S)
RES (UNIT 3/IPEC ONLY)
REC/TRN(UNT 3/IPEC ONLY)
EMER PLN (ALL EP'S)
OPS (UNIT 3/IPEC ONLY)
DOC (UNIT 3/IPEC ONLY)
RECORDS US NRC(UNIT 3/IPEC ONLY)
NRC (ALL EP'S)
NRC (ALL EP'S)
NRC (ALL EP'S)
J A(UNIT 3/IPEC ONLY)
ST.
EMERG.
MGMT.
OFFICE DISASTER & EMERGENCY EMERGENCY SERVICES DISASTER & CIVIL DEFENSE OFFICE OF EMERG MANAGE TRAIN(UNIT 3/IPEC ONLY)
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TRAIN (UNIT 2/IPEC ONLY)
US NRC(UNIT 2/IPEC ONLY)
TRAIN/LIB (ALL EP'S)
NUC SAFETY/LIC(ALL EP'S)
Page:
LOCATION 45-3-B
- 48 45-4-A 45-3-F EOF IP3 IP3 (ONLY)
EOF WPO-12D WPO/7A 45-3-F 45-2-B OFFSITE OFFS ITE OFFS ITE OFFSITE EOF EOF OFFSITE WESTCHESTR ROCKLAND ORANGE PUTNAM 48-2-A TRL #2A
- 48
- 48 EOF
- 48
- 48
- 48
- 48
- 48 IP2 IP2 IP2 IP2 IP2 TODDVILLE IP2
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En tergy Indian Point 3 AP-18,2 Page lof 1 Revision 10 CONTROLLED DOCUMENT TRANSMITTAL FORM TO: DISTRIBUTION DATE 11/6/2002 TRANSMITT'AL NO: 27419 FROM:1P3 DOCUMENT CONTROL GROUP EXTENSION: 2038 The Document(s) identified below are forwarded for use. In accordance with AP-18.2, please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s). Sign and return the receipt acknowledgement below within fifteen (15) working days.
AFFECTED DOCUMENT:
EMERGENCY PROCEDURES IP3 DOC #
REV #
TITLE INSTRUCTIONS
- FOLLOW ATTACHED INSTRUCTIONS***************
- PLEASE NOTE EFFECTIVE DATES**
RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED. I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH EFECTIVE DATE(S) (IF APPLICABLE) AS SHOWN ON THE DOCUMENT(S).
N-AME (PRINT)
SIGNATURE DATE CC#
TO:
Nuclear Regulatory Commission FROM:
IPEC Emergency Planning I'
SUBJECT:
Emergency Planning Document Update Date: 11/05/02 trpý 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 11/5/02 9
11/18/97 Replace Entire 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 INDIAN POINT NO.
3 NUCLEAR POWER PLANT EMERGENCY PLAN -
VOLUME III IMPLEMENTING PROCEDURES PROCEDURE #
Dose Assessment TABLE OF CONTENTS PROCEDURE TITLE Determining the Magnitude of Release Replaced by IP-EP-310 Post-Accident Monitoring of Noble Gas Concentration in Plant Vent Obtaining Meteorological Data Replaced by IP-EP-510 Midas Computer System Replaced by IP-EP-510 VOID N/A 4
02/99 VOID N/A VOID N/A Environmental Monitoring Offsite Monitoring/Site Perimeter Surveys Emergency Airborne Activity Determination Post-Accident Environmental Sampling and Counting Protective Actions IP-1017 IP-1019 Personnel Inlur IP-1021 IP-1023 Damage Assessm4 IP-1025 IP-1027 IP-1028 Protective Action Recommendations for the Offsite Population Replaced by IP-EP-410 Emergency Use of Potassiun Iodide (KI) 2X Radiological Medical Emergency Use and Set Up of the IP3 Personnel Decon Suite ent Repair and Corrective Action Teams Emergency Personnel Exposure Core Damage Assessment VOID N/A 10 11/02 25 06/98 VOID N/A 12 12 9
12/98 12/97 06/98 Notification and Communication Offsite Emergency Notifications Emergency Response Data System (ERDS)
Activation and Testing i
IP-1001 IP-1002 IP-1003 IP-1004 DATE IP-1011 IP-1012 IP-1015 24 4 7
05/99 02/99 12/98 IP-1038 IP-1039 26 4 09/01 02/01 I
REV.
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
JEn ter~gy I
CONTROLLED COPY #:
EMERGENCY PLAN PROCEDURES PROCEDURE NO.
TITLE:
IP-1019 REV.
EMERGENCY USE OF POTASSIUM IODINE (KI)
THIS PROCEDURE IS TSR THIS PROCEDURE IS NOT TSR THIS BY:
U IS
//13 T02S REVIEWED BY:
APPROVED BY:
EFFECTIVE DATE:
SIGNATURE/DATE 1"
SA T URE/
K (ATuRf/oDATE 10 tArn TrTm; PROCEDURE USE IS REFERENCE 1
I
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.
Page 1 of 3 IP-1019
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.
4.2 IF thyroid CDE is expected to exceed 25 Rem for any Entergy personnel, 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.
Page 2 of 3 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 9 Ci/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.
IJ.
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.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 number of a medical representative under contract with Indian 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:
IP-2 Offsite Monitoring Team Personnel DO NOT carry KI in their vehicles.
