ML021430386
| ML021430386 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/15/2002 |
| From: | Watts R Rochester Gas & Electric Corp |
| To: | Clark R Document Control Desk, NRC/NRR/DLPM/LPD1 |
| References | |
| Download: ML021430386 (165) | |
Text
l A Subsidiary of RGS Energy Group, Inc.
ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE, ROCHESTER, N.Y 14649-0001
- 716 546-2700 www.rge.com May 15, 2002 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Robert Clark (Mail Stop O-8-E9)
Project Directorate I-1
Subject:
Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:
In accordance with 10 CFR 50.4(b)(5), enclosed are revisions to Ginna Station Emergency Plan Implementing Procedures (EPIP).
We have determined, per the requirements of 10 CFR 50.54(q), that these procedure changes do not decrease the effectiveness of our Nuclear Emergency Response Plan.
Very truly yours, Richard J. Watts Manager, Nuclear Training Department Enclosures xc: USNRC Region 1 (2 copies of letter and 2 copies of each procedure)
Resident Inspector, Ginna Station (1 copy of letter and 1 copy of each procedure)
RG&E Nuclear Safety and Licensing (1 copy of letter)
Dr. Robert C. Mecredy (2 copies of letter only)
PSP/jtw
-ACDL+5
U.S. Nuclear Regulatory Commission May 15, 2002 Page 2 of 2 PROCEDURE REVISION NUMBER EPIP 1-0 28 EPIP 1-11 26 EPIP 2-5 14 EPIP 2-9 5 EPIP 2-11 19 EPIP 2-12 22 EPIP 2-18 14
I 05/14/02 PAGE: 1 REPORT NO. 01 GINNA NUCLEAR POWER PLANT REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PREPIP EMERGENCY PLAN IMPLEMENTING PROCEDURE STATUS: EF 5 YEARS ONLY:
PARAMETERS: DOC TYPES - PREPIP EFFECT LAST NEXT PROCEDURE DATE REVIEW REVIEW ST REV NUMBER PROCEDURE TITLE 028 05/15/02 05/15/02 05/15/07 EF EPIP-1-0 GINNA STATION EVENT EVALUATION AND CLASSIFICATION 003 11/02/01 11/02/01 11/02/06 EF EPIP-1-1 UNUSUAL EVENT 004 11/02/01 11/02/01 11/02/06 EF EPIP-1-2 ALERT 005 12/09/96 01/23/98 01/20/03 EF EPIP-1-3 SITE AREA EMERGENCY 005 11/02/01 11/02/01 11/02/06 EF EPIP-1-4 GENERAL EMERGENCY 049 04/10/02 04/10/02 04/10/07 EF EPIP-1-5 NOTIFICATIONS 013 12/20/01 12/20/01 12/20/06 EF EPIP-1-6 SITE EVACUATION 009 11/02/01 11/02/01 11/02/06 EF EPIP-1-7 ACCOUNTABILITY OF PERSONNEL 005 12/20/01 12/20/01 12/20/06 EF EPIP-1-8 SEARCH AND RESCUE OPERATION 021 12/20/01 12/20/01 12/20/06 EF EPIP-1-9 TECHNICAL SUPPORT CENTER ACTIVATION 010 07/25/00 07/25/00 07/25/05 EF OPERATIONAL SUPPORT CENTER (OSC) ACTIVATION EPIP-1-10 026 05/15/02 05/15/02 05/15/07 EF EPIP-1-11 SURVEY CENTER ACTIVATION 009 12/20/01 12/20/01 12/20/06 EF REPAIR AND CORRECTIVE ACTION GUIDELINES DURING EMERGENCY SITUATIONS EPIP-1-12 003 08/04/95 01/23/98 01/23/03 EF EPIP-1-13 LOCAL RADIATION EMERGENCY 005 04/24/96 03/03/99 03/03/04 EF EPIP-1-15 USE OF THE HEALTH PHYSICS NETWORK HPN 004 02/13/98 02/13/98 02/13/03 EF RADIOACTIVE LIQUID RELEASE TO LAKE ONTARIO OR DEER CREEK EPIP-1-16 002 06/21/00 06/21/00 06/21/05 EF EPIP-1-17 PLANNING FOR ADVERSE WEATHER 002 04/24/02 04/24/02 04/24/07 EF EPIP-1-18 DISCRETIONARY ACTIONS FOR EMERGENCY CONDITIONS 019 06/04/01 06/04/01 06/04/06 EF EPIP-2-1 PROTECTIVE ACTION RECOMMENDATIONS 011 09/28/01 09/28/01 09/28/06 EF THEIR USE IN EMERGENCY EPIP-2-2 OBTAINING METEOROLOGICAL DATA AND FORECASTS AND DOSE ASSESSMENT 014 09/28/01 09/28/01 09/28/06 EF EPIP-2-3 EMERGENCY RELEASE RATE DETERMINATION 013 07/20/01 07/20/01 07/20/06 EF EMERGENCY DOSE PROJECTIONS - MANUAL METHOD EPIP-2-4 011 06/21/00 06/21/00 06/21/05 EF EMERGENCY DOSE PROJECTIONS - MIDAS PROGRAM EPIP-2-6 010 10/23/00 10/23/00 10/23/05 EF EPIP-2-7 MANAGEMENT OF EMERGENCY SURVEY TEAMS
