ML041040009
| ML041040009 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/22/2004 |
| From: | Jamil D Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML041040009 (127) | |
Text
PO Power.
Duke D.M. JAMIL Vice President A Duke Energy Company Duke Power Catawba Nuclear Station 4800 Concord Rd. / CN01 VP York, SC 29745-9635 March 22, 2004 803 831 4251 803 831 3221 fax U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Corporation Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413 and 50-414 Emergency Plan Implementing Procedures Please find enclosed for NRC Staff use and review the following Emergency Plan Implementing Procedures:
HP/0/B/1000/006 Emergency Equipment Functional Check and Inventory (Rev. 056)
HP/O/B/1009/009 Guidelines for Accident and Emergency Response (Rev. 040)
HP/O/B/1009/026 On-Shift Offsite Dose Projections (Rev. 007)
SH/0/B/2005/001 Emergency Response Offsite Dose Projections (Rev. 003)
SH/0/B/2005/002 Protocol for the Field Monitoring Coordinator during Emergency Conditions (Rev. 003)
These revisions are being submitted in accordance with 10CFR 50.54(q) and do not decrease the effectiveness of the Emergency Plan Implementing Procedures or the Emergency Plan.
There are no new regulatory commitments in these documents. By copy of this letter, two copies of the above documents are being provided to the NRC, Region II.
If there are any questions, please call Tom Beadle at 803-831-4027.
Attachments 16 Y5 www. duke-energy. corn
U.S. Nuclear Regulatory Commission March 22, 2004 Page 2 xc (w/attachments):
L. A. Reyes U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 (w/o attachments):
S. E. Peters NRC Project Manager (CNS)
U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, DC 20555-0001 E. F. Guthrie Senior Resident Inspector (CNS)
U.S. Nuclear Regulatory Commission Catawba Nuclear Site
Page ] of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I PROCEDURE TITLE RP/0/A/5000/001 Classification of Emergency (Rev. 015)
RP/0/A/5000/002 Notification of Unusual Event (Rev. 037)
RP/0/A/5000/003 Alert (Rev. 040)
RP/0/A/5000/004 Site Area Emergency (Rev. 042)
RP/0/A/5000/005 General Emergency (Rev. 042)
RP/0/A/5000/06 Deleted RP/O/A/5000/006 A Notifications to States and Counties from the Control Room (Rev. 017)
RP/0/A/5000/006 B Notifications to States and Counties from the Technical Support Center (Rev. 017)
RP/0/A/5000/006 C Deleted RP/0/A/5000/007 Natural Disaster and Earthquake (Rev. 022)
RP/0/A/5000/08 Deleted RP/O/B/5000/008 Spill Response (Rev. 022)
RP/0/A/5000/009 Collision/Explosion (Rev. 008)
RP/O/A/5000/010 Conducting A Site Assembly or Preparing the Site for an Evacuation (Rev. 016)
RP/0/A/5000/11 Deleted RP/O/B/5000/12 Deleted RP/0/B/5000/013 NRC Notification Requirements (Rev. 029)
RP/0/B/5000/14 Deleted RP/0/A/5000/015 Core Damage Assessment (Rev. 005)
RP/OIB/5000/016 Deleted RP/0/B/5000/17 Deleted March 15, 2004
Page 2 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I PROCEDURE TITLE RP/0/A/5000/01 8 Emergency Worker Dose Extension (Rev. 001)
RP/0/B/5000/01 9 Deleted RP/0/A/5000/020 Technical Support Center (TSC) Activation Procedure (Rev. 018)
RP/O/A/5000/02 1 Deleted RP/0/B/5000/022 Evacuation Coordinator Procedure (Rev. 004)
RP/0/B/5000/023 Deleted RP/0/A/5000/024 OSC Activation Procedure (Rev. 013)
RP/0/B/5000/025 Recovery and Reentry Procedure (Rev. 003)
RP/01B/5000/026 Site Response to Security Events (Rev. 006)
RP/0/B/5000/028 Public Affairs Emergency Response Plan (Rev. 002)
March 15, 2004
Page 3 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME 11 PROCEDURE TITLE HP/0/B/1000/006 Emergency Equipment Functional Check and Inventory (Rev. 056)
HP/0/B/1 009/001 Radiation Protection Recovery Plan (Rev. 008)
HP/0/B/1009/003 Radiation Protection Response Following a Primary to Secondary Leak (Rev. 008)
HP/0/fB/1 009/004 Environmental Monitoring for Emergency Conditions Within the Ten-Mile Radius of CNS (Rev. 028)
HP/0/B/1009/005 Personnel/Vehicle Monitoring for Emergency Conditions (Rev. 016)
HP/O/B/1009/006 Alternative Method for Determining Dose Rate Within the Reactor Building (Rev. 008)
HP/lO/B/1009/007 In-Plant Particulate and Iodine Monitoring Under Accident Conditions (Rev. 019)
HP/0/B/1 009/008 Contamination Control of Injured Individuals (Rev. 015)
HP/0/B/13009/009 Guidelines for Accident and Emergency Response (Rev. 040)
HP/0/B/1009/014 Radiation Protection Actions Following an Uncontrolled Release of Radioactive Material (Rev. 008)
HP/0/B/1009/016 Deleted HP/0/B/1 009/017 Deleted HP/i/B/1009/017 Deleted HP/2/B!/1009/017 Deleted HP/0/B/1 009/018 Deleted HP/0/B/1009/019 Emergency Radio System Operation, Maintenance and Communication (Rev. 010)
HP/0/B/13009/024 Implementing Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 002)
March 15, 2004
Page 4 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE HP/0/B/I 009/025 Deleted HP/0/B/1 009/026 On-Shift Offsite Dose Projections (Rev. 007)
SH/013B/2005/001 Emergency Response Offsite Dose Projections (Rev. 003)
SH/0/1B/2005/002 Protocol for the Field Monitoring Coordinator During Emergency Conditions (Rev. 003)
SHIO/B/2005/003 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Rev. 000)
OP/0/A16200/02 1 Deleted SR/0/1B/2000/001 Standard Procedure for Public Affairs Response to the Emergency Operations Facility (Rev. 004)
SR/0/1B/2000/002 Standard Procedure for EOF Services (Rev. 003)
SR10/B/2000/003 Activation of the Emergency Operations Facility (Rev. 012)
SR0/B1/2000/004 Notification to States and Counties from the Emergency Operations Facility (Rev. 007)
March 15, 2004
(RO7-2)
Duke Power Company (I) ID No. IIPIOIB/1000/006 PROCEDURE PROCESS RECORD Rcvision No. 056 PREPARATION (2) Station Catawba Nuclear Station (3) Procedure Title Emergency Equir)ment Functional Check and Inventory (4) Prepared By Date (5) Requires NSD 228 Applicability Dete inatin? If Applicability Determination is required, attach NSD 228 documentation.
o Yes (New procedure or revision wi major changes) 1 No (Revision with minor changes) 0 No (To incorporate previously approved changes)
(6) Reviewed By G N U S (QR) Date iA8/oq Cross-Disciplinary Review By Ax (QR) NAG21 Date /
Reactivity Mgmt. Review By (QR) NAk4 Date Y Mgmt. Involvement Review By (Ops. Supt.) NA e1 Date 7U/§ (7) Additional Reviews ,= / A at Reviewed By Date Reviewed By A X[ Date 3 1f le (8) Temporary Approval (if necessary)
By (OSM/QR) Date By (QR) Date (4 Approved By_ ______Date 3
-Zo- '1 PERFORMANCE (Compare with controlcopy every 14 calendardayswhile work-is being performCed.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (I I) Date(s) Performed Work Order Number (WO#)
COMPLETION (12) Procedure Completion Verification:
o Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
o Yes 0 NA Required enclosures attached?
0 Yes 0 NA Data sheets attached, completed, dated, and signed?
o Yes 0 NA Charts, graphs, etc. attached, dated, identified, and marked?
o Yes 0 NA Procedure requirements met?
Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additionalpages, if necessary)
r Duke Power Company Procedure No.
Catawba Nuclear Station IIr/Om/looo/006 Revision No.
Emergency Equipment Functional Check and Inventory 056 Electronic Reference No.
Multiple Use CN005CPJ
HP/0/B/1 000/006 Page 2 of 10 Emergency Equipment Functional Check and Inventory Reference Use
- 1. Purpose To verify availability and readiness of Radiation Protection (RP) emergency response equipment.
- 2. References 2.1 HP/O/B/10031022 - Inservice Radiation Protection Instrument Source Check 2.2 HP/O/B/1005/008 - Radiological Respirators 2.3 HP/0/B/1009/019 - Emergency Radio System Operations, Maintenance and Communication 2.4 NSD 208 - Problem Investigation Process 2.5 NSD 702 - Records Management
- 3. Limits and Precautions None
H P/0/B/1 000/006 Page 3 of 10
- 4. Procedure 4.1 Emergency Kit Inventory Requirements NOTE:
- RP personnel using emergency kit items are responsible for completing a kit inventory and ensuring that items are replaced as necessary.
- RP personnel using off-site kit items are responsible for inventory and restocking as soon as practical after use; (e.g., Piedmont Medical Center medical response).
- RP personnel performing inventory of emergency kits may perform procedure steps in any sequence to successfully complete an inventory.
4.1.1 Perform an emergency kit inventory following use or if contents could have been compromised; (e.g., drills or Emergency Response Organization (ERO) activation):
- Replace used, mutilated or damaged procedure(s) or enclosure(s) with Control Copy(s).
- Ensure equipment is stored in operable condition; (e.g., survey meters and/or protective clothing is not returned to kit in a damaged condition).
- Verify battery operated equipment is turned off before placing item in storage.
Verify items against kit enclosure list of contents using applicable Enclosure 5.4 (Recovery Kit List of Contents) through 5.13 (Miscellaneous Kit List of Contents).
4.1.2 Return or replace equipment removed from emergency kit(s) within twenty-four hours following termination of an event.
- IF items can not be replaced or restocked in a kit, complete Enclosure 5.16 (Emergency Equipment Deviation Form) per section 4.5.
4.1.3 Document results using Enclosure 5.14 (Emergency Kit Inventory Record).
4.1.4 Replace kit tamper seal.
IiP/0/B/OOO/OO6 Page 4 of 10 NOTE: Emergency response kits with a tamper seal remaining intact between quarterly inspections provide a satisfactory substitute for a complete inventory of all kit contents.
4.2 Emergency Kit Quarterly Inventory Requirements 4.2.1 Perform quarterly inspections of emergency kits based on table in Enclosure 5.2 (Emergency Kit Inspection Record).
4.2.2 Perform quarterly inventory of designated emergency kits using applicable Enclosure 5.4 through 5.12 (Technical Support Center Kit List of Contents).
IF Miscellaneous Kit is required for fuel transfer event, transportation event or on-site (out of protected area) event, use Enclosure 5.13 (Miscellaneous Kit List of Contents) to assemble items for the kit.
4.2.3 Verify emergency kit procedures using Enclosure 5.3 (Emergency Kit Control Copy Procedure Record).
- Ensure current Control Copy(s) are in kits.
- Record procedure revision number and/or approval date on Enclosure 5.3.
- Record any additional information as needed on Enclosure 5.3.
4.2.4 Ensure all electronic dosimeters meet calibration requirements.
- Verify that all electronic dosimeters are in "autonomous mode".
- Replace any EDs which are NO' in "autonomous mode".
4.2.5 Ensure portable survey instruments are available and acceptable for use.
- Perform instrument source check in accordance with HP0/1B/1003/022 (Inservice Radiation Protection Instrument Source Check).
- Inspect instrument for physical damage which could affect operation.
- Verify instrument calibration sticker indicates instrument has been calibrated within past six months.
HP/0/B 10001006 Page 5 of 10 4.2.6 Ensure air samplers are available and acceptable for use.
- Inspect sampler for physical damage which could affect operation.
- Verify air sampler operates when plugged into an electrical outlet.
- Verify calibration sticker indicates sampler has been calibrated within past six months.
4.2.7 Ensure emergency kit batteries are acceptable for use.
- Verify battery tester needle indicates "good" when batteries are tested.
- Inspect batteries for acceptable physical condition; (e.g., no dents or corrosion).
4.2.8 Ensure battery-operated equipment has no corrosion.
4.2.9 Ensure bulbs in battery-operated equipment illuminate properly.
4.2.10 Ensure Silver Zeolite or equivalent type cartridge packet is sealed AND undamaged.
Remove damaged packets.
- Notify RP Staff Scientist.
4.2.11 Ensure protective clothing has not exceeded recommended limits of Enclosure 5.15 (Recommended Shelf-life for Protective Clothing).
NOTE,: Potassium Iodide (KI) tablets are normally shipped in bottles with a label having a factory lot number and expiration date.
4.2.12 Ensure the following for supply of KI tablets:
IF KI tablets are within three months of expiration date, THEN order replacement tablets.
- Maintain a minimum of 1000 bottles (14 tablets per bottle) of KI onsite.
- Store in a low humidity location and avoid direct exposure to liquids.
- Store in a location protected from exposure to light.
HP/0/B 1000/006 Page 6 of 10 4.2.13 Upon receipt of a shipment of new KI tablets:
A. Open boxes to inspect contents.
B. Exchange existing supplies of KI tablets to ensure adequate supply of new KI tablets.
C. Discard KI tablets after they have exceeded the expiration date.
Information Use NOTE: Duke General Office TLD Laboratory provides Thermoluminescent Dosimeters (TLDs) to Catawba Dosimetry Records Control (DRC) at least quarterly. Electronic dosimetry is provided by Duke's EnRad Laboratory personnel.
4.2.14 Replace TLDs in kits, including control TLDs issued by DRC.
4.2.15 Return TLDs removed from kits to DRC.
4.2.16 Replace electronic dosimeters (EDs) as required by calibration due dates.
4.2.17 Return EDs removed from kits to DRC.
NOTE: ES1P-2 check sources exceeding manufacturer expiration date are analyzed using count room Multi-Channel Analyzer (MCA) equipment to verify (Ba-133) source decay.
4.2.18 11F inspection of emergency kit instrument sources show any damage, T'111EN notify RP Staff Scientist for further investigation and/or analysis.
Reference Use NOTE:
- Respiratory equipment is inspected and maintained by RIC group using IHP/0/B/1005/008 (Radiological Respirators).
- Replacement or alteration of emergency kit respiratory equipment is per direction of Emergency Response RP Staff Scientist and RIC.
4.3 Einmergency Kit Respirator Inspection 4.3.1 Ensure minimum of twenty-two particulate masks are available in the Emergency Kit Storage Room.
H P/0/B/1 000/006 Page 7 of 10 4.3.2 Verify respiratory equipment in emergency kits is acceptable for use.
- Ensure no physical damage or deformation of respiratory masks.
- Ensure minimum of twenty-two GMRI canisters or equivalent, NOT exceeding expiration date, are available in designated emergency kits.
4.3.3 IF expiration date on GMRI canisters is within three months of date, THEN order replacement canisters.
4.3.4 Ensure minimum of ten particulate masks and GMRI canisters or equivalent NOT exceeding expiration date, are available in Operations Support Center Kit.
Information Use 4.4 Emergency Kit Deviations NOTE: An emergency kit deviation is considered to be equipment that does not meet inspection criteria, and/or items that cannot be restocked within twenty four hours, and/or any condition that degrades equipment reliability or compromises operable condition of a kit or its contents.
4.4.1 Document emergency kit deviations on Enclosure 5.16.
4.4.2 Re-inventory emergency kits found with items missing and/or seals removed to ensure that all kit contents are restored to operable requirements.
4.4.3 Usc Enclosure 5.16 to document corrective action(s) that remedy a deviation.
4.4.4 Initiate a PIP to document and trend kit deviations, per Reference 2.4 (NSD 208-Problem Investigation Process).
4.4.5 Retain completed Enclosure(s) 5.16 in Emergency Equipment Inventory Logbook.
IHP/0/B/ 1000/006 Page 8 of 10 Reference Use 4.5 Field Monitor Team (FMT) Quarterly Radio Check NOTE: Emergency Planning Group performs quarterly EOF/TSC base radio checks. .... I 4.5.1 Perform quarterly check of Field Monitor Team (FMT) radios and Technical Support Center (TSC) base station radio in accordance with HP/0/B/1009/019 (Emergency Radio System Operations, Maintenance and Communication).
NOTE:
- A radio identifier call sign for high band radio frequency is automatically transmitted when keying a high band FMT radio.
- Onsite portable radio-to-radio check may be used to verify operability after repair of radio equipment (e.g., prior to returning FMT radios into service).
4.5.2 Check FMT sample van radios and portable radios at a distance approximately five to ten miles from the plant.
4.5.3 Verify each FMT radio transmits and receives a message.
- Communicate from TSC base station to each portable radio.
- Communicate from each portable radio to TSC base station.
4.5.4 Rcmove inoperable radios from service.
- IF replacement and/or repair of FMT radios is necessary, contact Catawba communications Single Point Of Contact (SPOC).
4.5.5 Record radio identifier engraved on hand-held portable radios in first column of Enclosure 5.17 (Quarterly Field Team / Radio Cellular Phone Check Record).
4.5.6 Record results of radio check in comments section of Enclosure 5.17 (Quarterly Field Team Radio / Cellular Phone Check Record).
IP/0//BI1000/006 Page 9 of 10 4.6 Quarterly Operability Check of FMT Cellular Telephone 4.6.1 Verify telephones are acceptable for use by initiating a phone call.
- Test each telephone by receiving a call.
4.6.2 Charge cellular telephone batteries.
- Plug battery into the charger for at least twelve hours.
- Remove battery after charge.
- Store batteries and portable cellular telephones in Emergency Kit Room.
4.6.3 Remove inoperable cellular phones from service. -
- IF replacement or repair of FMT cellular telephone equipment is necessary, contact Catawba Emergency Planning personnel.
4.6.4 Record results of cellular phone check in comments section of Enclosure 5.17.
4.7 Retention Requirements
- Retain Enclosure 5.14 with each kit for at least one year.
- Retain Enclosures 5.2, 5.3, 5.14, 5.16, and 5.17 in Emergency Equipment Inventory Logbook for at least one year.
- Forward emergency kit inspection records to Document Management for microfilming in accordance with Nuclear Policy Manual-Nuclear Site Directive 702 Records Management.
- 5. Enclosures 5.1 Emergency Kit Storage Location 5.2 Emergency Kit Quarterly Inspection Record 5.3 Emergency Kit Control Copy Procedure Record 5.4 Recovery Kit List of Contents 5.5 Emergency Sample Van Survey Kit List of Contents (I'll' C-02-00495) 5.6 Emergency Survey Teams Vehicle Survey Kit List of Contents
EiPrOrB/1000/006 Page 10 of 10 5.7 Personnel Survey Kit List of Contents (Security PAP Area) 5.8 Personnel Survey Kit List of Contents (Evacuation Facility) 5.9 Emergency Medical Kit List of Contents (First Aid Room) 5.10 Emergency Medical Kit List of Contents Piedmont Medical Center (PMC) 5.11 Operations Support Center Kit List of Contents (PIP C-02-0 1526) 5.12 Technical Support Center Kit List of Contents 5.13 Miscellaneous Kit List of Contents 5.14 Emergency Kit Inventory Record 5.15 Recommended Shelf-life for Protective Clothing 5.16 Emergency Equipment Deviation Form 5.17 Quarterly Field Team Radio / Cellular Phone Check Record
Enclosure 5.1 HP/O/B/1O000006 Emergency Kit Storage Location Page 1 of 1 Information Use NOTE: 1. Emergency Sample Van kits containing battery operated equipment are stored in the Emergency Kit Room in Administration Building Room 148.
- 2. Recovery Kits for Newport (Evacuation Site) and Plant Allen (Evacuation Site) are stored in the Emergency Kit Room in Administration Building Room 148.
- 3. IF required, assemble and inventory Miscellaneous Kit on an as needed basis.
Tvpc Storage Location Emergency Sample Van & kit room trunk (NOTE 1.) (2 kits): ................ Admin. assigned parking space Emergency Survey Team Vehicle Survey Kit (2 kits): ..................................... Admin. Building Rm. 148 Recovery Kit Evacuation Facility (Newport) (NOTE 2.) (1 kit): .......... ........... Admin. Building Rm. 148 Recovery Kit Evacuation Facility (Plant Allen) (NOTE 2.) (I kit): ...................Admin. Building Rm. 148 Recovery Kit Security Pap Area (I kit): ............................. ................... Admin. Building Rm. 148 Miscellaneous Kit (NOTE 3.) (I kit): ....................... ......................... Admin. Building Rm. 148 Personnel Survey Kit Security Pap Area (I kit): ............................................... Admin. Building Rm. 148 Personnel Survey Kit Evacuation Facilities Alpha (I kit): ............................................... Newport Personnel Survey Kit Evacuation Facilities Bravo (I kit): ............................................... Plant Allen Emergency Medical Kit (PMC) (I kit): ................................................ Piedmont Medical Center Emergency Medical Kit (CNS) (I kit): .................. .................. Auxiliary Building First Aid Room Operations Support Center Kit (OSC) (I kit): ................................................ Operations Support Center Technical Support Center Kit (TSC) (I kit): ................................................ Technical Support Center
( Encd :5.2 HP/O/B/lOd A6 Emergency Kit Quarterly Inspection Record Page 1 of 1 Information Use IstQuarter 2nd Quarter l ard arter 4th Quarter LOCATION Complete Kit Date of Complcte Kit 1 Date of Complete Kit Date of Complete Kit Date of Inventory Yes/No l Inventory Inventory YesN nett Inventory Yes/No Inventory Inventory Yes/No Inventory Sample Van I & (Kit Rm. Trunk)
ESI'-2 Ba 133 MCA check Ist. Qtr. Yes Sample Van 2 & (Kit Rm. Trunk)
ESP-2 Ba 133 MCA check Ist. Qtr. Yes Emergency Vehicle Survey Team Kit - Alpha (Kit Rm.) Yes Emergency Vehicle Survey Team Kit - Bravo (Kit Ri.) Yes Recovery Kit - Newport (Kit Rim) Yes Recovery Kit - Plant Allen (Kit 1Itm.) Yes_
Recovery Kit - Security PAP Area (Kit Rm.) Yes Personnel Survey Kit -
(l'ant Allen) Yes Personnel Survey Kit e Yes (Newport )
Personnel Survey Kit -
Securitv PAP Area (Kit Rin.) Yes Emergency Medical Kit -
(CNS First Aid Room) Yes Emergency Medical Kit -
Piedmont Medical Center (PMNIC) Yes Operation Support Center Kit - (OSC) _ Yes Technical Suppon Center Kit - (TSC) Yes Miscellaneous Kit - Yes (Kit Rut. )
SIGNATURE FORINVENTORY SIGNATURE: SIGNATURE: SIGNATURE: SIGNATURE:
PERFORMED BY:
TIltS coPY HAS BEEN COMPARED WITII TItE TItIS COPY HAS BEENCOMPARED WITH THE THIS COPY HAS BEEN COMPARED wITH THE THIS COPY HASBEEN COMPARED WITH THE INITIAL, DATE AND TIME REQUIRED CONTROL COPYAND IS VERIFIED CORRECT. CONTROLCOPY AND IS VERIFIED CORRECT. CONTROL COPY AND IS VERIFtED CORRECT. CONTROL COPY AND IS VERIFIED CORRECT.