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 Page 3 of 3 IP-1019
VOLUME III IP-1019 Rev. 10 Page 1 of 1 ATTACHMENT 5.1 PATIENT PACKAGE INSERT FOR THYRO-BLOCK POTASSIUM IODIDE THYRO-BLOCK TABLETS (POTASSIUM IODIDE TABLETS, USP)
(pronounced poe-TASS-e-um EYE-oh-dyed)
(abbreviated KI)
TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC HEALTH OFFICIALS TELL YOU. IN A RADIATION EMERGENCY.
RADIOACTIVE IODINE COULD BE RELEASED INTO THE AIR. POTASSIUM IODIDE (A FORM OF IODINE) CAN HELP PROTECT YOU.
IF YOU ARE TOLD TO TAKE THIS MEDICINE. TAKE IT ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE OFTEN. MORE WILL NOT HELP YOU AND MAY IN CREASE THE RISK OF SIDE EFFECTS. DO NOT TAKE THIS DRUG IF YOU KNOW YOU ARE ALLERGIC TO IODIDE. (SEE SIDE EFFECTS BELOW.)
INDICATIONS THYROID BLOCKING IN A RADIATION EMERGENCY ONLY.
DIRECTIONS FOR USE Use only as directed by State or local public health authorities in the event of a radiation emergency.
DOSE Tablets:
ADULTS AND CHILDREN 1 YEAR OF AGE OR OLDER-One (11 tablet once a day. Crush for small children.
BABIES UNDER I YEAR OF AGE:
One-half (1/2) tablet once a day. Crush first.
Take for 10 days unless directed otherwise by State or local public health authorities.
Store at controlled room temperature between 150 and 30°C (59° to 86°F). Keep container tightly closed and protect from light.
WARNING Potassium iodide should not be used by people allergic to iodide.
Keep out of the reach of children. In case of overdose or allergic reaction, contact a physician or the public health authority.
DESCRIPTION Each THYRO-BLOCK TABLET contains 130 mg of potassium iodide.
Other ingredients-magnesium stearate, microcrystalline cellulose, silica gel, sodium thiosulfate.
HOW POTASSIUM IODIDE WORKS Certain forms of iodine help your thyroid gland work right. Most people get the iodine they need from foods, like iodized salt or fish. The thyroid can "store" or hold only a certain amount of 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 bably not show itself for years. Children are most hkely to have thyroid damage.
If you take potassium iodide, it will fill up your thyroid gland.
This reduces the chance that harmful radioactive iodine will enter the thyroid gland.
WHO SHOULD NOT TAKE POTASSIUM IODIDE The only people who should not take potassium iodide are people who know they are allergic to iodide. You may take potassium iodide even if you are taking medicines for a thyroid problem (for example, a thyroid hormone or antithyroid drug). Pregnant and 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. More will not help you because the thyroid can "hold" on ly limited amounts of iodine. Larger doses will increase the risk of side effects. You will probably be told not to take the drug for more than 10 days.
SIDE EFFECTS Usually, side effects of potassium iodide happen when people take higher doses for a long time. You should be careful not to take more than the recommended dose or take it for longer than you are told. Side effects are unlikely because ofthe low dose and the short time you will be taking the drug.
Possible side effects include skin rashes, swelling of the salivary glands, and "iodism" (metallic taste, burning mouth and throat.
sore teeth and gums, symptoms of a head cold, and sometimes stomach upset and diarrhea).
A few people have an allergic reaction with more serious symp 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.
ing immediate medical attention Taking iodide may rarely cause overactivity of the thyroid gland. underactivity of the thyroid gland, or enlargement of the thyroid gland (goiter).
WHAT TO DO IF SIDE EFFECTS OCCUR 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 HOW SUPPLIED THYRO-BLOCK TABLETS (Potassium Iodide Tablets, USP}
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:
REVIEWED BY:
APPROVED BY:
EFFECTIVE DATE:
&ex SINATURDATE Q'Ar Av 0ViWI 1 13 fSIGNA72U/,/DATE V,.. ý -) -d I/u/
l DATE PROCEDURE USE IS REFERENCE I,/ 31oý_
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.
TITLE:
IP-1063 REV.
12 VEHICLE/EOUIPMENT RADIOLOGICAL CHECK AND DECONTAMINATION THIS PROCEDURE IS TSR THIS PROCEDURE IS NOT TSR WRITTEN BY:
REVIEWED BY:
APPROVED BY:
EFFECTIVE DATE:
SIGNATURE/DATE (d,,fc/o SIGN TURE/DATE LtL k,,
S MDATE PROCEDURE USE IS REFERENCE f
1
" ll" 1
9,ý 111310
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
5.1 IPEC Service Center Layout IK
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.
2.2 The Emergency Director (ED) is responsible for authorizing vehicles or equipment to leave the site with measurable contamination or without being radiologically monitored when otherwise required.
2.3 The Operations Support Center (OSC) Health Physics (HP) Team Leader is 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" Page 1 of 3 IP-1063
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 Page 2 of 3 IP-1063
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 depression where it will be contained and concentrated by the land contour.
C. Isolate and post the run off area, as necessary.
D. Using hoses hooked up to the nearest fire hydrant or utilizing a 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 Check" or EP-Form #17, "Equipment Contamination Check".
Return these forms to the RATL or HPTL.
4.6 IF it is necessary to have a vehicle or piece of equipment leave the 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 Page 3 of 3 IP-1063
VOLUME III IP-1063 Rev. 12 Page 1 of 1 ATTACHMENT 5.1 IPEC SERVICE CENTER LAYOUT 0
VR S
E W
E-4N --W N