GINNA NUCLEAR POWER PLANT 05/14/02 PAGE: 2 REPORT NO. 01 PROCEDURES INDEX REPORT: NPSP0200 EMERGENCY PLAN IMPLEMENTING PROCEDURE DOC TYPE: PREPIP STATUS: EF 5 YEARS ONLY:
PARAMETERS: DOC TYPESS - PREPIP EFFECT LAST NEXT PROCEDURE DATE REVIEW REVIEW REV ST NUMBER PROCEDURE TITLE 05/16/00 05/16/00 05/16/05 EF OF EMERGENCY RADIATION EXPOSURE 005 EPIP-2-8 VOLUNTARY ACCEPTANCE 05/15/02 05/15/02 05/06/07 EF IODIDE (KI) 005 EPIP-2-9 ADMINISTRATION OF POTASSIUM 01/16/97 01/16/97 01/16/02 EF SURVEYS 003 EPIP-2-10 INPLANT RADIATION 05/15/02 05/15/02 05/15/07 EF 019 EPIP-2-11 ONSITE SURVEYS 05/15/02 05/15/02 05/15/07 EF 022 EPIP-2-12 OFFSITE SURVEYS 07/27/99 07/27/99 07/27/04 EF 008 EPIP-2-13 IODINE AND PARTICULATE ACTIVITY DETERMINATION FROM AIR SAMPLES 12/04/00 12/04/00 12/04/05 EF 014 EPIP-2-14 POST PLUME ENVIRONMENTAL SAMPLING 02/06/02 02/06/02 02/06/07 EF 005 EPIP-2-15 POST PLUME EVALUATION OF OFFSITE DOSES DUE TO DEPOSITION 08/31/01 08/31/01 08/31/06 EF 011 EPIP-2-16 CORE DAMAGE ESTIMATION 03/01/02 03/01/02 03/01/07 EF DOSE ESTIMATES 007 EPIP-2-17 HYPOTHETICAL (PRE-RELEASE) 05/15/02 05/15/02 05/15/02 EF 014 EPIP-2-18 CONTROL ROOM DOSE ASSESSMENT 08/31/01 08/31/01 08/31/06 EF (EOF) ACTIVATION AND OPERATIONS 017 EPIP-3-1 EMERGENCY OPERATIONS FACILITY 03/12/01 03/12/01 03/12/06 EF (ESC) 009 EPIP-3-2 ENGINEERING SUPPORT CENTER 12/20/01 12/20/01 12/20/06 EF 008 EPIP-3-3 IMMEDIATE ENTRY 03/12/01 03/12/01 03/12/06 EF 008 EPIP-3-4 EMERGENCY TERMINATION AND RECOVERY 11/16/99 11/16/99 11/16/04 EF 009 EPIP-3-7 SECURITY DURING EMERGENCIES 02/13/98 02/13/98 02/13/03 EF 006 EPIP-4-1 PUBLIC INFORMATION RESPONSE TO AN UNUSUAL EVENT 03/01/02 03/01/02 03/01/07 EF SIRENS 009 EPIP-4-3 ACCIDENTAL ACTIVATION OF GINNA EMERGENCY NOTIFICATION SYSTEM 08/31/01 08/31/01 08/31/06 EF 009 EPIP-4-6 JOINT EMERGENCY NEWS CENTER ACTIVATION 03/01/02 03/01/02 03/01/07 EF STAFFING 019 EPIP-4-7 PUBLIC INFORMATION ORGANIZATION 04/24/02 04/24/02 04/24/07 EF PERIODIC INVENTORY 024 EPIP-5-1 OFFSITE EMERGENCY RESPONSE FACILITIES AND EQUIPMENT CHECKS AND TESTS 027 04/24/02 04/24/02 04/24/07 EF PERIODIC INVENTORY EPIP-5-2 ONSITE EMERGENCY RESPONSE FACILITIES AND EQUIPMENT CHECKS AND TESTS 08/31/01 08/31/01 08/31/06 EF 013 EPIP-5-5 CONDUCT OF DRILLS AND EXERCISES
REPORT NO. 01 GINNA NUCLEAR POWER PLANT 05/14/02 PAGE: 3 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PREPIP EMERGENCY PLAN IMPLEMENTING PROCEDURE PARAMETERS: DOC TYPES - PREPIP STATUS: EF 5 YEARS ONLY:
PROCEDURE EFFECT LAST NEXT REV DATE REVIEW REVIEW ST NUMBER PROCEDURE TITLE (NERP) 004 05/28/99 05/28/99 05/28/04 EF EPIP-5-6 ANNUAL REVIEW OF NUCLEAR EMERGENCY RESPONSE PLAN 035 04/24/02 04/24/02 04/24/07 EF EPIP-5-7 EMERGENCY ORGANIZATION TELEPHONE NUMBER 006 05/28/99 05/28/99 05/28/04 EF EPIP-5-9 TESTING THE OFF HOURS CALL-IN PROCEDURE AND QUARTERLY CHECK EPIP-5-10 EMERGENCY RESPONSE DATA SYSTEM (ERDS) 006 03/28/02 03/28/02 03/28/07 EF "NERP GINNA STATION NUCLEAR EMERGENCY RESPONSE PLAN 020 03/21/01 03/21/01 12/09/04 EF "TOTAL FOR PREPIP 52