DATE TIME INITIAL DATE - TIME l_INTIAL DATE TIME - INmAL DATE TM E_
FORCONTROL COPYCOMPARISONS INITIAL
( Encl( .5.3 HPIO/B/I10( ,6 Emergency Kit Control Copy Procedure Record Page 1 of 1 Information Use SAMPLE VANS 11PIO/B/1000/006 IIP/0//13009/004 SI-1O/13=05/003 T HP/0/B/1009/019 I HP/01811003/072 I
Sample Van I j .
Sample Van 2 S NSURVEYTKIT PIOID/I000/006 IIP/E/BI_009j004 SH/o/B/2005/003 ' HP/OB/1009/019
_. I Alpha Vehicle Bravo Vehicle__
RECOVERY KITS HP/O/B/ 1000/006 SH/0/B/2005/003 i 1 I I
Security PAP PESNE SURVE KI Newport MEDICAL KITS HP/O/B/I 000/006 HP/O/D/ 1009/008 Stl/OlB/2001/003 First Aid Room CNS ___ _ _ _ _ _ _ _ _ _ _
Piedmont Medical PMC SUPPORT KITS HP/OD/BI000/006 SH/01/B/2005/003 HPI/B/I 009/019 SHIOIB/2001/003 I
TSC l OSC Nlisccilaneous Kit THIS COPY HAS BEEN COMPARED WITH COMMENTS:
THE CONTROL COPY AND IS VERIFIED CORRECT.
INITIAL .. DATE ., TIME _
( Encd 5.4 HP/O/B/lOd. .j6 Recovery Kit List of Contents Page I of I Continuous Use MINIMUM MINIMUM ITEM AMOUNT ITEM AMOUNT List of Contents.1 Pens2....................................................2 Eberline E-520 with/HP-270 Probe ........................................... ......... 1 Grease Pencil and Refills . ...................................................... I Cs-137 Exempt Source .............. 1a......................................
I Instrument/Smear Survey Sheets ......................................... ............. 10 Electronic dosimeters ............. 6:.......................................
6 KI Tablets:
Dosecards ..................................................... 10 Newport ........................... 275 bottles TLD Badges ......... 6 6...........................................
Security PAP .......................... 150 bottles Boundary Ribbon or Rope (50 yd. Roll) ..... 1...............................................
I Allen Station .......................... 275 bottles Masking Tape (roll) ..................................................... 1 KI Tablet Distribution Data Sheet ......................... : 100 Rain Suits (set) .......... 2 Smears (box) ........................................................
2.......................................... I Full Face Respirator with GMRI canister (or equivalent) (Note 1) .............. NuCon Nu.n.SSmears ears.............................2
..................................................... 10 Cotton Coveralls.2 Flashlig.....................................................2.I Hoods.2 Batteries.(size.D)6....................................................2 Gloves: Cotton (pair) ........................ 2 Scissors ........................................................ 1.....................
1 Rubber (pair) ...................................... 2 Medication Envelopes:
Shoe Covers: Disposable (pair) . .................................................... 2 Newport ............................ ............. 100 Rubber (pair) . .................................................... 2 Security PAP ................. ................ 60 Poly Bags (various sizes) ............... ..................................... 6 Allen ............................................. 100 Caution Signs with Inserts ..................................................... 2 Emergency Response Organization Directory (Note 2) ................................ 1 Legal Pad ...................................................... Road Block Passes (Note 2) ....................... ............................... 100 Radioactive Material Tags ................. .................................... 5 Emergency Planning Zone Maps (Note 2) .................................................. 3 HP/0B/1000/006 ....................................................... 1 SH/0/B/2005/003 ............................................... 1 I NOTE: 1. Respiratory equipment is stored in Emergency Kit Room and GMRI canisters are stored in kits.
- 2. Items for Recovery Kits used for Plant Allen and Newport.
( Encd ; 5.5 HP/O/B//10d; A6 Emergency Sample Van Survey Kit List of Contents Page 1 of 2 Continuous Use MINIMUM MINIMUM ITEM AMOUNT ITEM AMOUNT List of Contents .......... 1...........................................
I NuCon Smears ....................................................... 10 Rain Suits (sets) .................................................... 2 Instrument/Smear Survey Sheets ...................................... .................. 10 Cotton Coveralls .................................................... 4 Map of Ten Mile Zone Sectors ........................................................ 1 Disposable Sacksuits ............ 4..........................................
4 LegalPad ........................................................ 1 Hoods .. Pen .4 .. 2 Gloves: Cotton (pair) ...................... ............................... 8 Permanent Marker ........................................................ 1 Rubber (pair) ..................................................... 8 Dosecards ....................................................... 10 Shoe Covers: Disposable (pair) .................................................... 4 Hand Spade ............ 1 Rubber (pair) .......................... .......................... 4 Grease Pencil and Refills ......................................................... 1 Sandwich Bags (box) ...................................................... I Scissors ........................................................ 1 Poly Bags (various sizes) ............... ...................................... 6 Field Monitoring Data Sheet ........................... .............................. 4 Masking Tape (roll) ..................................................... 1.K Tablet Distribution Data Sheet ......................................................... 1 Tweezers........................................................................................................ 1 Radio Operator ............................................................................... I Limnological Sampler .................................................... I CPD1 Key ......................................................... 1 Cubitainers .................................................... 4 Road Block Passes ......................................................... 4 1 Liter Wide Mouth Bottles .................. ................................... 4 Reflective Safety Vests ........................................................ 2 Stopwatch...................................................................................................... I Funnel .................................................... 1I Silver Zeolite Filter Cartridges ........................ ............................ 10 Tygon Tubing ........................................................ - 4 ft Particulate Filters .................................................... 10 Fuses (Misc. Sizes) ........................................................ box Filter Cartridges Labels & Bags .......................... .......................... 20 Extension Cord ......................................................... 1 Smears (box) .. Shear.....................................................lI
( Encl( ; 5.5 HP/O/B/10 6 Emergency Sample Van Survey Kit List of Contents Page 2 of 2 Continuous Use MINIMUM MINIMUM ITEM AMOUNT ITEM AMOUNT Eberline E-520 with/HP-270 Probe ................................................. 1 Battery Operated Lantern (with 6 volt battery) .............. ..................... 1 Eberline E-140N with/HP-210 Tungsten Probe (or equivalent) ........... 1 Batteries (C size) .................................................. 12 Eberline RO-20 ................................................. 1 Batteries (D size) ......... 66...................
Cs-137 Exempt Source ................................................. 1 Flashlight ................................................... 1 Eberline ESP-2 with/Nal detector. ................................................ I Calculator ................................................... 1 Ba-133 exempt source ................. ................................ I Sample Van Keys ................................................... I1 Medication Envelopes (or small sample bottles) ................................. 2 Portable radio and/or cellular telephone (Note 2)................................ 1 KI Tablets (bottle) ................................................. 2 HP/0/B/1000/006 ................................................... 1 Electronic dosimeters ................................................. 4 HP/0/B/1003/072 ................................................... 1 TLD Badge ...... 66..........................................
HP/O/B/1009/004 ................................................... 1 Full Face Respirator with GMRI Canister (or equivalent (NOTE ) 1). 4 SH1/0/B/2005/003 .................................................. 1 I NOTE: 1. Respiratory equipment is stored in Emergency Kit Room and GMRI canisters are stored in vans.
- 2. Portable radios and cellular telephones with antennas are stored in Emergency Kit Room.
( Encld\ 5.6 HP/O/B/10d 6 Emergency Survey Teams Vehicle Survey Kit List of Contents Page I of I Continuous Use MINIMUM MINIMUM ITEM AMOUNT ITEM AMOUNT List of Contents ................................................. 1Shoe Covers: Disposable (pair) ................................................. 2 Eberline E-140N with/HP-210 Tungsten Probe (or equivalent) .......... I Rubber (pair) .............. 2 Eberline E-520 with/HP-270 Probe ............................................... I KI Ta blets (bottle) .2 Eberline RO-20 ................................................ I KI Tablet Distribution Data Sheet .I Cs-137 Exempt Source ............................................... I Medication Envelopes(or small sample bottles). 2 Field Monitoring Data Sheet ............................................... 4 Batteries (D size) .6 Flashlight ................................................ 1 Batteries (C size) .6 Electronic dosimeters ................................................ 2 Map of Ten Mile Zone Sectors .I TLD's.6 g1...............................................6LegalPa d Dosecards............................................................................................. 10 Pens..................................................2 Full Face Respirator with GMRI Canister (or equivalent ) (NOTE 1) 2 Portable Radio and/or cellular telephone (Note 2) .1 Cotton Coveralls ............................................... 2 R adio Operators M anual .I Disposable Sacksuits ............................................... 2 R oad Block Passes .2 Hoods ............................................... 2 Tape (roll) .
Gloves: Cotton (pair)........................................................... 4 HP/0/B/1000/006 .................................................. 1 Rubber (pair) .4 HP/0/B/1009/004 .................................................. I HP/0/B/1009/019 .................................................. 1 SH/
1 /B/2005/003 ........................................................... ...... I I NOTE: 1. Respiratory equipment is stored in Emergency Kit Room and GMRI canisters are stored in kits.
- 2. Portable radios and cellular telephones with antennas are stored in Emergency Kit Room.
( Encld . 5.7 HP/O/B/lOd. j6 Personnel Survey Kit List of Contents (Security PAP Area) Page 1 of 1 Continuous Use MINIMUM l MINIMUM ITEM AMOUNT I ITEM AMOUNT List of Contents.1 Roll of Radioactive Material Tape1 ....................................................... 1 Eberline E-140N with/HP-210 Tungsten Probe (or equivalent) ........ ........... 2 Step Off Pads ......................................................... 5 Cs-137 Exempt Source ..................................................... 1 Poly Bags (various sizes) ......................................................... 6 Radio Operator Manual ..................................................... I Smears (box) ......................................................... 1I Electronic dosimeters ..................................................... 2 NuCon Smears ........................................................ 10 Dosecards ;.................................................... 10 Instrument/Smear Survey Sheets ........................................................ 10 TLDs .................................................... 2 Pens.2 KI Tablets (bottle) .................................................... 2 Grease Pencil and Refills ............. I1....................
KI Tablet l Distribution Data Sheet ................................................... 1 Legal Pad ....... 1.I Medication Envelopes (or small sample bottles) ................................ 2 Scissors ......................................................... 1 Rain Suits.2 Deon.Supplies.1....................................................2 Cotton Coveralls .................................................... ........................................ 2 Shop Cloths Hoods .................................................... ....................................................... 2
- Mild, Liquid Soap Gloves: Cotton (pair) .................................................... ................... 2 Scrub Brush Rubber (pair) .................................................... ................ 2
- Cotton Swabs Shoe Covers: Disposable (pair) .................................................... .......... 2
- Fingernail Clippers Rubber (pair) .................. ................................... 2 Boundary Ribbon or Rope (50 yd. Roll) ..................................................... I Batteries (size D) ....................................................... 6 Caution Signs with Inserts .................................................... 4 Full Face Respirator with GMRI (or equivalent (see )Note) ........................ 2 Masking Tape (roll) ........ II.............................................
HP/0B/1000/006 ........................................................ 1I Radioactive Material Tags ............ 55.1.........................................
HP /B/1009/005 ........................................................ 1 SH10/B/2001/003 ........................................................ 1 SH/0/B/2005/003 ........................................................ 1 I NOTE: Respiratory equipment is stored in Emergency Kit Room and GMRI canisters are stored in kits.
( Encl< 5.8 HP/O/B/10d0 Personnel Survey Kit List of Contents (Evacuation Facility) Page I of I Continuous Use MINIMUM MINIMUM ITEM AMOUNT ITEM AMOUNT List of Contents ............................................... I Radioactive Material Tags .................. ................................... 5 Eberline E-140N with/HP-210 Tungsten Probe (or equivalent) ........ 2 Roll of Radioactive Material Tape .................................................... 1 Cs-137 Exempt Source ................................................ I Flashlight .................................................... I Electronic dosimeters ................................................ 4 Batteries (size D) ..................................................... 6 Dosecards ............................................... 10 Pens2 ................................................... 2 TLD's ..... 4lGrease 4..........................................
Pencil and Rfills . ................................................... 1 KI Tablets (bottle) ......... 2LegalPad 2.......................................
..................................................... 1 KI Tablet Distribution Data Sheet ............................................... I Decon Supplies ............ :.1 Medication Envelopes (or small sample bottles) ................................ 2
- Shop Cloths Disposable Sacksuits ............................................... 10
- Mild, Liquid Soap Gloves: Cotton (pair) . ............................................... 4
- Scrub Brush Rubber (pair) . ............................................... 4
- Cotton Swabs Shoe Covers: Disposable (pair) ................................................ 4
- Fingernail Clippers Rubber (pair) ............................................... 4 Scissors .I Boundary Ribbon or Rope (50 yd. roll) ............................................. 1 Instrument/Smear ns Survey Sheets .10 Caution Signs with Inserts ............................................... 4 Evacuation Personnel Dose Record .50 Step Off Pads ............................................... 5 C atawba Nuclear Station Telephone Directory .1 Masking Tape (roll) ............................................... I HP/O/B/1000/006 .I Poly Bags (various sizes) ............................................... 6 HP/O/B/1009/005 .1 Smears (box).1 ISHI O/B/2001/003 1...................
SH/IOB/2005/003 ............. .1 I
( Enclo( 5.9 HP/O/B/1 00( i Emergency Medical Kit List of Contents (First Aid Room) Page I of I Continuous Use MINIMUM MINIMIUM ITEM AMOUNT ITEM AMOUNT List of Contents ................................................ 1 Electronic dosimeters ..................................................... 5 Eberline E-140N with/HP-210 Tungsten Probe (or equivalent) .......... Flashlight..1..................................................
Flshlgh..............................I I Cs-137 Exempt Source ............................................... I Caution Signs with Inserts ..................................................... 3 Poly Bags (various sizes) ............ ................................... 6 Radioactive Material Tags . .................................................... 5 Smears (box) ...... I Scissors ....................................................
1........................................ 8 NuCon Smcars ............................................... 10 TLD's .................................................... 3 Rain Suits ...... 22........................................
Dose Cards .................................................... 10 Disposable Sacksuits ............................................... 2 Step Off Pads . 22...........
Hoods ..... 22.........................................
Decon Supplies ................................................... 1 Gloves: Cotton (pair) ........................................................... 2
- Shop Cloths Rubber (pair) .............................................. ........... 2
- Mild, Liquid Soap Shoe Covers: Disposable (pair) .............................................. ..... 2
- Scrub Brush Rubber (pair) .............................................. ........... 2
- Cotton Swabs Tape, Radioactive Material .............................................. .................. I
- Fingernail Clippers Tape, Masking 2" (roll)....................................................................... 1 HP//B1000/006.................................................1.. 1 Tape, Duct 2" (roll) . H.P//B/1009/008. .1 Instrument/Smear Survey Sheets.10 SH/e/B/2001/003 ............................................... 10.............. 1 I Pens ............................................... 2 Legal Pad .............................................. I Batteries (size D ) 6.....................................................................
( Enclo( 5.10 HP/O/B/100( 5 Emergency Meidical Kit List of Contents Piedmont Medical Center (PMIC) Page I of 1 Continuous Use MINIMUM MINIMUM ITEM AMOUNT ITEM AMOUNT List of Contents ...................................................... 1 HP/OIB/1000/006 .................................................... 1I Eberline E-520 with/HP-270 Probe . .................................................... I HP/0/B/1009/008 ..................................................... 1 Eberline E-140N with/HP-210 Tungsten Probe (or equivalent) ......... 1..........
SH/0/B/2001/003 .................................................... 1I Cs-137 Exempt Source ..................................................... I Poly Bags (various sizes) .................................................... 12 Smears (box) .................................................... I NuCon Smears. 10 (Items listed below are located in outside storage container)
Tape, Radioactive Material .......................... I1..........................
Stanchions ..................................................................................................... 4 Tape, Masking 2" (roll).................................................................................. 2 Trash Receptacle........................................................................................... 2 Tape, Duct 2" (roll)........................................................................................ 2 Step Off Pads ................................................................................................ 5 Instrument/Smear Survey Sheets .................................................... 10 Caution Signs with Inserts ............................................................................ 5 TLD's .................................................... 10 Roll of Rad Rope .......................................................................................... 1 Electronic dosimeters .................................................... 10 Floor Covering in trunk ................................................................................ I Dosecards...................................................................................................... 20 Scissors.......................................................................................................... 2 Radioactive Material Tags .......................... .......................... 20 Disposable Sacksuits ..................................................... 5 Disposable Shoe Covers (pairs) .................................................... 10 Cubitainers ..................................................... 4 Fingernail Clippers ..................................................... I Personnel Decontamination Forms (SH/0/B/2001/003) ............ ................... 5 Batteries (size D) .................................................... 6 Grease Pencil and refills ..................................................... I Gloves: (latex)................................................................................................ 20
( Enclo( 5.11 HP/O/B/1 0 I Operations Support Center Kit List of Contents Page 1 of 1 Continuous Use MINIMUMI MINIMUMI ITEM AMOUNT ITEM AMOUNT List of Contents ................................................................................. 1 Full Face Respirators with GMRI Canister (or equivalent) ............ 10 Eberline E-520 with/HP-270 Probc .................................................. 1 KI Tablet Distribution Data Sheets ................................................ 10 Eberline EI4ON with/HP-210 Tungsten Probe (or equivalent). Particulate Filters & Filter Cartridge Labels .................................... 30 1
Cs-137 Exem pt Source...................................................................... Silver Zeolite Filter Cartridges ......................................................... 30 Radeco H809V Air Sam pler ............................................................. 3 Poly Bags (various sizes) ................................................................. 12 Rain Suits .......................................................................................... 5 Decon Supplies ................................................................................. I Cotton Coveralls ............ 10
- Shop Cloths Hoods ... . .. 10
- Mild, Liquid Soap Gloves: Cotton (pair) ...................................................... 20
- Scrub Brush Rubber (pair) ........................................................ 20
- Cotton Swabs Shoe Covers: Disposable (pair) ................................................. 20
- Fingernail Clippers Rubber (pair) ........................................................ 20 Gym Shorts M isc. Sizes .................................................................... 10 Instrum ent/Sm ear Survey Sheets ...................................................... 10 M odesty Tops M isc. Sizes ................................................................ 10 Pens (box) ......................................................................................... I Flashlights ......................................................................................... 10 Grease Pencil and Refills ................................................................ 1 Large Lantern (with 6 volt battery) ................................................... 4 Extension Cords ............................................................................... 3 Batteries (size D) .............................................................................. 24 Stopwatch ......................................................................................... 2 CNS Site Map .................................................................................. 1 Electric Shaver ................................................................................. 1 M asking Tape (roll) .......................................................................... 2 Beard Trim m er ................................................................................. I Dosecards .......................................................................................... 100 Sm ears (box)..................................................................................... 1 Medication Envelopes (or small sample bottles) .............................. 10 Step Off Pads ................................................................................... 5 K! Tablets (bottle) ............................................................................ 20 OSC Dose Records Form s ................................................................ 125 HP/0/B/1000/006 .............................................................................. l SWO 0/B/2 005/003 .................................... .............. v.v........... I HP/0/B/1009/019 .............................................................................. 1 SH/0/B/2001/003 ............
( Enclos 5.12 HP/O/B/100( 5 Technical Support Center Kit List of Contents Page I of I Continuous Use MINIMUM MINIMUM ITEM AMOUNT ITEM AMOUNT List of Contents ............ I Pen .................................................... 2 2...................
Eberline E-520 with/HP-270 Probe ............................................... 1 Legal Pad .................................................... 1 Eberline E-1405N with/HP-210 Tungsten Probe (or equivalent) 1.......
Grease Pencil and Refills . .................................................. 1 Cs-137 Exempt Source ............................................... 1 Flashlights .................................................... 6 Radeco H809V Air Sampler.. ............................................... I Batteries (size D) .................................................... 12 Extension Cord .......... 1.....................................
Small Sample Bottles or Medication Envelopes ................... .............. 10 Electronic dosimeters ............................................... 50 D Supplies econ ..................................................... 1 Dosecards.......................................................................................... 150
- Shop Cloths Silver Zeolite Filter Cartridges ..... 10....................................................