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 25 PROCEDURE NO. EPIP 1-0 REV. NO. 28 GINNA STATION EVENT EVALUATION AND CLASSIFICATION TECHNICAL REVIEW REtPONSI.BLE AGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
THIS PROCEDURE CONTAINS 41 PAGES
EPIP 1-0 GINNA STATION EVENT EVALUATION AND CLASSIFICATION
1.0 PURPOSE
1.1 The purpose of this procedure is to provide guidance to personnel in evaluating situations which may require activation of the Nuclear Emergency Response Ian and direct them to appropriate implementing procedures. Prompt recognition and classification is necessary to ensure the timely activation of support functions and notification of offsite organizations.
2.0 RESPONSIBILITY
2.1 The Shift Supervisor/Emergency Coordinator (SS/EC) is responsible for initiating this procedure.
2.2 Once the EOF assumes command and control of the emergency, the EOF/Recovery Manager becomes responsible for continuing this procedure.
3.0 REFERENCES
3.1 Developmental References 3.1.1 10CFR50 Appendix E 3.1.2 NUREG-0654 3.1.3 NUREG-0696 3.1.4 Nuclear Emergency Response Plan.
3.1.5 NUMARC Methodology for Development of Emergency Action Levels (NESP 007).
I 3.1.6 R.E. Ginna EAL Technical Basis Revision 28 3.2 Implementing References 3.2.1 ER-SC.4, Earthquake Emergency Plan.
3.2.2 TEG-2.0, Response Spectrum Calculation.
3.2.3 TEG-2.1, Safe Shutdown Earthquake (SSE) & Operating Basis Earthquake (OBE) Exceedence Determination.
4.0 PRECAUTIONS
4.1 For emergency events involving the Emergency Operating Procedures, classification should only be made after the diagnostic steps of E-0 have been completed.
4.2 In the event that multiple "Initiating Conditions" are identified, the SS/EC shall review each condition and classify according to the highest Emergency Classification Level obtained.
4.3 During any event, the entire procedure should be reviewed for possible reclassification of the event.
4.4 See Definitions (Attachment 2) for terms used in this procedure.
4.5 Any time a current set of conditions is identified which requires an Emergency Classification, the event shall be classified and declared, even if the condition identified is quickly corrected.
4.5.1 Conditions which depend on delayed evaluation results, i.e., chemistry, RP analysis, etc., shall be classified and declared as soon as the results are known.
5.0 PREREQUISITES
5.1 Entry to this procedure may be directed by various other plant procedures or at the discretion of the SS/EC.
6.0 ACTIONS
6.1 In the event of an abnormal condition the Control Room Personnel will:
6.1.1 Perform the immediate responses defined in the appropriate plant procedures.
6.1.2 Identify the initiating conditions using either the guidelines of the EAL wallchart or Attachment 1 of this procedure.
6.1.3 Implement applicable Emergency Plan procedures based on Appendix guidelines.
6.1.3.1 EPIP 1-4, General Emergency 6.1.3.2 EPIP 1-3,Site Area Emergency 6.1.3.3 EPIP 1-2, Alert 6.1.3.4 EPIP 1-1, Unusual Event
6.2 Periodically re-evaluate the condition after initial classification of accident using the EAL wall chart or Attachment 1.