- Mild, Liquid Soap Particulate Filters.............................................................................. 10
- Scrub Brush Filter Cartridge Labels ............................................... ....................... 10
- Cotton Swabs KI Tablets (bottle) .............................................. 25..............................
- Fingernail Clippers KI Tablet Distribution Data Sheet ............................................... 10 Vinyl or latex type gloves ............................. ....................... 10 Boundary Ribbon or Rope (50 yd. roll) ............................................ 1 Disposable Shoe Covers .................... ............................... 10 Caution Signs with Inserts ................................................ 3 Disposable Sacksuits ................. 5....................
5 Roll of Rad Tape ............ 2/...................................
2 Instrument/Smear Survey Sheets .................................................... 10 Smears (box) ............................................... 1 HP/O/B/1000/006 ................................................... 1I Poly Bags (various sizes) ................................................ 6 SH/0/B/2005/003 ..................................................... 1 I Masking Tape (roll) .................................................. I HP /B/1009019 .................................................... I StepOff Pads.5SHIO/B/2001/003 .1
( Enclo( 5.13 HP/O/B/10,. ,6 Mise'llaneous Kit List of Contents Page 1 of 1 Continuous Use
- TIllS KIT IS ASSEMBLED ON AS NEEDE.D BASIS. KIT ITIEMIS ARE LOCATED IN EMERGENCY EQUIPMENT STORAGE ROOM%(ADMIN. BUILDING Room 148)
MINIMNENUM MINIMUM ITEMI AMOUNT ITEM AMOUNT List of Contents ....................................................... .50 1 yd. Roll of Barricade Tape (Magenta & Yellow) ...................................... .......... 4 Eberline E-140N with/HP-210 Tungsten Probe (or equivalent) ............................... I Step Off Pads ... 5 Eberline E-520 witlI-270 Probe ........................................................ I Poly Bags (various sizes) ... 6 Cs-137 Exempt Source ........................................................ IHand Gardening Spade ... I Radeco H809V Air Sampler ........................................................ I Wid Mouthe Samp Bottles le ... 4 Full Face Respirators with GMRI Canister (or equivalent) (Note 1)...................... 2 Smears (box)....................................I Rain Suit.2 Kiwip...(box).2........................................................2 Cotton Coveralls.5NuCon Smears...............................................uCon Smears Disposable Sacksuits ........................................................ 5 of CopyNAC-I Drawings (prints) .I Hoods ......................................................... 5 Copy of Loading and Unloading Instructions.
Gloves: Cotton (pair) .5 Duct Tape (roll) ............................................................ 2 Surgeons gloves (vinyl or latex type) .10 Tape, Masking 1" ............................................................
Rubber (pair) .5 Tape, Masking 2"............................................................ I Shoe Covers: Disposable (pair) .5 Contact Pyrometer with Probe ........................................................... 2 Rubber (pair) .5 Safety Glasses ............................................................ 5 Hard Hats.2 Binoculars.........................................................I Silver Zeolite Cartridges ............ 10.ToolKKit.............................................I Particulate Filters.10 Batteries.(size.D)...6...............................................Bti(e Bags and Labels for filter/cartridges ....................................................... 10 Batteries (size C)............... .. 6 KI Tablets (bottle) ....................................................... 30 Flashlights ...
Plastic Sample Bottles or Medication Envelopes .................................................... 10 Steno Pad ............... I KI Tablet Distribution Data Sheet ...................... .................................. I Mechanical Lead Pencil and refills .......... . 2 TLD's.5Grease Pencils.........................................................I Eletronic dosimeters ......................................................... 5All Purpose Markerer ............... .
Dose Cards ... ,Scotch
,10 Tape Roll and Dispenser...
Weather-Proof Caution Signs with Inserts ....................................................... 4 Quarers4........4 Radioactive Waste Signs (4" x 6") ....................................................... 10 Instrument/Smear Survey Sheets ..... . . . 10 Caution: Radiation/Radioactive Material Tags ....................................................... 10HP/0//1000/006 ............. . ................. 1 S H0/1/2005/003 ........................................................................ 1 I NOTE: Respiratory equipment is stored in Emergency Kit Room and GMRI canisters are stored in kits.
( Enclo( 5.14 HP/O/B/1O(d 6 Emergency Kit Inventory Record Page I of 1 Information Use Type and Location of Emergency Kit:
WAS KIT COMPLETE MINIMUM DEVIATION INVENTORY COMMENTS KIT SIGNATURE FOR INVENTORY TAMPER SEAL INVENTORY INVENTORY? ENCLOSURE (e.g., Kit inventory following drill INVENTORY INTACT? OF KIT (Drill / Quarterly 5.16 use or quarterly inventory) DATE Initial, date and time isrequired for CONTROL COPY CONTENTS? Inventory) REQUIRED? COMPARISON YES/NO YES /NO YES/NO YES / NO Signature:
THIS COPY HAS BEEN COMPARED WITH THE CONTROL COPY AND IS VERIFIED CORRECT.
INITIAL DATE TIME Signature:
THIS COPY HAS BEEN COMPARED WITH THE CONTROL COPY AND IS VERIFIED CORRECT.
INMAL DATE TIME Signature:
THIS COPY HAS BEEN COMPARED WITH THE CONTROL COPY AND IS VERIFIED CORRECT.
INmAL DATE TIME Signature:
TltlS COPY HAS BEEN COMPARED WITH THE CONTROL COPY AND IS VERIFIED CORRECT.
_ INITIAL _ DATE TIME Signature:
THIS COPY HAS BEEN COMPARED WITH THE CONTROL COPY AND IS VERIFIED CORRECT.
INMAL DATE TIME Signature:
THIS COPY HAS BEEN COMPARED WITH THE CONTROL COPY AND IS VERIFIED CORRECT.
INITIAL _ DATE___ TIME Signature:
THIS COPY HAS BEEN COMPARED WITH THE CONTROL COPY AND IS VERIFIED CORRECT.
_ INIAL DATE TIME
Enclosure 5.15 HiP/O/B/I000/006 Recommended Shelf-Life for Protective Clothing Page 1 of I Information Use
- IF the date recorded on protective clothing package exceeds the allowable shelf-life (below),
remove and replace appropriate protective clothing in Emergency Kit.
Rubber Shoe Covers - 2 yrs Rubber Gloves - 2 yrs Cotton PCs - 5 yrs Cotton Liners - 5 yrs Sacksuits - 5 yrs Disposable Shoe Covers - 2 yrs Vinyl gloves - 5 yrs
Enclosure 5.16 HP/01B/ 1000/006 Emergency Equipmcnt Deviation Form Page 1 of I Information Use EMERGENCY KIT Description of kit deviation:
Action taken to remedy deviation:
PlP# C- -
Individual identifying deviation: Date: Time: :-
Signature File Completed Form in Emergency Equipment Inventory Logbook TIllS COPY HAS BEEN COMPARED WITH TIHE CONTROL COPY AND IS VERIFIED CORRECT.
INITIAL Date TIME
( Enclot 5.17 HP/O/B/1001 6 Quarterly Field Team Radio / Cellular Phone Check Record Page I of I Information Use RADIO / PHONE COMMENTS PERFORMED AT DATE IDENTIFIER 5-10 MILE ONSITE OF RADIO or PHONE
_CHECK THIS COPY HAS BEEN COMPARED WITH Radio / Phone check performed by: ,Date .
THE CONTROL COPY AND IS VERIFIED CORRECT.
INITIAL _ _ Date ___ TIME
(M70M2) Duke Power Company (1) IDNo. IIP/O//1009/009 PROCEDURE PROCESS RECORD Revision No. 040 PREPARATION (2) Station Catawba Nuclear (3) Procedure Title Guidelines for Accident and Emergency Response (4) Prepared By . 3* /i4 7 Date _ _ _c_
(5) Requires NSD 228 Applicability DeterminatiouJlf Applicability Determination is required, attach NSD 228 documentation.
o Yes (New procedure or revision with major changes) 0 No (Revision with minor changes) o No (To incorporate previously approved changes)
(6) Reviewed By _ _ __ _ _ (QR) Date 31 o Cross-Disciplinary Review By (QR) NAeŽH Date 3I/9Ze Z Reactivity Mgmt. Review By (QR) NASH Date ?/c %
Mgmt. Involvement Review By (Ops. Supt.) NAB- Date 3 IRA (7) Additional Reviews r at }p /1 Reviewed By {1 ( ,41 V4 ul Date Reviewed By ' /61 1 Date / /C (8) Temporary Approval (if necessary)
By (OSM/QR) Date By (QR) Date (s Approved By __ __ Date ________
PERFORMANCE (Comnpare with control copy every 14 calendardays while work is being perfomied.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date
( 1) Date(s) Performed Work Order Number (WOM)
COMPLETION (12) Procedure Completion Verification:
o Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
o Yes 0 NA Required enclosures attached?
0 Yes 0 NA Data sheets attached, completed, dated, and signed'?
o Yes 0 NA Charts, graphs. etc. attached. dated, identified, and marked'?
o Yes 0 NA Procedure requirements met'?
Verified fBy Date (13) Procedure Completion Approved Date (14) Remarks (Attach ad!ditionalpages, if necessary)
Procedure No.
Duke Power Company Catawba Nuclear Station HP/O/B/1009/009 Revision No.
040 Guidelines for Accident and Emergency Response Electronic Reference No.
Reference Use CN005CVD
HP/O/B3/1009/009 Page 2 of 4 Guidelines for Accident and Emergency Response
- 1. Purpose To provide guidance for notification/activation of Radiation Protection (RP) Emergency Response Organization (ERO) in the event of an emergency situation.
- 2. References 2.1 HP/0/B/1001/018 - RP Compliance Sampling 2.2 HP/0/B/1009/003 - Radiation Protection Response Following a Primary to Secondary Leak 2.3 HP/0/B/1009/004 - Environmental Monitoring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear Station 2.4 1-P/0/B/1009/005 - Personnel/Vehicle Monitoring for Emergency Conditions 2.5 HP/O/B/1009/006 - Alternative Method for Determining Dose Rate Within the Reactor Building 2.6 HP/0/13/1009/007 - In-plant Particulate and Iodine Monitoring Under Accident Conditions 2.7 lIP/O/B/1009/008 - Contamination Control During Transportation of Contaminated Injured Individuals 2.8 1-1/O/B/ 1009/01 1 - EMF Loss 2.9 HPP/0/B/1009/014 - Radiation Protection Actions Following an Uncontrolled Release of Liquid Radioactive Material 2.10 HP/0/13B1009/026 - On-Shift Offsite Dose Projections 2.11 Rl'/O/A/5000/010 - Conducting a Site Assembly or Preparing the Site for an Evacuation 2.12 RI/O/A/5000/02() - Technical Support Center (TSC) Activation Procedure
SP/0IB/1I009/009 Page 3 of 4 2.13 RP/0/1315000/024 - OSC Activation Procedure 2.14 SH/0113/20051003 - Distribution of Potassium Iodine Tablets in the Event of a Radioiodine Release 2.15 Nuclear Policy Manual NSD 114 - Site Assembly/Site Evacuation 2.16 CNS Emergency Plan
- 3. Limits and Precautions None
- 4. Procedure 4.1 Activate Emergency Response Organization per CNS Emergency Plan.
4.2 Activate RP ERO using one or more of the following methods:
- RP Management notification
- Beeper Activation
- Station Paging System NOTE: IF a Site Assembly is announced RP work group assembles in the OSC per Nuclear Policy Manual NSD 114 (Site Assembly/Site Evacuation).
4.3 Activate RP ERO positions the in Operations Support Center (OSC) using RPIO/13/5000/024 (OSC Activation Procedure).
- Contract personnel sponsored by RP (e.g., vendor RP Technicians) report to OSC RP Supervision for assignment, as necessary.
- ERO personnel providing RP support (e.g., Drivers for Field Monitor Teams report to their assigned work group Site Assembly point per NSD 114 and then proceed to OSC for assignment and dispatch).
4.4 Activate RlI ERO positions in the Technical Support Center (TSC) using RIVO/A15000/020 (Tecinical Support Center (TSC) Activation Procedure).
IIP/0/B/1 009/009 Page 4 of 4 NOTE: RP Duty Shift is responsible for on-site emergency response during backshifts, weekends and/or holidays until augmented by oncoming RP personnel.
4.5 Provide RP support to Operations Shift Supervisor/Emergency Coordinator.
- Use Enclosure 5.1 (Radiation Protection Initial/Continuing Emergency Rdsponse) as a guide for RP ERO response.
- IF necessary, provide turnover to oncoming RP personnel.
4.6 Ensure ERO facilities and RP emergency equipment is restored to a state of operational readiness after termination of response.
- Notify Emergency Planning and/or RP Supervision if RP Emergency Kits, equipment or ERO facilities can not be restored or replaced to state of readiness within twenty four hours following termination of ERO activation.
- 5. Enclosures 5.1 Radiation Protection Initial/Continuing Emergency Response 5.2 Radiation Protection Assignment Log
Enclosure 5.1 HIP/0/m/1009/009 Radiation Protection Initial/Continuing Page I of 5
Response
NOTE:
- Enclosure steps may be implemented in any sequential order to provided radiological protection functions, based on severity of emergency conditions.
- 1. Recommend on-site protective action(s) for any assembled personnel and provide protective actions for those personnel with work duties in radiological areas.
- 2. Coordinate in-plant monitoring to support Control Room, Technical Support Center (TSC) and Operations Support Center (OSC).
NOTErl: HPI0/1B/10091026 (On-Shift Offsite Dose Projections) is to be performed by RP Duty Shift prior to activation and availability of Emergency Response Organization (ERO) dose assessors nonnally located in the TSC or Emergency Operations Facility (EOF).
- 3. IF Operations Shift Manager (OSM) and/or On-Shift Emergency Coordinator notifies RP Duty Shift that a site Emergency Action Level (EAL) classification has been declared and notification to offsite agencies is required, perform offsite dose projection(s) using HP/0/13/1009/026 (On-Shift Offsite Dose Projections).
- Respiratory Printout or computer access to respiratory issue software
- Master keys for Extra High Rad areas
- Radiation survey instruments (e.g., Gamma Alarn, extendable Teletector, Eberline RO-20, or equivalent type instruments)
NOTEl: IF computer method for personnel accountability) are not available per NSD 114 (Site Assembly/Site Evacuation), notify Security within 30 minutes of ERO activation for all RP personnel on Site.
- 6. Wh'IlN ERO is activated begin accounting for RI' personnel on site.
- IF available, Rl' personnel on site report to Supervisor or lead person.
- IF necessary, Rl' Lead Person or work group supervisor notify Rl' Shift or OSC RlI Supervisor for tile work group accountability.
Enclosure 5.1 H1P/0/131009/009 Radiation Protection InitiaUContinuing Page 2 of 5
Response
- IF necessary, Security can be contacted at any of the following phone numbers: 831-3254, 5364 or 2393.
NOTE: Notify OSC Coordinator of any RP work teams assigned prior to OSC activation, (e.g.,
Rescue and Repair Teams or Field Monitor Teams).
WARNING: Give consideration to the possibility that reactor conditions may be unstable and radiological conditions may be unknown.
- 8. IF necessary, provide immediate RP support for any of the following activities:
- Fire Brigade
- Contaminated medical injury response
- Emergency Rescue and Repair teams
- RP job coverage for chemistry sampling, plant operations and/or maintenance activities
- Other actions or mitigation strategies prescribed by ERO management
- 9. Il' required, initiate emergency response procedures as necessary.
- I1 necessary, initiate HP/0/B/1001/018 (EMF Sampling).
- IF necessary, initiate HP/0/B/10091003 (Radiation Protection Response Following a Primary to Secondary Leak).
- IF necessary, initiate IIP/O/B/1009/008 (Contamination Control During Transportation of Contaminated Injured Individuals).
- IF necessary, initiate HlP/O/1311009/01 1 (EMF Loss).
- IF necessary, initiate HP/0/13/1009/014 (Radiation Protection Actions Following an Uncontrolled Release of Liquid Radioactive Material).
Enclosure 5.1 OP/0/13lo009/009 Radiation Protection Initial/Continuing Page 3 of 5
Response
- IF necessary, assist RP Supervision complete Minimum Staffing Levels for RP OSC Personnel from RP/IOB/5000/024 (OSC Activation Procedure).
- IF necessary, assign a person to verify respiratory qualifications of OSC personnel.
- IF necessary, assist in completion of OSC Team Work Sheet from RP/01B1/5000/024 (OSC Activation Procedure).
E necessary, assist RP Supervision with trending and recording of available radiological IF information to support RP OSC response.
- IF necessary, assist RP Supervision coordinate RP shift rotation and augmentation of RP ERO personnel.
I1. IF available, assist RP Supervision coordinate RP activities for OSC teams.
- Establish travel route to and from job to be performed.
- Establish dose limits and/or dose rate limits during pre-job planning for high exposure jobs.
- Manage planned emergency exposures using station procedures and CNS Emergency Plan.
- Inform teams of known plant radiological conditions during RP job planning.
- Prescribe protective clothing requirements to prevent the spread of contamination.
- 12. IF necessary, assist RP Supervision coordinate and dispatch IField MonitorTeams (FMT) from available OSC personnel per HP/O/B/1009/004 (Environmental Monitoring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear Station).
NOTE:
- IF necessary, an on site survey team (e.g., Foxtrot Team) may be dispatched from OSC to perform radiation surveys inside the security protected area fence in addition to offsite FMT's under direction of TSC or EOF.
- On-Site Survey Teams sent out from OSC report survey information back to OSC RP Supervision (e.g., on-site survey radiological results inside Protected Area Fence are to be reported to OSC ERO Management).
- Oni-site survey results should be reported to TSC Rl' Support or Field Monitor Coordinator (FMC) as directed by OSC RP Supervision (c.g., use telephone to report on-site radioactive release information) to supplement offsite EMT survey results.
Enclosure 5.1 HIP/0/B/1009/009 Radiation Protection Initial/Continuing Page 4 of 5
Response
- 13. IF necessary, assist RP Supervision implement contamination control requirements for the Site.
- 14. IF necessary, assist RP Supervision coordinate the set up and source check of radiological monitoring equipment in plant areas (e.g., portal monitor and/or portable frisking equipment).
- IF necessary, use page announcement to notify personnel of requirement for use of personnel monitoring equipment (e.g., portal monitors and frisker use).
- Ensure contamination control methods are used according to station procedures.
15 IF necessary assist RP Supervision monitor dose rates in the OSC.
- IF necessary, establish control methods for personnel radiation exposure.
- IF necessary, limit personnel exposure to blanket dose extension levels.
- IF necessary, initiate discussion with RPM on the need to evacuate the OSC if General Area dose rate approaches 5 mremlhr and dose rate is expected to continue.
- 11 necessary, relocate Personnel Monitoring Teams to Low dose areas (< 5 mremlhr),
appropriate to site radiological conditions (e.g., plume directional movement).
- 16. Evaluate radioactive contamination in the OSC.
- Direct contamination surveys appropriate to radiological conditions.
- IF necessary, initiate decontamination of equipment and/or personnel.
- 17. IF necessary, assist RP Supervision request Commodities and Facilities (CMF) support for additional protective clothing, dosimetry, or other necessary emergency response equipment.
- Use equipment and supplies available at normal issue points (e. g., ERO Emergency Kits).
- 18. IF necessary, assist RP Supervision coordinate radiological monitoring of food items supplied to OSC with assistance from CMF and Emergency Planning (EMP) representatives.
- IF necessary, initiate "no eating or drinking" contamination control requirements when food items are brought into emergency response facilities.
- Ensure contamination control methods are used according to station procedures.
Enclosure 5.1 IP/O/Bl10091009 Radiation Protection Initial/Continuing Page 5 of 5
Response
- 19. WHEN necessary, assist RP Supervisor and/or Radiation Protection Manager (RPM) establish Count Room sample analysis priority based on need for isotopic results (e.g., FMT, OSC, TSC and/or Chemistry sample results).
IF necessary, assist RP Supervisor or RPM determine alternate sample counting-location as a result of adverse Auxilary Building RP Count Room conditions.
NOTE:
- Site Assembly areas specified in NSD 114 (Site Assembly/Site Evacuation) may be changed based on updated radiological assessments of plume directional movement and/or other radiological conditions per RP ERO management discretion.
- Non-essential personnel should be sent to appropriate staging area; (e.g., non-essential personnel may be sent to the Administrative Building) considering upwind directional movement of a plume, if such information is available from TSC Dose Assessor and/or Field Teams.
- 20. IF necessary, assist RP Supervision in movement of non-essential personnel per RP/O/A/5000/010 (Conducting a Site Assembly or preparing the Site for an Evacuation).
- WHEN moving non-essential personnel give consideration to declared pregnant women.
- 21. IF necessary, assist RP Supervision in initiation of emergency procedures.
- HiP/0/B/1009/006 (Alternative Method for Determining Dose Rate Within the Reactor Building)
- IHP/0/13/1009/007 (In-Plant Particulate and Iodine Monitoring Under Accident Conditions)
R Seles/B/2005/003 (Distribution of Potassium Iodine Tablets in the Event of A Radioiodine Release)
- 22. 11 required, identify RP personnel for personnel monitoring teams as they become available, for the following locations:
- On-site assembly areas identified in NSD 114 (Site Assembly/Site Evacuation).
- PAIP Area
- Evacuation Facility
- 23. 11F necessary, initiate HP/0/B/1009/O05 (P'ersonnel/Vehicle Monitoring for Emergency Conditions).
- 24. Assist RI' management restore equipment to a ready state condition after a drill or ERO activation event is terminated.
Enclosure 5.2 HP/0/B/1009/009 Radiation Protection Assignment Log Page I of I NOTE:
- Personnel that may have consumed alcohol within the last 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> must have approval from a member of Station Management prior to assignment of ERO duties.
- Personnel shall be Fit for Duty and clean shaven for OSC and FMT team assignments.
- 1. Assignment to the following positions is on an as needed basis with consideration of RP ERO qualifications and availability of RP personnel.
- 2. RP Technicians and drivers not assigned to Field Monitor Teams should remain available for ERO assignment and/or relief duties, as designated by RP Supervision (or RP Duty Shift).
FMT Sample Van # I RP Technician FMT Sample Van # 1Drivcr FIMT Sample Van It 2 RP Technician FMT Sample Van # 2 Driver FMT ALPHA Vehicle RP Technician FMT ALPHA Vehicle Driver FMT BRAVO Vehicle RP Technician FMT BRAVO Vehicle Driver FMT CHARLIE Vehicle RP Technician FMT CHARLIE Vehicle Driver FMIT DELTA Vehicle RP Technician FIMT DELTA Vehicle Driver OSC/RP Technician It I OSC/RP Tcchnician # 2 OSC/RP Technician #t3 OSC/RP Technician It 4 OSC/RP Technician It 5 OSC/RP Technician It 6 OSC/RP Technician ft 7 OSC/RP Technician It 8 OSC/RP Technician ft 9 OSC/RP Technician II 10 OSC On-Site Team FOXTROT TSC Rl' Tecinician_
PHONE NUMBERS:
TSC RADIATION PROTECTION SUPPORT 831 - 5882 / 8182 OSC RADIATION PROTECTION MANAGER 831 - 4157 EOF FIELD MONITORING COORI)INATOR 382 - 0736 EMERGENCY KIT ROOM 831 - 5634 SECURITY SillFT SUPERVISOR 831 - 3253 / 2393 I 3254
(R0ll".)
, Duke Power Company (I) ID No. TIP/OJB/1009/026 PROCEDURE PROCESS RECORD Revision No. 007 PREPARATION (2) Station Catawba Nuclear Station (3) Procedure Title On-Shift Offsite Dose Proiections (4) Prepared By Date -3/ /0 (5) Requires NSD 228 Applicability Dcterminaton? If Applicability Determination is required, attach NSD 228 documentation.
0 Yes (New procedure or revision wit ~ir changes) 0 No (Revision with minor changes) 0 No (To incorporate previously approved changes)
(6) Reviewed By (QR) Date ?l2S7/c Cross-Disciplinary Review By (QR) NAi-4 Date 316,1,9F Reactivity Mgmt. Review By (QR) NA1V Date I/WO Y Mgmt. Involvement Review By (Ops. Supt.) NAG~ Date /i Y (7) Additional Reviews C Date Reviewed By Date Reviewed By Date _________
(8) Temporary Approval (if necessary)
By (OSM/QR) Date ApvBBy (OR) Date (IApprovcd By , _ Il 'f^Ro Date PERFORMANCE (Compare with control copy every 14 calendardays while work is beingperfonned.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (I I) Date(s) Performed WVork Order Number (WOM)
COMPLETION (12) Procedure Completion Verification:
o Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
o Yes 0 NA Required enclosures attached?
o Yes 0 NA Data sheets attached, completed, dated, and signed?
o Yes 0 NA Charts. graphs, etc. attached. dated, identified, and marked?
o Yes 0 NA Procedure requirements met?
Verified By Date (13) Procedure Completion Approved Dale (14) Remarks (Attach additionalpages, if necessary)
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Duke Power Company Procedure No.
KJ Catawba Nuclear Station HP/O/B/1009/026 Revision No.
On-Shift Offsite Dose Projections 007 Electronic Reference No.
Reference Use
. CP00945J KJ K>
IP/0/B1/1009/026 Page 2 of 13 On-Shift Offsite Dose Projections
- 1. Purpose The purpose of this procedure is to provide on-shift Radiation Protection (RP) personnel instruction for using the Raddose 5 Dose Assessment Software (DAS) computer program to project downwind offsite dose to the public and provide guidance for completing offilte dose sections on an Emergency Notification.
- 2. References 2.1 RP/O/A/5000/001 - Classification of Emergency 2.2 EPA 400-R-92-001 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.3 Earth Tech RADDOSE 5 Operator's Manual 2.4 PIP # C-03-03436 - Unit Vent Flow Computer Point Not Indicating Properly
- 3. Limits and Precautions None
- 4. Procedure 4.1 Procedure use 4.1.1 Obtain a Working Copy of this procedure.
4.1.2 Use this procedure during emergency conditions, including exercises and drills.
- Perform dose assessment when Operations Shift Manager (OSM) or On-Shift Emergency Coordinator notifies RP to perform this procedure due to declaration of a site Emergency Action Level (EAL) classification.
- Perform on-shift dose assessment prior to availability of Emergency Response Organization (ERO) dose assessor in the Technical Support Center (TSC) or Emergency Operations Facility (EOF).
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HPlO/B/1009/026 Page 3 of 13 KU NOTE:
- This procedure may be performed in sectional parts to evaluate and assess offsite dose from gaseous radioactive releases that may occur.
- This procedure describes information for using Raddose 5 (Earth Tech Raddose 5 Operator's Manual) in an abridged form where steps are performed for a single offsite dose projection. IF multiple offsite dose projections are required, r.ports can be obtained by repeating procedure steps.
4.2 Raddose-5 Automatic Version 4.2.1 Obtain information from Unit OSM as to Accident Type, Reactor Status, Release Information and current Emergency Classification per Enclosure 5.1 (Catawba Release Pathway Evaluation).
4.2.2 Select "RADDOSE" icon.
- Select appropriate unit icon for CNS.
4.2.3 Select Mode of Operation as "Automatic".
4.2.4 IF data is NOT available OR Automatic Mode does not continue, perform any or all of the following:
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- Close current application window
- Select "Cancel" on current application window
- Exit Raddose-5
- Go to step 4.3.1.
4.2.5 Select "Drill Mode" or "Accident Mode" as appropriate for the situation.
NOTE: IF the reactor did NOT trip and shutdown is in progress, THEN current date and time is the same as "Reactor Trip Date" and "Reactor Trip Time". IF start of offsite release is NOT known, THEN current date and time is the same as "Release Date" and "Release Time".
4.2.6 Input "Reactor Trip Date/Release Date" and "Reactor Trip Time/Release Time" per Enclosure 5. 1.
4.2.7 Enter operator's initials.
4.2.8 IF? all data input is correct, select "Accept".
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HP/0/B/1I009/026 Page 4 of 13 4.2.9 IF any data requires correction, select "Cancel".
- Select "Begin New Incident"
- Select "Yes" to "This erases all previous data..." question.
- Go to Step 4.2.6.
4.2.10 Select appropriate Accident Type for use with Automatic Mode.
- SG Tube Rupture 4.2.11 Select "Enter/Edit Meteorological Data" button.
4.2.12 IF all data automatically input via OILS PI (SDS), select "Accept".
4.2.13 IF all data is NOT automatically input via OILS PI (SDS), select "Cancel".
- Select "Go to Start-Up Menu".
- Select "Exit Raddose V".
- Go to Step 4.3.3.
4.2.14 Select "Enter/Edit Source Term Data" (automatically populating fields from PI data server).
4.2.15 IF all data is automatically input via OILS PI (SDS), select "Accept".
4.2.16 IF all data is NOT automatically input via OILS PI (SDS), select "Cancel".
- Select "Go to Start-Up Menu".
- Select "Exit Raddose V".
- Go to Step 4.3.3.
4.2.17 Select "Emergency Classification".
4.2.18 Select appropriate current classification.
4.2.19 Select "Continue".
4.2.20 Select "Start Auto Mode w/ Auto Reports" 4.2.21 114 you want to continue, select "Yes".
HP/0/13/ 1009/026 Page 5 of 13 4.2.22 IF you want to return to previous screen, select "No".
NOTE: Raddose-5 ("Automatic Mode Status Screen") will immediately generate a dose assessment report for the first step. The program will automatically wait 15 minutes and generate a report for the second and subsequent steps.
4.2.23 Create at least one copy of each dose assessment report for filing.
4.2.24 Provide data from Enclosure 5.5 (Emergency Notification), page 2 and 3 to OSM via the Emergency Notification Form, page 1.
- Continue production of offsite dose projections as OSM requests.
4.2.25 IFOSM requests additional Raddose-5 offsite dose projections, continue with Automatic Mode.
- Evaluate any increasing or adverse trends on additional dose projections.
4.2.26 IF no further on-shift dose assessment is required, select "Quit Automatic Mode".
- Select "Yes" to "Are you sure you want to exit Automatic operating K> mode?"
- Exit Raddose-V per Section 4.4.
4.2.27 IF notified by Unit OSM that Accident Type has changed, select "Quit Automatic Mode".
- Select "Yes" to "Are you sure you want to exit Automatic operating mode?"
- Select "Go to Start-Up Menu".
- Select "Begin New Incident".
- Select "Yes" in box with "This erases all previous data".
- Go to step 4.2.6.
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HP/0/13/1009/026 Page 6 of 13 4.3 Raddosc-5 Manual Data Collection 4.3.1 Use Enclosure 5.1 (Catawba Release Pathway Evaluation) for recording initial information about current site conditions.
- Obtain affected unit and reactor status information from Operations Shift Manager or designee.
4.3.2 Use Operator Aided Computer (OAC) Satellite Display System (SDS) to obtain information about site meteorological and radiological conditions.
4.3.3 IF additional information is necessary, use the following enclosures:
- Enclosure 5.2 (Catawba Meteorology for Manual Inputs) for meteorological data
- Enclosure 5.3 (Catawba Unit Vent Data for Manual Inputs) for release through a unit vent
- Enclosure 5.4 (Catawba Steam Release Data for Manual Inputs) for steam generator tube rupture or steam line release.
4.3.4 Select "RADDOSE" icon.
- Select icon for affected unit at CNS.
NOTE: This section of the procedure is for "Normal Mode" operation of Raddose.
4.3.5 Select "Normal".
4.3.6 Select "Drill Mode" or "Accident Mode", as appropriate to ERO response.
4.3.7 Select "Manual" at next prompt to manually enter all data.
A. Select "Begin New Incident".
B. Click "YES" at pop up box prompt, "This erases all previous data."
C. Use information from Enclosure 5.1 at "Accident Scenario Definition menu" to enter the following:
HP/O/B/ 1009/026 Page 7 of 13 NOTE: IF the reactor did NOT trip and shutdown is in progress, THEN current date and time is the same as "Reactor Trip Date" and "Reactor Trip Time". IF start of offsite release is NOT known, THEN current date and time is the same as "Release Date" and "Release Time".
- Reactor trip date
- Reactor trip time
- Release date
- Release time
- Raddose 5 operator's initials D. Ensure all data is correct.
IF any data is incorrect, select field with mouse to enter correct data.
NOTE: IF "Cancel" is selected to exit screen, no data will be saved.
E. Select "Accept" to progress to "Main Menu"; or select "Cancel" to exit screen.
4.3.8 At "Main Menu" select "Enter/Edit Meteorological Data".
- Select "OK" on "No Automatic meteorological data available. Enter data manually".
A. Enter the following meteorological data:
- Wind speed
- Wind direction
- Mixing height - (computer generated value)
- Delta temperature
- Air temperature
- Precipitation
HP/0/B/13009/026 Page 8 of 13 KJ~ B. Ensure all data is correct.
. IF any data is incorrect, select field with mouse to enter correct data.
NOTE: IF "Cancel" is selected to exit screen, no data will be saved.
C. Select "Accept" to return to "Main Menu" or select "Cancel" to exit screen.
4.3.9 At "Main Menu" select "Enter/Edit Source Term Data".
Click "OK" on "No Automatic monitor data is available. Enter data manually".
NOTE: "Accident Type" is option selected by user for each time step path based on accident for affected Unit Ior Unit 2.
4.3.10 Under "Accident Type", click on "None" field to select LOCA or SGTR.
4.3.11 IF LOCA is selected, use information from Enclosure 5.1 for affected Unit Vent release Path 1.
K>~ A. For "NG Method", click on field to select EMF.
B. Select Unit Vent EMF36L.
NOTE: A pop-up box "Unit Vent Release Pathway Data" will be displayed and the user must select conditions for Unit Vent filter status using information obtained from Operations.
C. Select "Filter Status" on "Unit Vent Release Pathway Data" screen.
D. Select "Ice Condenser" status.
E. Select "Hold-Up Time" status.
F. Select "Spray Status".
G. Select "OK".
H. Enter EMF monitor reading.
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HP/0B/1 009/026 Page 9 of 13 NOTE: IF Unit Vent Flow Monitor is inoperable OR Unit Vent Flow Rate indication is
< 1.00E+5 ft 3/min, 1.90E+5 ft3 /min shall be used for Unit Vent "Flow Rate" (PIP # C-03-03436).
I. Enter Unit Vent "Flow Rate".
J. Repeat steps 43.11 A. through 4.3.11 I. for the unaffected Unit Vent release Path 2.
K. IF appropriate, enter accident type and required data for additional release path within the same time step.
L. IF any data is incorrect, select field with mouse to enter correct data.
NOTE: IF "Cancel" is selected to exit screen, no data will be saved.
M. Select "Accept" to return program to "Main Menu" or "Cancel" to exit screen.
4.3.12 IF SGTR is selected, use information from Enclosure 5.1 for affected Unit release Path 1:
K-' A. For "NG Method", click on field to select EMF.
B. Select Unit Vent EMF36L.
NOTE: A pop-up box "Steam Line Release Pathway Data" is displayed where the user must choose conditions for Steam Generator release being Partitioned or Not-Partitioned; using information obtained from Operations.
C. Select "Partitioned" or "Not Partitioned", and then "OK".
D. Enter EMF "Monitor Reading".
E. Enter release flow rate.
F. Repeat steps 4.3.12 A. through 4.3.12 E for the unaffected Unit Vent release Path 2.
G. For "NG Method", Path 3 for affected Unit, select affected Steam Generator EMF.
- 11. Select "[artitioned" or "Not Partitioned", and then "OK".
- 1. Enter EMF "Monitor Reading".
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i IP/013B/1009/026 Page 10 of 13 J. Enter release flow rate.
K. IF appropriate, enter accident type and required data for additional release path within the same time step.
L. IF any data is incorrect, select field with mouse to enter correct data.
NOTE: IF "Cancel" is selected to exit screen, no data will be saved.
M. Select "Accept" to return program to "Main Menu" or "Cancel" to exit screen.
4.3.13 Select "Emergency Classification".
4.3.14 Select appropriate Classification.
4.3.15 Select "Accept".
4.3.16 Select "Continue".
4.3.17 Select "Perform Calculations" at "Main Menu".
NOTE: The program displays a pop-up box "Please wait...calculating Step # - Loop over Puffs -
number of puffs = "; and calculates the offsite dose for the current time step. The final output is a Real-Time Mode display of the plume path with Maximum Dose Rates (mrem/hr) on 10-Mile Emergency Planning Zone (EPZ) map.
A. Select "Continue" on 10-Mile EPZ Map to go to "Output Menu".
NOTE: A pop-up box is presented "Please wait, writing spreadsheet data file" where final display is the Real-Time Mode Output Menu.
B. Select "Continue Calculations" to return to "Main Menu".
C. At "Main Menu" select "Perform Forecast".
NOTE: A pop-up box is presented "Please wait, writing spreadsheet data file" where final display is thre Real-Time Mode Output Menu.
D. Select "Continue Calculations" to return to "Main Menu".
E. At "Main Menu" select "Perform Forecast".
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HP0/BI/1 009/026 Page 11 of 13 NOTE: The program displays a Forecast Mode dialogue box where the user must select options for current conditions that the program uses for Line #10 and #13 on Enclosure 5.5.
(Emergency Notification).
F. Select one of the following for "Emergency Release Status":
- None
- Potential
- Is Occurring
- Has Occurred G. Ensure "New" is selected for "Status of Projected Offsite Dose".
H. Click on Forecast Period (hours) box to enter release duration.
- IFrelease duration is unknown, enter default time of one (1) hour.
- Ensure data selections are correct.
I. Select "OK" to proceed.
J. Select "OK" at pop-up box; "Note: Forecast will use meteorological and source term data from Step #. Continue?"
NOTE: A pop-up box with "Forecast for Period ending in i#hours -Number Puffs =" is displayed while the program calculates offsite dose. Final screen display is plume path on 10-Mile EPZ map with dose results in mrem.
K. Select "Continue" at EPZ plume map to proceed to "Output Menu" L. Select "No" at pop-up box "Do you want to save PAZs identified in Forecast Mode for evacuation?"
NOTE: The program displays pop-up box "Please wait, writing data spreadsheet file" and then returns to the Output Menu in the Forecast Mode.
M. Select "Go to Report Menu" at "Output Menu".
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IOP//B/ 1009/026 Page 12 of 13 NOTE: User can select printing options when the program displays a pop-up box for computer print Setup parameters. The program has option for number of copies to print and user can make selection to change desktop computer settings for printers.
N. Obtain the following Raddose-5 reports by selecting individual menu options:
NOTE: User must select "OK", "Cancel" or "Setup" following each report option "pop up box".
- 'Print Green Form + Summary Form"
- "Print Summary Form", for additional summary reports
- 0. Select "Return to Output Menu" to exit "Report Options Menu".
P. At the "Output Menu" in Forecast Mode select "Return to Main Menu".
Q. Select "OK" at pop-up box "You just completed a Forecast. Remember to check the meteorological and source term data for current information."
R. Go to Step 4.3.8 to continue report generation as required from "Main Menu" screen.
4.4 Exit Raddose-V 4.4.1 IF at "Output Menu" select "Return to Main Menu".
4.4.2 IF at "Main Menu" select "Go to Start-Up Menu".
4.4.3 Select "Exit Raddose-V" at "Start-up Menu".
4.5 Turnover 4.5.1 Provide all pertinent dose assessment documents to TSC Dose Assessors after TSC Emergency Response Organization (ERO) is activated.
4.6 Record retention 4.6.1 Retain the following:
- Reports generated during event
- Working Copy of procedure
- Other miscellaneous logs and notes KJ'
HP/0/13/1009/026 Page 13 of 13
- 5. Enclosures 5.1 Catawba Release Pathway Evaluation 5.2 Catawba Meteorology for Manual Inputs 5.3 Catawba Unit Vent Data for Manual Inputs 5.4 Catawba Steam Release Data for Manual Inputs 5.5 Emergency Notification
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Enclosure 5.1 HP/0/1B/1009/026 Catawba Release Pathway Evaluation Page I of 3 K>
Automatic: Affected Unit? U-I or U-2 Obtain Accident Type? LOCA or SG Tube Rupture SGTR information from Emergency Classification? NOUE Alert SAE GE Operations for affected Unit Did Reactor trip? Yes No Date/Time of Reactor Trip? ( / .
and record data I Mo yy/ hr. mn for Raddose-5 INITIAL IF the Reactor did NOT trip and shutdown is in progress, THEN current date and time is the same DATA as "Reactor Trip Date" and "Reactor Trip Time". ( /.*)
ENTRY: Mo yy/ hr. mn (Automatic & EF Operations does not know or provide a release time, then use current date & time.
Manual) Mo yy/ hr: nan Circle selected Manual: Affected Unit? U-I or U-2 options Accident Type? LOCA or SG Tube Rupture SGTR Emergency Classification? NOUE Alert SAE GE Did Reactor trip? Yes No Date/Time of Reactor Trip? ( / : )
Mo dd yy hr: mn K)~ IF the Reactor did NOT trip and shutdown is in progress. THEN current date and time is the same as "Reactor Trip Date" and "Reactor Trip Time". ( :
Mo yy/ hr mn IF Operations does not know or provide a release time, then use current date & time.
Mo dd yy fir: mn Is affected Unit Vent release filtered by Unit Vent VE/VA filtcr fans? ON OFF Ice Condenser Status?: "No Recirculation" "Recirculation" or "No Ice" Hold-Up?: " <=24 Hours" or " > 24 Hours" Spray Status?: ON OFF-Is unaffected Unit Vent release filtered by Unit Vent VEIVA filter fans? ON OFT Ice Condenser Status?: "No Recirculation" "Recirculation" or "No Ice" Hold-Up?; " <--24 Hours" or " > 24 Hours" Spray Status?: ON OFF IF a SGTR release, what is the affected steam generator? (A 13 C D) for steam line EM L( )
IF a SGTR release occurred, is the affected S/G isolated? Yes No Are affected S/G secondary side "U" tubes covered with water AND)is release Partitioned? Yes No Is steam from affected steam generators currently being released?! Yes No
Enclosure 5.1 HP/0/B/I 009/026 Catawba Release Pathway Evaluation Page 2 of 3 Release Duration Can radioactive release (steam or vent) pathway be isolated? Yes No Unknown (Manual What is the estimated stop time for the release?
ONLY)
Circle selected (F release stop time is unknown, use default of lhr.)
options Obtain from OAC SDS wind speed ( ) in mph - lower tower measurement preferred (Encl. 5.2); wind direction ( ) in degrees from North - upper tower measurement (Manual ONLY) Mixing height ( XXXXX ) in meters - calculated by program; Temperature DIT ( ) D/T in C0 AirTemperature ( ) inC0 Precipitation ( ) inches per quarter hour Obtain EMF STEP 1:
Monitor Reading and Accident Type: LOCA Vent or Steam release flow rate Unit 1 Vent AND Unit 2 Vent from OAC SDS NG Method (EMF36L-UV1L) (EM36L-UV2L)
(Encl. 5.3 & Filter Status ( On Off ) ( On Off )
5.4); (Manual Monitor Reading ( ) cpm ( ) cpm KJ ONLY) Vent Flow Rate ( ) cfm ( ) efm Circle selected options Accident Type: SGTR Unit 1 Vent AND Unit 2 Vent NG Method (EMF36L-UV1L) (EM[F6L-UV2L)
Filter Status ( On Off ) ( On Off )
Monitor Reading ( ) cpm ( ) cpm Vent Flow Rate ( ) cfm ( ) cfm Unit I OR Unit 2 AffectedS/G ( A, B, C, D ) AffectedS/G (A,B,CD )
NG Method(EMF) ( ) NG Method(EMF) ( )
Partitioned ( Yes No ) Partitioned ( Yes No )
Monitor Reading(mR/hr) ( ) Monitor Reading(mR/hr)( )
Steam Rel. (Ibm/1S min) ( ) Steam Rel. (IbmfI15m) ( )
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Enclosure 5.1 HP/O/B/1009/026 Catawba Release Pathway Evaluation Page 3 of 3 K>
NOTE:
- Use consistent Accident Type (LOCA or SGTR) for each Raddose 5 release path, for each fifteen minute time step.
- Change the Accident Type only when reactor plant status indicates conditions that are degrading to a different type of accident.
- 1. Use Loss Of Coolant Accident (LOCA) Accident Type for assessment method for either Unit Vent(s) release path(s).
- LOCA - Loss of coolant (normal coolant) - leaks released into containment with fission products normally found in coolant and release pathway is through either Unit Vent
- After a valid increase or Trip 2 alarm on a Unit Vent radiation monitor select a vent EMF monitor
- Unit I or Unit 2 Vent EMF36 (low range in counts per minute)
- 2. Use S/G Tube Rupture (SGTR) Accident Type for primary to secondary system tube leak with relief valve open or steam line break and/or noble gas release through Unit Vent.
- SGTR - Steam generator tube rupture (normal coolant) - steam generator release accidents with fission products normally found in coolant where release pathway is any main steam line and/or KIj power operated relief valve open
- After a monitor increase or valid Trip 2 alarm on any steam line radiation monitor select affected steam line and EMF radiation monitor
- Unit 1 EMF26 EMF27 EMF28 EMF29 (Steamline A, B, C, D) with reading in mR/hr
- Unit 2 EMF1O EMFI I EMF12 EMF13 (Steamline A, B, C, D) with reading in mR/hr K>11
Enclosure 5.2 HiPI/OB/1009/026 Catawba Meteorology for Manual Inputs Page I of 2
- 1. Access CNS Meteorological Tower data using OAC Satellite Display System (SDS) by entering GD ERORD5 (meteorological and EMF data), or GD EROENV (15 minute average data).
NOTE: Table below shall be used to record appropriate RADDOSE information.
71
- Use lower tower wind speed (WS) in miles per hour
- Use upper tower wind direction; in degrees from North where (N) = 00
- Use upper tower wind speed (WS) if lower tower wind speed is not available
- Use lower tower wind direction if upper tower wind direction is not available
- 2. IF CNS Meteorological Tower data is not available request meteorological information from Operations or obtain meteorological information by calling McGuire Nuclear Station Control Room (8-875-4262,4263 or 4138).
- IF CNS meteorological tower temperature gradient D/T is unknown use the following default based on time of day, for stability classification, and complete the table below.
A. Between 1000 - 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />; assume AT = - 0.3 and Stability Class D B. Between 1600 - 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />; assume AT = + 1.3 and Stability Class F
- 3. Obtain fifteen minute average meteorological data for Raddose-5.
- Record information on Enclosure 5.1
- Complete Enclosure 5.2 as necessary Temperature Gradient AT in (C0 ) Stability Class AT` < -0.97 A extremely unstable AT -0.97 < AT * -0.87 B moderately stable AT -0.87 < AT < -0.76 C slightly unstable AT -0.76 < AT * -0.25 D neutral AT-0.25 < AT _+0.76 E slightly stable AT+0.76 < AT <+2.04 F moderately stable AT +2.04 <AT G extremely stable K>
Enclosure 5.2 1P/013B/l009/026 Catawba Meteorology for Manual Inputs Page 2 of 2
- 4. Enter data in the Raddose-5 program.
- Use MNS wind and temperature meteorological data if live time data is unavailable
- Use CNS default time of day D/T if data is unavailable
- wind speed in miles per hour (mph)
- wind direction; where wind direction is from North (N = 00)
- delta temperature gradient in degrees centigrade (AT = C0 ); where meteorological tower temperature is recorded for the low level sensor (lOm) with delta-temperature (AT) as the difference in the reading between the low and high sensor (60m)
- meteorological stability class is computer generated
- mean mixing height (in meters) is computer calculated using AT
- air temperature is in degrees centigrade (Temperature in C0 )
- precipitation occurring (inches per fifteen minute period)
KH> 5. Obtain most current meteorological conditions for Raddose-5.
- Obtain most current wind direction and wind speed to determine downwind Protective Action Zones (PAZs)
Enclosure 5.3 H P/O/B/ 009/026 Catawba Unit Vent Data for Manual Inputs Page I of 2 K)
- 1. Determine type of accident, source term release pathway, and EMF noble gas monitor method; (e.g., normal reactor coolant activity, with reactor coolant leak inside containment, LOCA, with radioactive gas leakage to Annulus through Unit Vent, with all filters intact and vent radiation monitor EMF36L).
- 2. Access OAC Satellite Display Systems (SDS) by entering GD ERORD5 (meteorological and EMF data), or GD EROEMF15 (15 minute EMF average data), or GD EROEMF (live time EMF display).
IF necessary, use top menu bar item GRAPHICS; select Ventilation and scroll to VE NTMENU; and use OK to open the display.
NOTE: I. IF Unit Vent Flow Monitor is inoperable OR Unit Vent Flow Rate indication is
< 1.00E+5 ft 3 /min, 1.90E+5 ft 3 /min shall be used for Unit Vent "Flow Rate" (PIP # C-03-03436).
- 2. Table below shall be used to record appropriate RADDOSE information.
Step Step- Path Accident Vent NG Monitor NG - I/P Iodine Part Number -Time Type Flow Method Reading Release Method Release Release LOCA or Rate in EMF in cpm or Rate Rate Rate
- SGTR ft 3 /min Monitor mR/hr Ci/sec Cilsec Ci/sec Computer Computer Computer Computer Computer Computer generated generated generated gcnerated generated generated generated
- Record information on Enclosure 5.1
- Complete Enclosure 5.3 as necessary
- Enter data in the Raddose-5 program
- 3. Select LOCA accident type for affected unit vent release pathway:
- LOCA - Loss of Coolant Accident (normal coolant)
- 4. Select affected Unit Vent Noble Gas method.
- UV 1L - Unit Vent 1 EMF-36L UV2L - Unit Vent 2 EMF-36L Other monitors available, but not specified for use in procedure:
- UVIH - Unit Vent 1 EMr-36H UV2H - Unit Vent 2EMF-36H
- UVIHH - Unit Vent lEMF-54 UV21 - Unit Vent 2EMF-54
- Use on-scale EMF readings when vent EMF sample pump is not tripped or EME package is not isolated; resulting from loss of power and/or EMF54 reading > 5 R/hr
- Evaluate (e.g., Auxiliary Building release) and select EMF radiation monitor for each unit vent.
Enclosure 5.3 HP/0/B/10091026 Catawba Unit Vent Data for Manual Inputs Page 2 of 2 K>
- 5. Select unit vent filtration reduction factors: Vent Filters On or Off, Ice Condenser Status - No Recirculation, Recirculation or No Ice, Hold Up time - "<= 24 Hours or > 24 Hours and Spray Status - On or Off.
- 6. Use RADDOSE 5 to calculate source term - vent release in Ci/sec.
- Ci/sec is calculated by isotope spectrum based on accident type and time after reactor shutdown.
RR = EMF x CF x AJ x FR x (1E-6Ci/[tCi x 1/60min/sec x 28320 mft3 )
Where:
RR = release rate activity in Ci/sec EMF = Use EMF36L counts per minute (cpm), if reading <1E+7 cpm and vent EMF sample pump is not tripped (UV IL, UV2L)
EMF = Use EMF36H cpm reading if EMF36L is offscale and EMF36H <IE+6 cpm and sample pump is not tripped (UV1H, UV2H)
EMF = Use EMF54 (R/hr) reading if EMF36L and EMF36H are offscale, and/or vent EMF sample pump is tripped (UVIHH, UV2HH)
KJ CF = Unit Vent radiation monitor Noble Gas Correlation Factor AJ = Adjustment Factors for Noble Gas, lodines and Particulates for accident types FR = Unit Vent Flow Rate in ft3 per minute; maximum vent flow S 1.90E+5 f 3 /min
- 7. IF release duration time is not known use a default timc of (1) hour for Raddose 5 (Forecast mode) dose projection.
- DO NOT save forecasted dose to PAZs K>
Enclosure 5.4 HIPIOIB31009/026 Catawba Steam Release Data for Manual Page I of 2 K-I Inputs
- 1. Determine type of accident; source term release pathway and EMF NG gas monitor method; (e.g.,
steam generator (S/G) tube rupture, with normal reactor coolant activity, with steam line Power Operated Release Valve (PORV) open and steamline EMF radiation monitor).
- 2. Access OAC Satellite Display Systems (SDS) display typing GD ERORD5 (meteorological and EMF data), or EROEMF15 (15 minute EMF average data), or GD EROEMF.Q{ive.time EMFdisplay), or GD EROSECND (live time display of secondary system data)
- IF necessary, to view steam release information type GD EROSECND; use lower left SDS screen arrows 44- to view affected steam line release information.
I NOTE: Table below shall be used to record appropriate RADDOSE information.
Il Step- Step
- Path Accident Steam NG Method EMF NG I/P Iodine Part Number Time Type Flow in Steamline Monitor Release Method Release Release last 15 EMF Reading Rate Rate Rate SGTR minutes Monitor in mR/hr Ci/sec Cil/sec Ci/sec Computer Computer Computer Computer Computer computer Computer generated generated generated generated generated generated gcnerated
- Record information on Enclosure 5.1 KJ
- Complete Enclosure 5.4 as necessary
- Enter data in the Raddose-5 program
- 3. Select Steam Generator Tube Rupture (SGTR) accident type for affected steamline release pathway:
- a. Select affected Steamline Noble Gas method
- Unit 1 - EM;26 EMM27 EMF28 EMM29 (Steamline A, B, C, D reading in mRlhr)
- Unit 2 - EMFIO EMF1 I EMF12 EMFL3 (Steamline A, B, C, D reading in mR/hr)
Enclosure 5.4 IIP/O/B/1009/026 Catanwba Steam Release Data for Manual Page 2 of 2 Inputs NOTE: IF a steam generator is not overfilled with primary water and reading is determined to be within gage level indicator a partitioning effect for dose reduction for radio-iodine and particulates can be selected in Raddose-5.
- b. Select S/G release reduction method:
- WHEN Unit 1 S/G tube break is below secondary side water level measured >0% Narrow Range water level indicator OR > 55% Wide Range water level select Partitioned.
E Unit 1 S/G water level CAN NOT be determined OR is <0% Narrow Range water IF level indicator OR < 55% Wide Range water level OR the break is above the secondary side water level where reactor coolant is released by steam release directly to offsite environment, select Not Partitioned.
- WHEN Unit 2 S/G tube break is below secondary side water level measured >5% Narrow Range water level indicator OR > 45% Wide Range water level select Partitioned.
E Unit 2 S/G water level CAN NOT be determined OR is <5% Narrow Range water IF level indicator OR < 45% Wide Range water level OR the break is above the secondary side water level where reactor coolant is released by steam release directly to offsite environment, select Not Partitioned.
- 4. Use Raddose-V to calculate source term - steam release in Ci/sec.
- Ci/sec calculated by isotope spectrum based on accident type and time after reactor shutdown RR = EMF x CF x AJ x LR x (0.4 ft3 /lbm x 28320 mI/ft 3 x IE-6 Ci/gCi x 1/3600/lr/s)
Where:
RR = release rate activity in Ci/sec EMF = radiation monitor reading in mR/hr (normally a 15 minute average reading)
CF = steam line radiation monitor Correlation Eactor AJ = Adjustment Factor (unit-less) based on accident type LR = Steam release rate from safety valve in pounds mass of steam released through each valve during valve open period (Ibm/15 min.), where; default release rate
=5.235134 Ibm/ 15 min.
- 5. IF release duration time is not known use default time of(l) hour for Raddosc 5 (Forecast mode) dose projection.
- DO NOT' save forecasted dose to PAZs
Enclosure 5.5 HP/O/B/1009/026 Emergency Notification Page 1 of 7
- 1. Emergency Notification Form (example):
EMERGENCY NOTIFICATION I. [ THIS tS A DRILL El ACTUAL EMERGENCY [ INITIAL [ FOLLOW-UP MESSAGE NUMBER..
- 2. SITE. natawba UNIT: _ REPORTED BY:
- 3. TRANSMITTALTIME(DATE I I CONFIRMATION PHONE NUMBER (Eastern) mmVddlyy
- 4. AUTHENTICATION (If Required):
(Number) (Codewod)
- 5. EMERGENCY CLASSIFICATION:
IM NOTIFICATION OFUNUSUAL EVENT [D ALERT [D STE AREA EMERGENCY [0 GENERAL EMERGENCY
- 6. [] Emergency Declaration At [j] Termiation At TIME/DATE. -_ .J J.I (118. go to Item 16)
(Eastern) mm dd yy
- 7. EMERGENCY DESCRIPTIONS/REMARKS:
- 8. PLANT CONDmON: [A IMPROVING [MO STABLE [f] DEGRADING
- 9. REACTOR STATUS: g] SHUTDOWN: TIME/DATE: :.L.... JJ_ i % POWER (Eastem) mm dd yy
- 10. EMERGENCY RELEASE(S):
[A NONE (Go to Item 14) [K] POTENTIAL (Go to Item 14) [C IS OCCURRING MD HAS OCCURRED
-111. TYPE OF RELEASE: [ ELEVATED E GROUND LEVEL AM AIRBORNE STARTED. 00-00 STOPPED: _
TIme (Eastern) Date Time (Eastern) Date
.K>-
[OLUQUID: STARTED: . J STOPPED:
- I I_
Time (Eastern) Date Time (Eastern) Date
-12. RELEASE MAGNITUDE 3 Curles Per Sec [TI Curies NORMAL OPERATING uMiTs: EIELOW 0 ABOVE A NOBLE GASES o00oF+00 (i IODINES 0-00E++/-
tCJ PARTICUtLATES o.tE0o [J OTHER
- -13. ESTIMATE OF PROJECTED OFFSITE DOSE: 0 NEW [ UNCHANGED PROJECTION TIME:
TEDE Thyroid CDE (Eastern) mOMr mrem ESTIMATED DURATION: _I HRS.
SITE BOUNDARY o0 F+w oo001+/-0 2 MILES O00E7+0 OD0F+00 5 MILES 0 OOEOO 10 MILES 0-00rf+0 o 0017+0
'14. METEOROLOGICALDATA ri] WINDDIRECTION(from) deg [1] SPEED (mph) _
C STABILITY CLASS _ [F PRECIPITATION (type) Iki1 Srmin
- 15. RECOMMENDED PROTECTIVE ACTIONS:
A NO RECOMMENDED PROTECTIVE ACTIONS EVACUATE C SHELTER IN-PLACE
_ OTHER
- 16. APPROVED BY: TIME/I:DATE: t___
(Name) (Titl) (Eastern) mm dd yy
' If Items 8-14 have not changed. only Items 1-7 and 15-16 are required lo be completed
- tnformation may not be available on Intial notificatIon
Enclosure 5.5 HlP/O/B/1009/026 Emergency Notification Page 2 of 7 K>
- 2. Dose Assessment Forecast Report ("Green Sheet") (example):
Catawba Nuclear Station Unit No 1 Dose Assessment RADDOSE-V Version 3.Oc Copyright 2002 Earth Tech Cwrent Date: 024r20 Step 1: I Current Tune: 09:2 Slep Date: 02/0420r0 Operat:rc CVW Step Th'4: 09:26 FORECAST FOR 1 HOUR ....
ACOOOD(T DESCRIPTION: C-.* En.eeeY h_- NOT b d RPAclor Shutdon02/04r20 0911tIths Accident Trte: 02V42003 0911 tIhs PATHWAY 1 Aocidont Type: LOCA FlowFRats: 1I30 6E+5 fttin Noble Gas Metiod UtIL(EM1F36L) Uonftor Reading: 2.t4ECO41t (P)
VentCF I1 .69E-C RELEASE RATEL Nobe Gas Pleoase Rate (Cilsec) 7.21 E-C6 Cs Below Nonta Operatog Liits bdine PRelease Rate (Cksec): 1.63E-09 CMs Partictwae Release Rale (C/sec): 2.50E1I Cts ACTUAL. FORtECAST AND TOTAL (Ferme
- k.qr) DOSES:
oDtU-I TEDE (ns) Thyeid COE ()
(nsI-11 Adue Ferseau TOW Acbu Foeoat ToW 0.e0 5se2E05 2ME604 2s1E04 1.44E04 s77E04 722644 100 0006.00 1oO6604 1.34E-04 eo00E.00 229sE04 2.216C04 2.00 000E.00 3s96s.05 1W66.0 6ooE.00 5266605 526E45 80 0o006.00 0C006.00 0e00.00 0E.00 0C006E.oo 000C.00 10.00 0:006.00 0:006.00 0.006.00 a:006.0 0006.00 0.006.00 UCTEOROLOCACL DATrA Wind Speed 2.5 rrsh (P) Stability Cass: G (P)
Whi Direction: Frorr 188.02 deogTo C02 dog KI RECOM4MCNDED PROTECT1VE ACTIONS: Based on Radiological Conditons Evacuate: None Shelter: None TOTAL (Fol. . Mte..6.d) DOSES FROM 0210400 09:11 TO 10:26:
rMirh cw~4 D( Rt_ (-M O. X/O (4n1k) 7EDE Thvld CDC TE6t Thbeld CDC (-d.M
.so +/-33644 5.77E04 zQIE104 722E.04 e4ASE04 1.00 1.396E4 2.29E04 1.39044 2294E4 3.37644 2.00 7.92T6o 1.0tCC04 3966.5 5266E45 I SSE44 s.W 00E6.00 eooE.00 0ooE.00 0o00E.00 0o006.00 10.00 0.006.00 a0006.00 0.006.00 0006E.00 0006E.00 DOSE CONVERSION FACTORS: rr re.n rrO3/Ci 0EDE: 2C7i-+07 PtoneEDE- 8.56E+04 Gro-nd EDE: 755E406 CDE Thyroid: 4.18E.08 ihalatiion: 131E.07 E6ERCGEN C-A5 . .....................
Tow Etieee_ Admit D.. Equ.1ten Thyroid Se Acre Emrwgency: No < 100 rrm No . 500 rrerm General Emegeini: No < 1000 Wrorn No < 5000 mrern I
I K>
Enclosure 55 HP/0/1B/10091026 Emergency Notification Page 3 of 7
- 2. Dose Assessment Forecast Report ("Green Sheet"):
PAGDose Units Iremn Srrm PAG Exoeeded at She Boundaty? No No PAQ Distance (miles): N/A N/A MONrTOR CORRECTION FACTORS:
Pathey I Tine Since Trip (Hs) 0.00 Ibe Condenser No Redrc Sprays On old-Up Time 4-24 tvs Cont Leak Rate Metiod Cont Leek Tye Cont Pressure Cont Leak Rate Cont Bypass Fraction FMtrs Yes SG Partitioned Pool Scmtbbl--
Field Measurement -
Orstanoe Direction Fuel Assenvy Age (Days)
Enclosure 5.5 HP/0/1B/1009/026 Emergency Notification Page 4 of 7
- 3. Provide Control Room personnel completing an Emergency Notification Form the following information using Raddose-5 data from Dose Assessment Forecast Report ("Green Sheet").
NOTE: Line # 5 - Emergency Action Level (EAL) classification is determined by OSM using RP/0/A/5000/001 (Classification Of Emergency) if offsite dose exceeds Selected Licensee Commitment (SLC) limits.
- Unusual Event - if gaseous or liquid radiological effluents exceed SLC limits
- Site Area Emergency - is classified if site boundary dose rate exceeds Forecasted TEDE dose > 100 mrem; and/or Forecasted CDE Thyroid dose 2 500 mrem
- General Emergency - is classified if site boundary dose rate exceeds Forecasted TEDE dose 2 I rem; and/or Forecasted CDE Thyroid dose > 5 rem Line # 10 - Emergency Release(s); use the following guidelines:
A. None - no release of radioactivity generated by the event and no release expected.
B. Potential Release - radioactivity generated during an event that has potential to be K.. released but is not currently being released.
- Discretionary option for the Emergency Coordinator or the EOF Director.
C. Is Occurring - radioactivity generated during an event that is currently being released through any defined accident pathway, using any of the following indicators:
- Either containment particulate, gaseous, iodine monitor readings indicate an increase in activity, OR Containment monitor readings indicate greater than 1.5 R/hr AND Either containment pressure is greater than 0.3 psig, OR An actual containment breach is known to exist;
Enclosure 5.5 HP/013/I1009/026 Emergency Notification Page 5 of 7
- Unit vent particulate, gaseous, iodine monitor readings indicate an increase in activity.
- Condenser air ejector exhaust monitor or other alternate means indicate Steam Generator tube leakage.
- Confirmed activity in the environment reported by Field Monitbr Team(s).
- Knowledge of the event and the impact on systems operation and resultant release paths.
D. Has Occurred - any radioactivity generated during an event that has been released previous to ERO activation that may require offsite agency notification.
Line I 11 - Type of Release
- Ground Level release and Airborne release with start time and stop time; if known.
Line # 12 - Release Magnitude in Curies per second (Ci/sec) released (from "RELEASE RATES:`
on Dose Assessment Report)
A. Indicate Normal Operating Limits: above or below site boundary limits; where Technical Specification site boundary dose rate limit is; < 0.05 mrem/hr and Child K<J Thyroid Dose rate limit is < 0.17 mrem/hr; using the following guidelines:
- Release Below Normal Onerating Limits is radioactivity released at any time during an event and/or radioactivity that may have been previously released that is not above site boundary normal operating limits.
- Release Above Normal Onerating Limits is any radioactivity released during the event and/or any radioactivity previously released that is above normal site boundary operating limits.
B. Quantity of each form of radioactive material released:
- Noble Gases
- lodines
- Particulates
Enclosure 5.5 HPP101B/10091026 Emergency Notification Page 6 of 7 Line # 13 - Estimate of Projected Offsite Dose (from "ACTUAL, FORECAST AND TOTAL (Forecast + Integrated) DOSES:" on Dose Assessment Report)
A. New - used for initial forecast and when forecasted dose results are calculated for Emergency Notification B. Unchanged - used when forecasted dose results are exactly the same as a previously issued Emergency Notification (for On-Shift Projections "New" is only selection).
C. Proiection Time - is "Step Time" from Dose Assessment Report D. Estimated Duration - is duration of release in hours; (On -Shift dose assessment projection time using "Automatic Mode" defaults to one hour. In "Manual" if release time is known to be > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, input time in hours.)
E. TEDE - projected offsite dose in mrem at; Site Boundary, 2 miles, 5 miles and l0 miles F. CDE- projected offsite dose in mrem at; Site Boundary, 2 miles, 5 miles and 10 miles K>
Line it 14 - Meteorological data A. Wind Direction - in degrees from North; where N = 00 B. Wind speed - in miles per hour (mph)
C. Stability Class - (A,B,C,D,E,F or G)
D. Precipitation - (type; e.g., rain, sleet, snow) inches in the last fifteen minutes Line 1 15 - Recommended Protective Actions (from "RECOMMENDED PROTECTIVE ACTIONS: Based on Radiological Conditions" oil Dose Assessment Report)
A. No Recommended Protective Actions - recommended if EPZ projected dose for PAZs is < 1.OE+03 mrem TEDE or < 5.0E+03 mremn Adult Thyroid CD)E.
Enclosure 5.5 HP/01B/10091026 Emergency Notification Page 7 of 7 B. Evacuate - recommiended for affected PAZs if the projected dose is Ž 1.OE+03 mrem TEDE or 2 5.0E+03 rnrem Adult Thyroid CDE; and recommend Shelter in Place for all other PAZs.
- IF the "Forecasted Dose" at the site boundary is 2 5.OE+03 mrem (Adult)
Thyroid CDE, notify the Control Room SRO to complete Line R15 per the following:
o Check block D ("Other")
o Enter the following sentence on the line to the right of "Other":
"Consider the use of KI (Potassium Iodide) in accordance with state plans and policy".
K>-
(R04-01) Duke Power Company (1) ID No. SUiO/B/2005/OOI PR6CEDURE PROCESS RECORD Revision No. 003 FOR STANDARD PROCEDURES PREPARATION (2) Procedure
Title:
Emerqencv Response Offtite Dose Proiections K>
,- -'I (3) Prepared By, &)A WZ Date 6 -A'g -° ,
IT (4) Applicable To: 0 ONS MNS X CNS (5) Technical Advisor ___ (97 I:tP L
- Cho ' GJNP y (6) Requires DYes No A Yes O No Yes 0 No NSD 228 Applicability YES= Nw procedure or reissue with major changes Determination NO = Reissue with minor changes OR to incorporate previously approved changes (7) Review (QR) By 4By./0 By Date____ _ Date....bt z/9/ Date Cross-Disciplinary _ By By 64Pay/7 tL-S97 Review (QR) NA Date NA Date 40 NA Date Z-Z3-0t/
Reactivity Mgmt. BY__y By Review (OR) NA " Date N- <<e Mgmt. Involvement By ByBy Review (Ops. Sup) NA Date NA &eDate ./7/°t NA&- Dateei-°0 (8) Additional By (QA) By (QA) ByjZ. -
K-i Reviews Date Date Date A/1 /0 By_ Byv. 2 By DateDate Date____________
(9) Approved By__ _ 1Lg ByG~n.
Date Date also U
'. Date 3- //-a0 (10) Use Level Use evelRcfrenc Reference Use PERFORMANCE (Compare with Control Copy every 14 Cdaendar days while work is being performed.)
(11) Compared with Control Copy . Date Compared with Control Copy Date Compared with Control Copy_ Date (12) Date(s) Performed Work Order Number (W)O#)
COMPLETION (13) Procedure Completion Verification O Yes J NA Check lists or blanks property initialed, signed, dated, or filled in NA. as appropriate?
O Yes 0 NA Required endosures attached?
O Yes 0 NA Data sheets attached, completed, dated, and signed?
0 Yes 0 NA Charts, graphs, etc.. attached and properly dated. identified, and marked?
0 Yes 0 NA Procedure requirements met?
Verified By Date (14) Procedure Completion Approved Date (15) Remarks (attach additional pages, itnecessary)
Duke Power Company Procedure No.
Catawba and McGuire Nuclear Stations SHl1/B/2005/001 Revision No.
Emergency Response Offsite Dose Projections 003 Electronic Reference No.
Reference Use MP007OPF KJ
SH/01B/2005/001 Page 2 of 17 KJ Emergency Response Offsite Dose Projections
- 1. Purpose To provide instruction to Emergency Response Organization (ERO) dose assessors for determining source term and calculating the projected offsite dose to the public using Raddose 5 (Earth Tech TM Windows© based computer program); and to provide dose assessment guidance for completion of Emergency Notification form.
NOTE: This procedure is an Emergency Plan Implementing Procedure (EPIP) to be used for Catawba and McGuire Nuclear Stations. Emergency Planning must be notified of any changes to this procedure.
- 2. References 2.1 Earth Tech Raddose 5 Operator's Manual, Detailed Design Manual, System Design Specification, Verification and Validation Report Vol 1 and 2 2.2 Station specific procedures for alternate method of determining Reactor Building dose rate:
CNS - HP/O/B/1009/006 Alternative Method for Determining Dose Rate Within the Reactor Building MNS - HP/O/B/1009/002 Alternative Method for Determining Dose Rate Within the Reactor Building 2.3 Station specific procedure for abnormal unit vent sampling:
MNS - HP/0B/1009/006 Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions 2.4 EPA 400-R-92-001 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.5 Letter from F.G. Hudson, September 20, 1985, Re: Release Rate Informaiion for McGuire and Catawba Nuclear Stations (File: GS-750.25, NUC-0306) 2.6 Letter from H.B. Tucker, November 30, 1989, Re: Follow-up on McGuire Alert (March 7 - 8, 1989) Critique Action Items 2.7 U.S. Nuclear Regulatory Commission Response Technical Manual (RTM-93)
K>
SH/0/13/2005/001 Page 3 of 17 K>~
2.8 Station specific procedures for classification of emergencies:
CNS - RP/IOA/5000/001 Classification of Emergency MNS - RP/0/A/5700/000 Classification of Emergency 2.9 Station specific procedures for notification to the States and Counties from. the Technical Support Center:
CNS - RP/0/B/5000/006B Notifications to States and Counties from the Technical Support Center MNS - RP/0IAI5700/018 Notifications to State and Counties from the Technical Support Center 2.10 SR/I/B/2000/004 Notification to States and Counties from the Emergency Operations Facility I
- 3. Limits and Precautions 3.1 Use this procedure during abnormal or emergency conditions (including exercises and drills).
3.2 This procedure may be performed in sections or parts, using steps in any sequential order, to evaluate and/or assess offsite radiological conditions.
- 4. Procedure 4.1 Use Raddose 5 program to calculate Total Effective Dose Equivalent (TEDE) exposure, Committed Dose Equivalent (CDE) Thyroid exposure, and Effective Dose Equivalent (EDE) exposure in ten-mile Emergency Planning Zone (EPZ).
- Provide information for offsite dose exposure and projected offsite dose rate results, from any radioactive material(s) released offsite, to ERO Management.
4.2 Access the Raddose 5 software.
4.2.1 Click on the Raddose 5 icon.
4.2.2 A dialog box should appear stating "Note: this workstation is configured as (EOF or TSC)". Click on "OK" to access the DAS (Dose Assessment Software) Desktop.
KJ
I1 SHa/OB/2005/001 Page 4 of 17 K>
4.2.3 IF the dialog box above does NOT appear, change the DAS configuration as follows:
4.2.3.1 At the DAS Desktop, click on "FILE".
4.2.3.2 Click on "DAS Configuration".
4.2.3.3 Click on appropriate Work Station Type (EOF or TSC) and Mode (Production or Training).
4.2.3.4 Restart Raddose 5 for changes to take affect.
4.2.4 Select the appropriate Station and Unit from the DAS Desktop.
NOTE: This procedure is for "Normal Mode" operation of Raddose only. The "Automatic Mode"-
contains limited choices and default assumptions. The "Automatic Mode" is used for on-shift dose assessment only.
4.2.5 Select "Normal Mode" at the Dialog Box.
4.2.6 Select "Accident Mode" or "Drill Mode" as appropriate.
K> 4.2.7 Select "PI Server" or "Manual" as appropriate.
- Select "PI Server" for program query of fifteen minute average data from Operator Aided Computer (OAC).
- Select "Manual" for keyboard entry of data.
K>
SH/0/132005/001 Page 5 of 17 4.2.8 IF this is the initial dose assessment calculation, select "Begin New Incident".
4.2.8.1 Enter information (e.g., reactor trip date, reactor trip time, release date and release time).
E the reactor did not trip, and shutdown is in progress, IF THEN use current time in the blank for reactor trip time.
CAUTION: IF the automatic transfer of Raddose data into the Electronic Emergency Notification Form is going to be used, per the "Save Green Form Data To Ini File" Function, it is important that the release time entered is the time of the actual release. This time is transferred to the Electronic Emergency Notification Form.
- Enter release time (estimated or known).
- Enter operator initials and use the mouse to accept and/or cancel.
4.2.9 IF this is a continuation of a previous incident, AND IF previous TSC or EOF files are valid, select "Continue Previous Incident".
4.2.9.1 Select "Local Data" to continue previous dose assessment calculation that was previously performed on the current workstation.
4.2.9.2 Select "Network Data" to continue previous dose assessment calculation that was previously performed at another facility.
4.3 Select "Enter/Edit Meteorological Data" from program selection.
4.3.1 IF "Manual" was selected in Step 4.2.7, select "OK" to Raddose pop-up message: "No automatic meteorological data available. Enter data manually." I 4.3.2 Input data for current meteorological conditions.
- Use actual site meteorology for assessment of a release until it is appropriate to use forecasted data provided by a meteorologist K>
l SH/0/B3/2005/001 Page 6 of 17 4.3.3 IF site meteorology cannot be obtained from meteorological tower systems, refer to Enclosure 5.1 (Meteorology) for alternate methods for obtaining meteorological data.
4.3.4 Enter meteorological data, or "Requery" for automatic meteorological input.
4.3.4.1 IF manual meteorological data entries are-required, use Enclosure 5.1 (Meteorology) as necessary.
- Enter lower wind speed in miles per hour (mph).
- Enter upper wind direction; where wind direction is from North (N=0 degrees).
- Enter Delta temperature gradient (AT) in degrees centigrade (AT = 0C).
- Enter air temperature in degrees centigrade (Temperature in 0 C).
- Enter precipitation occurring (inches per fifteen minute period).
- Mean mixing height (in meters) is computer selected from a table of seasonal afternoon mixing heights for each station.
- Manually overwrite meteorological data or "Requery" for data that is acceptable.
4.3.5 Select the appropriate button for the meteorological data acceptance.
4.3.5.1 IF all of the meteorological data entered or retrieved is correct, click on "Accept".
4.3.5.2 IF new automatic data retrieval is needed, click on "Requery".
4.3.5.3 IF a new time step is needed, click on "Add New Step".
4.3.5.4 IF the meteorological data input needs to be aborted, click on "Cancel" to return to the main menu.
4.4 Select "Enter/Edit Source Term Data".
4.4.1 IF "Manual" was selected in Step 4.2.7, select "OK" to pop-up message: "No automatic monitor data available. Enter data manually."
SHIO/B/2005/oo0 Page 7 of 17 4.4.2 Select the appropriate Accident Type from the list below.
- Consult with ERO personnel (e.g., TSC Operations Engineering and/or EOF Accident Assessment) as necessary.
E the Containment High Range Monitor is greater than 117 Whr, the "gap IF release" accident types (LOCAG, SGTRG, and LOCOG) should be considered.
E the Containment High Range Monitor is greater than the values in the IF Table in Step 4.5.2, the "melt release" accident types (LOCAM, SGTRM, and LOCOM) should be considered.
- "LOCA" - Loss of coolant (normal coolant) - leaks released into containment with those fission products normally found in coolant.
- "LOCAG" - Loss of coolant gap release - coolant leaks into containment of fission products in the fuel pin gap after fuel cladding has failed (e.g.,
core being uncovered, fuel pin heat up, and/or if mechanical fuel pin damage has occurred).
- "LOCAM" - Loss of coolant core melt - coolant leaks released into t.> containment of fission products expected to be released from a core that is partially melted after being uncovered for some period of time.
- "SGTR" - Steam generator tube rupture (normal coolant) - steam generator release accidents with those fission products normally found in coolant.
- "SGTRG" - Steam generator tube rupture gap release - steam generator tube release accidents that release fission products in the fuel pin gap after fuel cladding has failed (e.g., core uncovery or fuel pin heat up and/or after mechanical fuel pin damage has occurred).
- "SGTRM" - Steam generator tube rupture core melt - steam generator tube release accidents that release fission products expected to be released from a core that is partially melted after being uncovered for some period of time.
- "LOCO" - LOCA outside containment (normal coolant) - leaks released directly from containment to outside environment (e.g., Annulus or Auxiliary Building) with fission products normally found in reactor coolant.
SH/0/B12005/001 Page 8 of 17
- "LOCOG" - LOCA outside containment gap release - leaks released directly from containment to outside environment (e.g., Annulus or Auxiliary Building) with fission products in the fuel pin gap after fuel cladding has failed (e.g., core uncovery or fuel pin heat up and/or after mechanical fuel pin damage has occurred).
- "LOCOM" - LOCA outside containment core melt - leaks released directly from containment to outside environment (e.g., Annulus or Auxiliary Building) with fission products expected to be released from a core that is partially melted after being uncovered for some period of time.
- "FUEL" - Fuel handling gap release - fuel pin fission products released from fuel during refueling, or Spent Fuel Pool accident.
- Use consistent Accident Type and identify release path(s) for each fifteen minute time step; changing Accident Type only when reactor and/or plant status indicate conditions degrading to a different accident.
4.4.3 Choose the appropriate NG Method based on the release pathway:
4.4.3.1 IF a steam release is occurring or suspected, refer to Enclosure 5.2 (Steam Source Term Release) for NG Method selection.
4.4.3.2 IF a containment release is occurring or suspected, refer to Enclosure 5.3 (Containment Source Term Release) for NG Method selection.
4.4.3.3 IF a unit vent release is occurring or suspected, refer to Enclosure 5.4 (Unit Vent Source Term Release) for NG Method selection.
4.4.4 Select the appropriate button for the Source Term Data acceptance.
4.4.4.1 IF all of the Source Term Data entered or retrieved is correct, click on "Accept".
4.4.4.2 IF new automatic data retrieval is needed, click on "Requery".
4.4.4.3 IF a new time step is needed, click on "Add New Step".
4.4.4.4 IF the Source Term Data input needs to be aborted, click on "Cancel" to return to the Main Menu.
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SH/O/B/.2005/00 1 Page 9 of 17 K>
4.5 Select "Emergency Classification" from the Raddose 5 main menu.
NOTE: This menu item is used to select the Current Emergency Classification in a drill or accident. Do NOT select a classification based on radiological conditions only.
4.5.1 Select the current Emergency Classification (Unusual Event, Alert, Site Area Emergency, General Emergency) from the menu.
4.5.2 IF General Emergency is chosen, respond to dialog box question: "Is the Fission Product inventory inside containment greater than gap activity?"
IF the Containment High Range Monitor is greater than the values in the table below, answer the question "Yes".
High Range Containment Monitor Reading Time After Shutdown (hours) (EMF 51 ANB or EMF 53 ANB) 0-2 864 R/Hr 2-4 624 RJHr 4-8 450 RIHr
>8 265 RfHr 4.6 Select "Perform Calculations" to calculate Real Time Mode dose results which are displayed on ten-mile map.
4.6.1 Select "Continue" from map display to go to the Real Time Mode Output Menu.
4.6.2 Select applicable real-time mode output options:
4.6.2.1 IF forecasted doses and an Emergency Notification Form is needed at this time, select "Continue Calculations".
4.6.2.2 Other menu items may be selected as follows:
- "Display Grid Receptor Doses" is used to display the Grid Receptor doses.
- "Display Plume Arrival Times" is used to display real-time plume arrival times.
- "Display 2-Mile Map" is used to see real-tine Plume EDE and Adult Thyroid dose rates within two miles of the site.
.I SH/0/B/2005/001 Page 10 of 17
- "Display 10-Mile Map" is used to see real-time Plume EDE and Adult Thyroid dose rates within ten miles of the site.
- "Display 50-Mile Map" is used to see real-time Plume EDE and adult thyroid dose rates within 50 miles of the site.
- "Review GenEmergency PAZ PARs" to display the PAZs that are recommended to'be evacuated.
- "Display Point-of-Interest Doses" is used to see real-time dose rates at any point of interest. This choice may be used to display doserates beyond the 10-mile radius of the site.
- "Display 50-Mile Deposition Data" is used to display the 50-mile deposition data.
- "Display Survey Point Receptors" is used to see real-timze dose rates and accumulated doses for predetermined sample points.
- "Go To Report Menu" is used if output of real-time is desired.
The real-time mode report menu choices are:
- "View Reports" may be selected to view all of the real-tirte reports
- "View Protective Action Zones" may be selected to view the Wind Direction/Affected Zone table.
- "Print Summary Form" may be selected to print the real-time summary report.
NOTE: The real-timze mode RQ Report is available from the "Print Reports and Maps" selection.
This report is used to display the "EPA RQ Fraction" released for each nuclide and a "Sum of the Ratios" for all of the nuclides released
- "Print Reports and Maps" may be selected to print any combination of the available real-lime mode reports.
.i SH/0/B1/2005/00 1 Page 11 of 17 4.7 Select "Perform Forecast" to calculate TEDE and CDE dose rates (mremllhr), and forecasted dose (mrem), for the release duration in Forecast Mode.
4.7.1 IF General Emergency was chosen in Step 4.5.1, the following screen prompt will appear: "General Emergency Classification is chosen. Is the Fission Product inventory inside Containment greater than gap activity?".,
- Answer this prompt the same as was performed in Step 4.5.2.
4.7.2 Select the appropriate Emergency Release Status (e.g., None, Potential, Is Occurring, Has Occurred), using the following logic:
4.7.2.1 "None" - no release of radioactivity generated by tile event and no release expected.
4.7.2.2 "Potential" - radioactivity generated during an event that has potential to be released but is not currently being released.
- Discretionary option for the Emergency Coordinator or the EOF Director.
4.7.2.3 "Is Occurring" - radioactivity generated during an event that is K currently being released through any defined accident pathway, using any of the following indicators:
- EITHER containment particulate, gaseous, iodine monitor readings indicate an increase in activity, OR Containment monitor readings indicate greater than 1.5 R/hr, AND EITHER containment pressure is greater than 0.3 psig, OR An actual containment breach is known to exist.
- Unit vent particulate, gaseous, iodine monitor readings indicate an increase in activity.
- Condenser air ejector exhaust monitor or other alternate means indicate Steam Generator tube leakage.
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SH/0/B/2005/001 Page 12 of 17 K>-
- Confirmed activity in the environment reported by Field Monitoring Team(s).
- Knowledge of the event and the impact on systems operation and resultant release paths.
4.7.2.4 "Has Occurred" - any radioactivity generated during an event that has been released previous to ERO activation that may require offsite agency notification.
4.7.3 Select the appropriate Status of Projected Offsite Dose (e.g., New or Unchanged).
NOTE: 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> is the lower limit allowed as a forecast period and the forecast period must be in increments of 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
4.7.4 Enter a Forecast Period (in hours).
4.7.5 IF all inputs are correct, select "OK".
4.7.6 Select "OK" to the screen prompt "Note: Forecast will use the meteorological K> and source term data from Step 1. Continue?"
NOTE: Forecast Mode doses are calculated using the most current time step and are displayed on ten mile EPZ map.
4.7.7 IF General Emergency was selected in Step 4.5, THEN select "Both PARs" to display the General Emergency Protective Action Recommendations, and the Dose Protective Action Recommendations.
4.7.8 Select "Continue" from map display to go to the Forecast Mode Output Menu.
4.7.9 At the popup dialog box item "Do you want to save PAZs identified in forecast mode for evacuation?", select "Yes".
4.7.10 Select "Go To Report Menu" to go to the Forecast Mode Reporit Options Menu and access the Raddose 5 Green Form.
SHIO/B/2005/001 Page 13 of 17 KJ NOTE: Refer to Step 4.6.2.2 for a description of the other choices on this menu. However, it should be noted that all outputs will consist offorecasreddata instead of real-time data.
4.7.11 Select "Print Green Form + Summary Form" to print the Emergency Notification Form (green sheet) and the Summary Report.
4.7.11.1 Review the dose assessment reports.
4.7.11.2 IF the projected dose OR field measurements at the site boundary is > 5 rem CDE thyroid, notify the TSC Dose Assessors or the EOF RAM, as applicable, to direct the Offsite Agency Communicators to edit the ENF to add the PAR for public use of KI per the applicable procedures:
CNS - RP/O/B/5000/006B Notifications to States and Counties from the Technical Support Center MNS - RP/O/A/5700/018 Notifications to States and Counties from the Technical Support Center K> SR/013/20001004 Notification to States and Counties from the Emergency Operations Facility 4.7.12 Select "Save Green Form Data to Ini File" to transfer the Raddose data to the Electronic Notification Form application.
4.7.13 Other menu items may be selected as follows:
- "View Green Form" is used to display the Green Form report.
- "View Reports" is used to view all reports.
- "Print Green Form" is used to print the Green Form report.
- "Print Summary Form" is used to print the Summary Form report.
- "Print Reports and Maps" 'is used to select any combination of the available reports.
4.7.14 Select "Return' to Output Menu" when done with Forecast Mode reports.
4.7.15 Select "Continue Calculations" to return to the main menu in real-tiue mode.
1
SH/0I13/2005/001 Page 14 of 17 4.7.16 Select "OK" to the Raddose prompt: "You have just completed a forecast.
Remember to check the meteorological and source term data for current information".
4.8 Refer to Enclosure 5.5 (Radiological Emergency Action Levels) and evaluate the Emergency Action Levels (EALs) based on radiological conditions.
4.8.1 Provide EAL radiological assessment classifications to ERO Management in the TSC and/or EOF.
4.9 IF desired, obtain the Self Reading Dosimeter Correction Factor (SRDCF) from the Real-Time Summary Report.
NOTE: Raddose 5 calculates Effective Dose Equivalent (EDE) exposure and provides Self Reading Dosimeter (SRD) correction factor (SRDCF).
SRDcF = TEDE EDE SRDcF = SRD correction factor TEDE = Total Effective Dose Equivalent EDE = Effective Dose Equivalent NOTE: The SRDCF value is based on accident specific source term nuclide(s) and is a calculation of TEDE to EDE ratio at site boundary.
- SRDCF is provided to offsite Emergency Workers during an accident, after a declared General Emergency, and when a release is occurring.
- SRDcF is used as a multiplier of Emergency Worker SRD readings for EPA 400 Manual Of Protective Action Guides And Protective Actions For Nuclear Incidents, "Early Phase" Emergency Worker TEDE estimate.
- Provide the SRDCF to the Field Monitoring Coordinator and the OSC. I
SHIO/B/2005/001 Page 15 of 17 4.10 IF manual completion of the Emergency Notification Form is to be used, provide the Radiological Assessment Manager (RAM), Lead TSC Dose Assessor and/or ERO personnel the following information for each of the Emergency Notification Form line items:
4.10.1 Obtain "Green Form Report" (example shown on Enclosure 5.6)....
4.10.2 Line It 10 - Emergency Release(s); use the guidance in Step 4.7.2.
4.10.3 Line # 11 - Type of Release; check Ground Level release and record Airborne or Liquid release with start time and stop time; if known.
4.10.4 Line # 12 - Release Magnitude in Ci/Sec released.
NOTE: The Normal Operating Limit in the Technical Specifications are: EDE 5.OE-2 mReml/hr, Child Thyroid 1.711 E-l mRem/hr.
4.10.4.1 Select "Above" or "Below" to indicate if the release is above or below the Normal Operating Limits.
- Release Below Normal Operating Limits is radioactivity K> released at any time during an event and/or radioactivity that may have been previously released that is NOT above site boundary normal operating limits.
- Release Above Normal Operating Limits is any radioactivity released during the event and/or any radioactivity previously released that is above normal site boundary operating limits.
4.10.4.2 Record value (in Ci/Sec) for each form of radioactive material released offsite.
- Noble gases
- lodines
- Particulates KJ
SH!/OB12005/001 Page 16 of 17 4.10.5 Line # 13 - Record Estimate of Projected Offsite Dose as "New" or "Unchanged":
- Record projection time of forecast.
- Record estimated duration of release. This value shall be theforecast period used in Step 4.7.4.
E the release is below normal operating limits, as determined in Step IF 4.10.4.1, enter "Not Required" in the TEDE and CDE fields on the Emergency Notification Form.
- IF the release is above normal operating limits, as determined in step 4.10.4.1, record the TEDE and CDE mrem forecasted dose at Site Boundary, 2 miles, 5 miles and at 10 miles.
4.10.6 Line #14 - Record meteorological data.
4.10.6.1 Wind Direction from North where N=Odegrees 4.10.6.2 Wind Speed (miles per hour) 4.10.6.3 Stability Class 4.10.6.4 Precipitation (type) (inches per 15 minute period) 4.10.7 Line #15 - Recommended PAZ protective actions as indicated on the "Green Form Report" (example displayed on Enclosure 5.6).
4.10.7.1 IF the projected dose OR field measurements at the site boundary is > 5 rem CDE thyroid, notify the TSC Dose Assessors or the EOF RAM, as applicable, to direct the Offsite Agency Communicators to edit the ENF to add the PAR for public use of KI per the applicable procedures:
CNS - RP/O/B/50001006B Notifications to States and Counties from the. Technical Support Center MNS - RP/O/A15700/018 Notifications to States and Counties from the Technical Support Center SR/O/B/2000/004 Notification to States and Counties from the Emergency Operations Facility
i SH/IOB/2005/001 Page 17 of 17 K>
4.10.8 Provide Raddose 5 printouts and summary reports to Federal, State and County agencies supporting ERO activation, with approval by lead TSC dose Assessor or EOF RAM.
4.10.9 Retain logs, computer printouts and computer generated dose assessment files, whenever ERO is activated.
- Exercise and Drill records are retained for Emergency Planning disposition.
- 5. Enclosure 5.1 Meteorology 5.2 Steam Source Term Release 5.3 Containment Source Term Release 5.4 Unit Vent Source Term Release 5.5 Radiological Emergency Action Levels 5.6 Raddose 5 Green Form Report To
Enclosure 5.1 SWOH/B/2005/001 Meteorology Page 1 of 2 5.1.1 Meteorological Tower OAC data is normally provided as 15 min. average.
- Use lower tower wind speed (WS) in miles per hour
- Use upper tower wind speed (WS) if lower tower wind speed is not available
- Use upper tower wind direction; in degrees from North (N) = 0°
- Use lower tower wind direction if upper tower wind direction is not available: in degrees from North (N) = 00 5.1.2 IF Meteorological Tower is not available, obtain meteorological information from:
- Duke meteorologist at 8-382-0139 l
- Unaffected plants control room:
CNS - Unit-I 8-831-5345 Unit-2 8-831-5344 MNS - Unit-i 8-8754262 K> Unit-2 8-875-4263
- National Weather Service (NWS) at 1-800-268-7785
- Gastonia Automated Surface Observation System (ASOS) at 704-868-9034 5.1.3 IF meteorological tower temperature gradient (AT0 ) is unknown, use the following default values:
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A Enclosure 5.1 SIuOIB/2005/001 Meteorology Page 2 of 2 K>
5.1.4 Use the following tables to determine stability class when AT data is available:
CNS MNS Stability Class (AT in 'C) (AT in 0C)
A - Extremely Unstable AT * -0.97 AT < -0.95 B - Moderately Unstable -0.97 < AT < -0.87 -0.95 < AT < -0.85 C - Slightly Unstable -0.87 < AT < -0.76 -0.85 < AT * -0.75 D - Neutral -0.76 < AT S -0.25 -0.75 < AT * -0.25 E - Slightly Stable -0.25 < AT < +0.76 -0.25 < AT * +0.75 F - Moderately Stable +0.76 < AT < +2.04 +0.75 < AT* +2.00 G - Extremely Stable +2.04 < AT +2.00 < AT K)
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Enclosure 5.2 SWO/B/2005/001 Steam Source Term Release Page 1 of 4 5.2.1 Determine type of accident, source term release path and EMF monitor method.
5.2.2 Select an Accident Type for an affected release pathway:
- "SGTR" - steam generator tube rupture (normal coolant)
- "SGTRG" - steam generator tube rupture gap release
- "SGTRM" - steam generator tube rupture core melt 5.2.3 Select the appropriate steam line Noble Gas Method as follows:
NOTE: Using the EMF data is the preferred method. Other Noble Gas Methods may be used as l l conditions and data availability warrant.
- IF steam line monitor EMF data is available, use the following guidance for Noble Gas Method selection:
(a) Review the steam line monitor data.
(b) Select appropriate steam line monitor: SG-A, SG-B, SG-C, or SG-D.
(c) Select "Partitioned" or "Not Partitioned" using the guidance below:
(i) IF the steam generator tube leak/break is below the secondary side water level AND the steam generator is NOT overfilled, select "Partitioned".
(ii) E the steam generator leak/break is above the secondary side water level OR the steam generator is overfilled, select "Not Partitioned".
(d) Click on "OK".
(e) IE manual data entry was selected in Step 4.2.7, enter the monitor data and the flow rate.
- IF secondary side steam sample data is available, select GRABSL.
(a) Enter the secondary side steam sample data.
(b) When all data is entered, click on "OK".
(c) Enter the Steam release rate in pounds mass per 15 minutes (LBM/15min).
KJ
Enclosure 5.2 SHIOB/2005/00I Steam Source Term Release Page 2 of 4 KU
- IF field team data is available, select BACKSL (a) Enter the field team data.
(b) Click on "OK" for Raddose to calculate the source term in Ci/sec.
NOTE: Raddose 5 calculates the steam source term release rate for the SG-A, SG-B, SG-C, and SG-D methods as follows:
- Ci/sec is distributed by isotope spectrum based on accident type and time after reactor shutdown
- Raddose 5 calculates the steam source term as follows:
RR = EMFx CFx AJ x LR x (0.41ft3/lbm x 28320 mI/ft3 x IE-6 Ci/gtCi x 1/3600/hr/s)
Where:
RR = release rate activity in Ci/sec K-I CF = steam line radiation monitor Correlation Factor EMF = radiation monitor reading in mR/hr (normally a 15 minute average reading)
AJ = Adjustment Factor (unit-less) based on accident types (SGTR, SGTRG, SGTRM)
LR = Steam release rate from safety valve in pounds mass of steam released through each valve during valve open period (Ibm/IS min), where; default release rate = 5.235E4 Ibm/15 min K>~
Enclosure 5.2 SWO/B/2005/001 Steam Source Term Release Page 3 of 4 NOTE: Raddose 5 calculates steam source term for the GRABSL method as follows:
RR = SLI x LR x (0.4lft3Ilbm x 28320 ml/ft 3 x 1E-6 Ci/fCi x 1/36001hr/s Where:
RR = release rate activity in Ci/sec SLg = secondary grab sample (gCi/ml)
LR = steam release rate from safety valves pounds mass of steam released through the respective valves during the valve open period (Ibmlhr) default release rate = 5.235E4 lbm/15 min NOTE: Raddose calculates the steam source term for the BACKSL method as follows:
RR = Field Measurement Device Reading (mR/hr) x FM Device Correlation (pCi/cc)/(mR/hr)/X/Q(sec/m 3 ) x (1 E-6 Ci/gCi x 1E+6 cc/mr3 )
5.2.4 For Catawba only, use Step 5.2.5 source term assessment worksheet with steam generator tube rupture coincident with loss of offsite power; when the following conditions are present:
- Loss of offsite power and steamline radiation monitor is unavailable
- Primary to secondary coolant leakage is occurring
- Steam source term release is occurring
- Steam generator sample cannot be obtained
- Computer program for calculating steam release is not available K>
I Enclosure 5.2 SH/0I1Or2005/001 Steam Source Term Release Page 4 of 4 5.2.5 (Catawba Only) Source term assessment worksheet with steam generator tube rupture coincident with loss of offsite power for unavailable Steam Line Monitor EMF_ _
Unit Dose Projection based on: I I : Time since trip: hours mm dd yy hh mm INOTE: If EMF53 <5 R/hr, use 5 R/hr.
II EMF53 Reading x Correction Factor x LRps x dT x Lbsmr x INOPEN R/hr x . C.i/ml x ga-x min x lbmr x Ix R/hr min 2400 Ibm sec.
Activity noble Gas x3.785E-3Ci ml x = Ci IiCi gal sec Activity noble Gas x Iodine Ratio LOCA Activity LOCA Iodine 131 Equivalent
__ Ci/sec Activity noble Gas x Iodine Ratio ce melt Activity Core Melt Iodine 131 Equivalent
=_ Ci/sec Where:
K)
LRps = Primary to secondary leak rate in gal/min.
dT = Time that primary to secondary leakage has lasted from the start of the leak to the time of date that the projection is based on, in minutes.
Lbsmr = Mass of steam released from the PORV and/or code safety valves, in Ibm.
VOPEN = Time the valve(s) are open in seconds.
3.785E-3 = I E-6 Ci/gCi x 3.785E3 ml/gal 2400 - Mass of steam in the faulted steam generator; conservative value is 2400 Ibm (mass of steam from SIG nozzle to MSIV)*** If Lbsmr > 2400 Ibm; use 2400 Ibm.
Time since Rx Trip EMF 53 Correction Factor Iodine Ratio LOCA Iodine Ratio Core Melt (hours) **(CF) -_:
Ž0 7.74 E+3 1.52 E-3 4.23 E-3
Ž2 9.82 E+3 1.95 E-3 1.46 E-3
Ž4 9.96 E+3 2.24 E-3 2.21 E-2
Ž8 1.28 E+4 2.63 E-3 4-09 E-2
Ž24 2.15 E+4 3.00 E-3 1.14 E-1 248 3.69 E+4 3.05 E-3 1.78 E-l Emergency l or Drill 0 Prepared by:
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Enclosure 53 SH0/13/2005/001 Containment Source Term Release Page I of 3 5.3.1 Determine type of accident source term release path and EMF monitor method.
5.3.2 Select an Accident Type for an affected release pathway:
- "LOCA"-Loss of Coolant Accident (normal coolant)
- "LOCAG"-Loss of Coolant Accident gap release
- "LOCAM"-Loss of Coolant Accident core melt 5.3.3 Select containment Noble Gas Method as follows:
NOTE: Using the EMF data is the preferred method. Other Noble Gas Methods may be used as conditions and data availability warrant. .
- IF containment sample line is NOT isolated AND containment sample pump is NOT tripped, use the following guidance for Noble Gas Method selection:
(a) IF; EMF 39(L) < IE7 counts per minute (cpm), select "CONL".
(b) IF EMF 39(L)> IE7 cpm AND EMF 39(H)< 1E6 cpm, select "CONH".
K.> (c) IF EMF 39(H) > IE6 cpm, select "CONHH".
- IF containment sample line is isolated OR containment sample pump is tripped, use the following guidance for Noble Gas Method selection:
(a) l containment sample results are available, select"GRABC".
(b) E containment sample results are NOT available, select "CONHH".
5.3.4 IF CONL, OR CONH, OR CONHH was selected in Step 5.3.3, Raddose displays the Containment Bypass Release Pathway screen. Choose the appropriate selections for:
(a) Ice Condenser: "No Recirculation", "Recirculation", or "No Ice" (b) Hold-Up: "<=24 Hours" or ">24 Hours" (c) Spray Status: "On" or "Off" (d) Containment Leak Rate Method: "Containment Pressure and Hole Size" or "Predefined/User Leak Rate" (e) Enter or verify the Containment Pressure K>
Enclosure 53 SHO/B/2005/001 Containment Source Term Release Page 2 of 3 (g) When all inputs on the Containment Bypass Release Pathway screen are correct, click on "OK##
[ NOTE: Containment source term can be calculated using containment EMF readings or l containment samples. Reference 2.2 can be used if no other data is available.
(h) IF "Manual" was selected in Step 4.2.7, enter the monitor reading.
NOTE: Raddose 5 calculates the containment source term for the CONL, CONH, AND CONHH methods as follows:
RR = EMF x CF x AJ x BY x lE-6 Ci/.Ci x 1/3600 hr/sec x LR Where:
RR = release rate activity in Ci/sec EMF = The appropriate EMF reading, in cpm or R/hr, as applicable.
CF = Containment Noble Gas monitor Correlation Factor KJ AJ = Adjustment factors for Iodine and Particulates BY = Containment Bypass Fraction - Fraction of containment leakage of gases from inside containment which bypasses the annulus and auxiliary building and passes directly to the environment where, (default value = 0.07)
LR = Leak Rate of containment air to the annulus or environment (ml/hr) based on one of the following methods:
(a) Based on containment pressure and hole size corresponding to:
- 1. Normal Leakage - 0.3% per day at design pressure (15 psig)
- 2. Small Hole - 100% per day at design pressure (15 psig)
(b) Pre-defined Leak Rate corresponding to:
- 1. Normal Leakage (0.3% per day)
- 2. Small Hole (100% per day)
- 3. Large Hole (100% per hour)
KJ
Enclosure 5.3 SwOI1/B/2005/00 1 Containment Source Term Release Page 3 of 3 NOTE: Raddose 5 calculates the containment source term for the GRABC method as follows:
RR = CONg x BY x LR x 1E-6 Ci/lgCi x 1/3600 hr/sec Where:
CONg= Containment grab sample (ICi/ml)
- All other parameters are the same as defined in the NOTE above.
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Enclosure 5.4 SWO/B/2005/00I Unit Vent Source Term Release Page I of 4 5.4.1 Determine type of accident, source term release pathway, and EMF monitor method.
5.4.2 Enter an accident type for affected release pathway.
- "LOCA" - Loss of Coolant Accident (normal coolant)
- "LOCAG" - Loss of Coolant Accident gap release
- "LOCAM" - Loss of Coolant Accident core melt
- "LOCO" - LOCA outside of containment (normnal coolant)
- "LOCOG" - LOCA outside of containment gap release
- "LOCOM" - LOCA outside of containment core melt
- "SGTR" - Steam Generator Tube Rupture (normal coolant) with Condensate Steam Air Ejector (CSAE) pathway to unit vent
- "SGTRG" - Steam Generator Tube Rupture gap release Condensate Steam Air Ejector (CSAE) pathway to unit vent K> * "SGTRM" - Steam Generator Tube Rupture core melt Condensate Steam Air Ejector (CSAE) pathway to unit vent
- "FUEL" - Fuel handling gas release 5.4.3 Select the appropriate unit vent EMF Noble Gas Method as follows:
NOTE: Using the EMF data is the preferred method. Other Noble Gas Methods may be used as conditions and data availability warrant.
IF Unit Vent EMF. Data is available, AND unit vent sample pump is NOT tripped, use the following guidance for Noble Gas Method selection:
(a) IF EMF 36(L) < I E7 counts per minute (cpm), select "U'VIL" or "UV2L" as appropriate.
(b) IF EMF 36(L) > IE7 cpm AND EMF 36(Hi) < 1E6 cpm, select "UV I H" or "UV2H" as appropriate.
(c) 11; EMF 36(H) > I E6 cpm, select "UV 1HIP or "JV21iH" as appropriate.
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Enclosure 5.4 SH/0/13/2005/001 Unit Vent Source Term Release Page 2 of 4 (d) Select the appropriate response for the Unit Vent Release Pathway Data screen as follows:
(i) Filter Status - "On" or "Off" (ii) Ice Condenser: "No Recirculation", "Recirculation", or "No Ice" (iii) Hold-Up: "< =24 Hours" or ">24 Hours" (iv) Spray Status: "On" or "Off' (v) When all inputs on the Unit Vent Release Pathway screen are correct, click on "OK" (e) IF "Manual" was selected in Step 4.2.7, enter the unit vent monitor reading (f) Verify or enter the unit vent flow rate
- IF Unit Vent EMF Data is NOT available, use one of the following choices for Noble Gas Method selection:
(a) IF Unit Vent Isotopic Sample data is available, select "GRABVI" or "GRABV2" as appropriate.
(i) Enter the grab sample data.
(ii) Click on "OK" for Raddose to calculate the source term in Ci/sec.
NOTE: BACKVI and BACKV2CANNOT be chosen on the first time step.
(b) I Field Team Data is available, select "BACKVI' or "BACKV2" as appropriate.
(i) Enter the field team data.
(ii) Click on "OK" for Raddose to calculate the source term in Ci/sec.
(c) IF Total Source Tern calculations are available, select "DRCTl " or DRCT2" as appropriate.
(i) Enter the Noble Gas, Iodine, and Particulate source term data.
(ii) Click on "OK" for Raddose to calculate the source term in Ci/sec.
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.i Enclosure 5.4 SWO/Br2005/001 Unit Vent Source Term Release Page 3 of 4 K>
- Check unaffected unit vent monitor data.
- IF appropriate, repeat Step 5.4.3 to include source term assessment for unaffected unit.
NOTE: Raddose 5 calculates the unit vent source term for the LVI UVIH, UV1HH, UV2L, UV2H, AND UV2HH methods as follows:
- Ci/sec is distributed by isotope spectrum based on accident type and time after reactor shutdown.
- Raddose 5 calculates unit vent source term as follows:
RR = EMF x CF x AJ x FR x 1E-6 Ci/tCi x 1/60 min/sec x 28320 m O/ft 3 Where:
RR = release rate activity in Ci/sec EMF = Use EMF36L counts per minute (cpm), if reading
- 1E+7 cpm and vetant EMF sample pump is not tripped (UVIL, UV2L)
KJ EMF = Use EMF36H cpm reading if EMF36L is offscale and EMF36H IlE+6 cpm and sample pump is not tripped (UVIH, UV2H)
EMF = Use EMF54 - CNS, EMF36HH - MNS (R/hr) reading if EMF36L and EMF36H are offscale, and/or vent EMF sample pump is tripped (UVIHH, UV2HH)
CF = Unit Vent radiation monitor Noble Gas Correlation Factor AJ = Adjustment Factors for lodines and Particulates for accident types FR = Unit vent flow rate in ft3 per minute, (No default rate); vent flow rate is a manual Raddose 5 input if query data is unavailable K>
.*1 Enclosure 5.4 S'On/B/2005/0o1 Unit Vent Source Term Release Page 4 of 4 NOTE: Raddose 5 calculates the unit vent source term for the GRABVI and GRABV2 methods as follows:
RR = UVg x FR x 1E-6 Ci/,Ci x 1/60 min/sec x 28320 ml/ft 3 Where:
RR = release rate activity in Ci/sec UVg = unit vent grab sample (jiCi/ml)
FR = Unit vent flow rate in ft3 per minute; (No default rate); vent flow rate is a manual Raddose 5 input if queried data is unavailable NOTE: Raddose 5 calculates the source term for the BACKV1, BACKV2 method as follows:
RR = Field Measurement Device Reading (mR/hr) x FM Device Correlation (ttCi/cc)/(mRlhr)/X/Q(seclmn3 ) x (1 E-6 Cilpi.Ci x IE+6 cc/M3 )
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- 1 Enclosure 5.5 Si-/OfB/2005/001 Radiological Emergency Action Levels Page lof I I
5.5.1 Evaluate the Emergency Action Levels (EALs) based on radiological conditions in the affected site's EAL procedure:
CNS - RPIOIA/5000/001 - Classification of Emergency MNS - RPIOIAI5700/000 - Classification of Emergency K>
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Enclosure 5.6 SH/O/B/2005/001 Raddose 5 Green Form Repoit Page I of 2 K)
Catawba Nuclear Station Unit No 1 Dose Assessment RADDOSE-V Version 3.Oc Copyright 2002 Earth Tech Current Date: 12/09/2002 Stl tp #: 1 Current Time: 14:41 Stlap Date: 12/09/2002 Operator: GTJ Stl ep Time: 12:15 FORECAST FOR 4 HOURS ACCIDENT DESCRIPTION: General Emergency has NOT been declared Reactor Shutdown:12/09/2002 1200 hrs Accident lime: 12/09/2002 1200 hrs PATHWAY 1 1.31 E+05 Accident Type: LOCA Flow Rate: ftAmin 1.54E+00 R/hr Noble Gas Method UV1 HH (EMF54) Monitor Reading: (P)
VentCF = 0.328 RELEASE RATES:
Noble Gas Release Rate (Ci/sec): 3.12E+01 Cis Above Normal Operating Limits Iodine Release Rate (CUsec): 4.61 E-02 CVs Particulate Release Rate (Ci/sec): 3.54E-03 CVs ACTUAL, FORECAST AND TOTAL (Forecast e Integrated) DOSES:
Distance TEDE (mrem) Thyroid CDE (mrem)
K) (miles) Actual Forecast Total Actual Forecast Total 0.50 1.67E+01 2.67E+02 2.84E+02 1.71 E+02 2.74E+03 2.91 E+03 1.00 7.71E+00 1.23E+02 1.31E+02 6.46E+01 1.03E+03 1.10E+03 2.00 3.36E+00 5.40E+01 5.74E+01 2.32E+01 3.74E+02 3.97E+02 5.00 O.OOE+00 1.42E+01 1.42E+01 O.00E+00 9.41E+01 9.41E+01 10.00 0.OOE+00 4.79E+00 4.79E+00 0.00E+00 2.81E+O1 2.81E+01 METEOROLOGICAL DATA:
Wind Speed: 9.5 mph (P) Stability Class: D (P)
Wind Direction: From 44.90 deg To 224.90 deg RECOMMENDED PROTECTIVE ACTIONS:
Evacuate: None Shelter: None K)
Enclosure 5.6 SvOI/B/2005/001 Raddose 5 Green Form Repori Page 2 of 2 K>_
Catawba Nuclear Station Unit No 1 Dose Assessment RADDOSE-V Version 3.Oc Copyright 2002 Earth Tech Current Date: 12/09/2002 Step #: 1 Current Time: 14:41 Step Date: 12/09/2002 Operator GTJ Step Time: 12:15
- FORECAST FOR 4 HOURS TOTAL (Forecast + Integrated) DOSES FROM 12/09/2002 12:00 TO 16:15:
Distance Current Dose Rates (mremnhr) Dose (mrem) X/O Thyroid Thyroid (miles) TEDE CDE TEDE CDE (seclm3) 0.50 6.68E+01 6.85E+02 2.84E+02 2.91EE+03 3.55E-05 1.00 3.08E+01 2.59E+02 1.31E+02 1.10E+03 1.34E-05 2.00 1.35E+01 9.35E+01 5.74E+01 3.97E+02 4.85E-06 5.00 3.49E+00 2.35E+01 1.42E+01 9.41E+01 1.22E-06 10.00 1I36E+00 8.03E+00 4.79E+00 2.81E+O1 4.16E-07 DOSE CONVERSION FACTORS: mrem mA^3Ci-hr TEDE: 2.15E+07 PlumeEDE: 8.65E+04 Ground EDE: 7.33E+06 CDE Thyroid: 4.1 8E+08 Inhalation: 1.41 E+07 K) EMERGENCY CLASS:
Total Effective Adult Dose Equivalent Thyroid Site Area Emergency: Yes >= 100 mrem Yes >= 500 mrem General Emergency: No < 1000 mrem No < 5000 mrem PAG Dose Limits: 1 rem 5 rem PAG Exceeded at Site Boundary? No No PAG Distances (miles): N/A N/A MONITOR CORRECTION FACTORS:
Pathway 1 Time Since Trip (Hrs) 0.00 Ice Condenser No Recirc Sprays On Hold-Up Time <=24 hrs Cont Leak Rate Method .....
Cont Leak Type Cont Pressure Cont Leak Rate Cont Bypass Fraction Filters No SG Partitioned Pool Scrubbing Field Measurement Distance Direction Fuel Assembly Age (Days)
(R04-01)
Duke Power Company (1) ID No. S11013/2005/002 PROCEDURE PROCESS RECORD FOR STANDARD PROCEDURES Revision No. 003 PREPARATION (2) Procedure
Title:
Protocol for the Field Monitorinq Coordinator KJ Durina Emeraencv Conditions l
- D (3) Prepared By, ~IAxa1. kX> Date_3 5° -
V (4) Applicable To: 0 ONS ,tA MNS Cf CNS (5) Technical ____
Advisor Gelt0leylaDi (6) Requires Q Yes O No {l Yes O No Yes O No NSD 228 _
Applicability YES New procedure or reissue with major changes Determination NO Reissue with minor changes OR to incorporate previously approved changes (7) Review (QR) By B 4 , By
, Date___________ Dat Date 3/1 ot Cross-Disciplinary By By By Review (QR) NA Date NA Date NA Date Reactivity Mgmt. By By_ By Review (QR) NA Date NAZW Date ;7/,'-t NA44 Date gmt. Involvement By__ By By Review (Ops. Supt.) X NA Date NA (4 Date /otHI NA t%'W Date /I/
(8) Additional By (QA) By (QA) By (QA)
Reviews Date Date Date_
By By. By G1 ,4 Date_________ Date Date, (9) Approved By_ By A By_
Date Date OV-ii-o:'/- Date________
(10) Use Level Reference Usc PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)
(11) Compared with Control Copy Date Compared with Control Copy_ Date Compared with Control Copy Date (12) Date(s) Performed
- Work Order Number (WO#)
COMPLETION (13) Procedure Completion Verification O Yes 0 NA Check lists or blanks properly initialed, signed, dated, or filled in NA, as appropriate?
o Yes 0 NA Required enclosures attached?
O Yes 0 NA Data sheets attached, completed, dated, and signed?
O Yes 0 NA Charts, graphs. etc., attached and properly dated, identified, and marked?
K> O Yes 0 NA Procedure requirements met?
Verified By Date (14) Procedure Completion Approved Date (15) Remarks (attach additional pages, if necessary)
Duke Power Company Procedure No.
KJ Standard Procedure for Catawba and McGuire SIwO/B/2005b002 Nuclear Stations Revision No.
Protocol for the Field Monitoring Coordinator 003 During Emergency Conditions Electronic Reference No.
Reference Use MP0070R4 K)
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.1*
Sa'O/B/2005/002 Page 2 of 8 Protocol for the Field Monitoring Coordinator During Emergency Conditions
- 1. Purpose To describe a systematic field monitoring method for sampling and identifying airborne plumes or liquid effluents in order to obtain field data indicative of the radiation exposure to the general public following an unplanned release of radioactive material.
- 2. References 2.1 Site specific procedures for emergency environmental monitoring:
CNS - HP/OBI/1009/004, Environmental Monitoring for Emergency Conditions Within Ten Mile Radius of CNS MNS - HP/Of13/1009/023, Environmental Monitoring for Emergency Conditions 2.2 EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.3 Site specific emergency phone directories:
CNS - CNS Emergency Phone Directory MNS - RP/O/A/5700/014, Emergency Telephone Directory 2.4 S1OIB/2005/003, Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release
- 3. Limits and Precautions 3.1 Field Monitoring Team environmental sampling performed during emergency conditions does not replace or substitute for normally required environmental monitoring.
3.2 During any drill or emergency, personnel safety and safe operation of the vehicle are of primary concern.
- 4. Procedure 4.1 Field Monitoring Team (FMT) Activation 4.1.1 Consult with the TSC to determine the status and availability of field teams.
4.1.2 IF the site has NOT activated field teams, consult with the Dose Assessors the need for team activation.
SH/0/B/2005/002 Page 3 of 8 4.1.3 Once the Radio Operator has established communications with the FMTs, the Field Monitoring Coordinator shall take control of the teams.
4.1 4 IF emergency conditions dictate, request additional survey vehicles.
4.1.5 IF emergency conditions dictate, request additional field monitoring support from an alternate station.
4.1.6 IF possible, ensure that at least one Field Monitoring Team (FMT) member be from the affected station.
4.1.7 Obtain an Emergency Planning map for the affected station.
4.2 Field Monitoring Team (FMT) Communications 4.2.1 Ensure the EOF Base Radio is set as follows:
- For MNS, Black Box Selector Switch to "A" AND Radio Line Selector to Position "1".
- For CNS, Black Box Selector Switch to "D" AND Radio Line Selector to Position "2".
4.2.2 Establish radio communications with each available field team.
4.2.3 Maintain open radio communications with each FMT.
NOTE: Telephone numbers are displayed in Enclosure 5.2 (Telephone Numbers).
4.2.4 IF radio communications become inoperable, use telephone communications as a back-up.
4.2.5 Provide only pertinent, general information when using the radio.
4.2.6 Communicate over the radio during a drill or exercise by beginning each transmission with "THIS IS A DRILL, THIS IS A DRILL".
NOTE: The phonetic alphabet is displayed on Enclosure 5.5 (Phonetic Alphabet).
4.2.7 Communicate information using the phonetic alphabet.
4.2.8 WHEN using the radio for communications with the FMTs, follow Federal I
Communications Commission (FCC) guidelines at all times.
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SH/0/132005/002 Page 4 of 8 4.3 Locating and Tracking the Plume NOTE: Steps in this section do NOT have to be performed in sequence.
4.3.1 Dispatch FMTs after vehicles and equipment have been confirmed operational.
4.3.2 IF onsite meteorological instruments are not available, consult with the National Weather Service (NWS) in Greenville/Spartanburg.
- The NWS phone numbers are: 1-800-268-7785 or 1-864-879-1085 (unpublished).
4.3.3 Estimate which meteorological sector or sectors appear to be affected by the plume according to predominant wind direction AND wind speed.
NOTE: Major roadways delineate the protective action zones (PAZs) surrounding the plant.
Either all or a portion of a PAZ would be expected to be affected to some degree by radioactivity released from the plant. Major roadways are therefore utilized to provide access to suspected regions (outer edges, leading edge(s), centerline) of the plume as necessary.
- Major roadways on the field monitoring map are identified by numerical designations and responsibility level (federal, state, county, or city) designations.
- Selected roadways on the field monitoring map are identified by a specific name, rather than a numerical responsibility designation.
- Predetermined sampling locations are denoted by a red text oval on the field monitoring map. The sampling point designator indicates the protective action zone the point is in and the mileage from the plant. For example, locations are designated in the format.
S 2 Where:
S = EvacuationZone 10 = Mile Radius 2 = Sample Point #2 4.3.4 Have the FIMTs traverse the appropriate meteorological sector or sectors nearest the station, utilizing major roadways, selected roadways, or predetermined sampling locations, as appropriate.
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SH/0/B/2005/002 Page 5 of 8 4.3.5 Request that the survey teams remain aware of terrain during air sampling or surveying (i.e., wind breaks formed by landscape or vegetation) which could inhibit acquiring a representative sample.
4.3.6 Have the survey vehicles report all dose rates above background.
4.3.7 Periodically request that the field team members report their accwmnulated dose.
4.3.8 Send each FMT to pre-determined sample locations, or other survey area as appropriate.
- Use local landmarks and street names to indicate desired sampling location when a pre-determined location is not available or suitable.
4.3.9 WHEN possible, have the FMTs park their vehicles completely off the road.
4.3.10 Direct the FMTs to use the emergency flashers and the strobe, if available, whenever the vehicle is stopped.
4.3.11 Record each field vehicle's sampling history on Enclosure 5.3, OR in the Field Monitoring Coordinator ERO Facility Log.
K> 4.3.12 Have the FMT obtain beta/gamma measurements and/or air samples.
4.3.13 Request survey teams to report the maximum radiation level and location of the boundaries while enroute AND while at sampling locations.
4.3.14 Request FMTs report the location of plume edges based on instrument readings.
4.3.15 Have the FMT take an Iodine sample WHEN, but not limited to:
- Fuel rod gap activity release has occurred.
- Waste gas decay tank rupture has occurred.
- Any suspected iodine release has occurred.
- The source of release is unknown AND the FMT is in the presence of measurable activity.
4.3.16 Use Enclosure 5.8 (1-131 Dose Calculation Methodology) to convert field team 1-131 concentration to CDE thyroid dose rate.
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Sw/O/B/2005/002 Page 6 of 8 4.3.17 Notify FMTs, as appropriate, of changing plant and meteorological conditions that may have an effect on environmental measurements.
- Record meteorological plant status information communicated to FMTs on Enclosure 5.4.
4.3.18 Notify FMTs of plant status as reported on the most recent Emergiency Notification Form.
4.4 Special Sampling INOTE: Sample locations and sample collection methodologies are described in Reference 2.1. I 4.4.1 WHEN plant conditions are considered to be stabilized, have the field monitoring team perform special sampling. Special sampling may include, but is not limited to:
INOTE: Do NOT take smear samples on automobiles. I
- Smears of surrounding areas (stationary, horizontal surfaces)
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- Vegetation
- Sediment
- Water
- Milk
- Integrated dose over time using TLDs 4.4.2 Communicate to teams to exercise care to prevent sample cross contamination.
4.4.3 Ensure that each FMT include (at minimum) the following information on each sample container:
- Sample location
- Sample reference date and time
- Sample collected by
SHI3O/B2005/002 Page 7 of 8 4.5 Sample Analysis 4.5.1 Direct each FMT to retain the samples for analysis.
4.5.2 Consult with the RPM as to the best sample drop off and storage location.
NOTE: Normally, the samples will be analyzed at the ENRAD Laboratory. However, other laboratories may be used, including MNS, CNS, ONS, or other, as appropriate.
4.5.3 Consult with the RPM and Laboratory Management to make appropriate arrangements for sample transport for analysis.
4.6 FMT Dose Tracking 4.6.1 IF any field team member is likely to receive 5 rem or greater of thyroid dose, refer to Reference 2.4 for the distribution of potassium iodide tablets.
4.6.2 IF conditions are such that any RMT member may receive 500 mrem or greater during the drill or emergency, use Enclosure 5.6 (Field Monitoring Team Radiation Exposure Record) to track the FMT's exposure.
4.6.3 Use Enclosure 5.7 as guidance for dose to workers providing emergency K..> services.
4.7 FMT Turnovcr 4.7.1 Consult with the TSC to establish FMT shift relief as appropriate.
4.7.2 Have the FMTs submit all data sheets to Emergency Planning Coordinator.
4.7.3 Have the FIMT members report to a designated counting facility for a post-job whole body count, as appropriate.
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Sl10n/B/20051002 Page 8 of 8
- 5. Enclosures 5.1 Field Monitoring Vehicle Designations 5.2 Telephone Numbers 5.3 Field Monitoring Survey Data Sheet 5.4 Meteorological Update for Field Monitoring Teams 5.5 Phonetic Alphabet 5.6 Field Monitoring Team Radiation Exposure Record 5.7 Guidance on Dose Limits for Workers Performing Emergency Services 5.8 I-131 Dose Calculation Methodology K)
.i Enclosure 5.1 SHJO/B/2005/002 Field Monitoring Vehicle Designations Page 1 of I K>~
Team Call Signs No. of Members Transportation Sample Van 1 2 Emergency Van Sample Van 2 2 Emergency Van Alpha 2 Station Vehicle Bravo .2 Station Vehicle Charlie 2 Land Vehicle*
Delta 2 Land Vehicle
- IF teams from both sites are being used, the team's call sign shall be designated with the station name (e.g., McGuire Sample Van 1, Catawba Sample Van 2, etc.)
- Form additional teams as necessary.
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I Enclosure 5.2 SWO/1B/2005/002 Telephone Numbers Page 1 of I Field Vehicle I Location Telephone Extension Sample Van 1
.atawba 803-372-9021.
Catawba Sample Van 2 803-372-9022 Catawba Alpha Station Vehicle 803-372-9023 Catawba Bravo Station Vehicle 803-372-9024 McGuire Sample Van 1 980-722-0595 McGuire Sample Van 2 980-722-0597 McGuire Alpha Station Vehicle 980-722-0599 McGuire Bravo Station Vehicle 980-722-0601 Catawba RP Support 8-831-5882 Catawba TSC Dose Assessment 8-831-5881 or 831-8042 FMC at EOF (General Office) 704-382-0735 or 704-382-0736 RP Support (Radio) Catawba TSC 803-831-8182 McGuire TSC Dose Assessment 8-875-4976 Dose Assessment Bridge Line 8-875-4980 K2
- Catawba Emergency Phone Numbers are found in the "CNS Emergency Plone Directory".
- McGuire Emergency Phone Numbers are found in RP/O/A/57001014, Emergency Telephone Directory.
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Enclosure 5.3 SH/OM/B2005/002 Field Monitoring Survey Data Sheet Page l of I K)
Air Instrument Readings mRemlhr Time Team Location .CDE Special Open l Closedl Beta I Gamma Thyroid T e 1 Ta I . Im
_p I . .
II K)
II
Enclosure 5.4 S/OI/B/2005/002 Meteorological Update for Field Page 1 of I Monitoring Teams Date: Time:
Classification:
Wind Speed: mph Wind Direction from: ° Zones Affected:
Information From Emergency Notification Form #
Other:
Date: Time:
Classification:
Wind Speed: mph Wind Direction from: a Zones Affected: --
Information From Emergency Notification Form #_
Other:
Date: Time:
Classification:
Wind Speed: mph Wind Direction from: 0.
Zones Affected:
Information From Emergency Notification Form #_ _
Other:
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Enclosure 5.5 SWO/B/2005/2 Phonetic Alphabet Page I of I A - Alpha B - Bravo C - Charlie D - Delta E - Echo F - Foxtrot G - Golf H - Hotel I - India J - Juliett K - Kilo L - Lima M - Mike N - November O - Oscar P - Papa Q - Quebec R - Romeo S - Sierra T - Tango U - Uniform V - Victor W - Whiskey X - X-ray Y - Yankee Z - Zulu
c C Enclosure 5.6 SHwO/B/2005/002 Field Monitoring Team Radiation Exposure Record Page I of 1 TEAM NAME Sample Van I Sample Van 2 Alpha FMT Bravo FMT Other FMTs Individual's Name TLD #
Time__
Current Deep Dose Equivalent (SRD or ED Reading)
Time__
Subsequent Deep Dose Equivalent (SRD or ED Reading)
Cumulative Deep Dose at Time _ .
Time Subsequent Deep Dose Equivalent (SRD or ED Reading) .
Cumulative Deep Dose at Time .
Total Deep Dose Equivalent For FMT Member (Total Deep Dose Equivalent) X (Committed Dose Equivalent SRD Correction Factor)'
= Total Effective Dose Equivalent .
a SRD Correction Factor is obtained from the Raddose Printout.
Enclosure 5.7 SHWO/Bl/20051002 Guidance on Dose Limits for Workers Page 1 of 1 Performing Emergency Services Dose Limit a Activity Condition (rem) 5 all 10 protecting valuable lower dose not practicable property 25 life saving or lower dose not practicable protection of large populations
>25 life saving or only on a voluntary basis protection of large to persons fully aware of populations the risks involved (see Tables 2-3 and 2-4)
K2 a Sum of external effective dose equivalent and committed effective dose equivalent to nonpregnant adults from exposure and intake during an emergency situation. Workers performing services during emergencies should limit dose to the lens of the eye to three times the listed value and doses to any other organ (including skin and body extremities) to ten times the listed value. These limits apply to all doses from an incident, except those received in unrestricted areas as members of the public.
Source: EPA 400-R-92-001 K)~
A.
Enclosure 5.8 SH/0/3/2005/002 1-131 Dose Calculation Methodology Page I of I K)
- 1. To calculate the CDE Thyroid dose rate from the field team results, use the following formula:
CDE Thyroid (mrem/hr) = jxCi/ml
- 1.3E9 mre/ hr Where:
gCi/ml = I-131 concentration from field team air sample results 1.3E9 = Dose conversion factor, 1-131 conc. (pCi/ml) to CDE Thyroid (mrem/hr) per EPA-400-R-922-001, Table 5-2
- 2. To calculate the expected I-131 concentration (gCi/ml) from a Raddose calculated CDE thyroid dose rate (mremlhr), use the following formula:
1-131 tCmI = CDE Thyroid (mrem/hr) 13 mrem/hr 1.3E9 tlCi / ml K) Where:
CDE thyroid (mrem/hr) from the Raddose Report 1.3E9 = Dose conversion factor, 1-131 conc. (ItCi/ml) to CDE Thyroid (mremlhr) per EPA400-R-922-001, Table 5-2