6.3 At the conclusion of the event, refer to EPIP 3-4, Emergency Termination and Recovery.
6.4 Any time previous initiating conditions are identified that would have warranted an Emergency Classification but they are no longer in effect at the time of identification, and do not require further evaluation or analysis, the event will be classified, but not declared.
6.4.1 Conditions which are corrected, but may require further safety evaluation or analysis, will be classified and declared.
6.4.2 The NRC will be notified any time an event is classified. This will be made by means of the NRC Emergency Notification System (ENS) phone using procedure 0-9.3 "NRC Immediate Notification".
6.4.3 The Plant Manager and Corporate Nuclear Emergency Planner (or their alternates) shall also be informed of this notification as soon as possible for notifications to Wayne County, Monroe County and New York State. For these notifications, there is no 15 minute requirement.
7.0 ATTACHMENTS
- 1. Detailed Accident Classification
- 2. Definitions
- 3. Barrier loss/potential loss
EPIP 1-0:4 EPIP 1-0 EMERGENCY ACTION LEVELS (EALS)
INDEX 5.0 RADIOACTIVITY RELEASE/ AREA RADIATION 1.0 CRITICAL SAFETY FUNCTION STATUS TREES (CSFST) 5.1 Effluent Monitors 1.1 Sub-criticality CSFST Status 5.2 Dose Projections/ Environmental Measurements 1.2 Core Cooling CSFST Status 5.3 Area Radiation Levels 1.3 Heat Sink CSFST Status 1.4 Integrity CSFST Status 6.0 ELECTRICAL FAILURES 1.5 Containment CSFST Status 6.1 Loss of AC Power Sources 6.2 Loss of DC Power Sources 2.0 REACTOR FUEL 7.0 EQUIPMENT FAILURES 2.1 Coolant Activity 7.1 Technical Specification Requirements 2.2 Failed Fuel Detectors 7.2 Safety System Failures 2.3 Containment Radiation 7.3 Loss of Indications/ Alarms/ Communication Capability 2.4 (6) Refueling Accidents 3.0 REACTOR COOLANT SYSTEM (RCS) 8.0 HAZARDS 8.1 Security Threats 3.1 RCS Leakage 8.2 Fire 3.2 Primary to Secondary Leakage 3.3 RCS Subcooling 8.3 Man-Made Events 8.4 Natural Events 4.0 CONTAINMENT 9.0 OTHER 4.1 Containment Integrity Status 4.2 Steam Generator Tube Rupture 4.3 Combustible Gas Concentrations NOTE: Changes to this attachment are required to be reflected on the EAL wall chart.
Attachment 1
EPIP 1-0:5 1.0 CRITICAL SAFETY FUNCTION STATUS TREES STATUS 1.1 Sub-criticality CSFST Status GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 1.1.3 1.1.2 1.1.1 RED path in F-0.1, RED path in F-0.1, Any failure of an automatic SUB-CRITICALITY SUB-CRITICALITY trip signal to reduce power AND Mode Applicability: range <5%
Actual or imminent entry into - (1) Power Operations AND either: - (2) Startup Manual trip is successful.
- RED path in F-0.2, CORE - (3) Hot Shutdown Mode Applicability:
COOLING -(1) Power Operations OR - (2) Startup
- RED path in F-0.3, HEAT - (3) Hot Shutdown SINK Mode Applicability
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown Attachment 1
EPIP 1-0:6 1.2 Core Cooling CSFST Status SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 1.2.2 1.2.1 RED path in F-0.2, ORANGE or RED path in CORE COOLING F-0.2, CORE COOLING AND Mode Appicoability:
Functional restoration - (1) Power Operations procedures not effective - (2) Startup within 15 minutes. - (3) Hot Shutdown Mode Applicability: - (4) Hot Standby
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby I 1.3 Heat Sink CSFST Status SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 1.3.1 RED path in F-0.3, HEAT SINK Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby __III Attachment 1
EPIP 1-0:7 1.4 Integrity CSFST Status SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-4 1.4.1 RED path on F-0.4, INTEGRITY Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby 1.5 Containment CSFST Status SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 1.5.1 RED path on F-0.5, CONTAINMENT resulting from loss of reactor coolant Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
EPIP 1-0:8 2.0 REACTOR FUEL 2.1 Coolant Activity SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-4 2.1.3 2.1.2 2.1.1 Coolant sample activity Coolant sample activity Coolant sample activity:
>300 PCi/gm of 1-131 >300 gCi/gm of 1-131 >100% of 1O0/E-Bar gCi/gm equivalent equivalent, total specific activity AND Mode Applicability: OR Any of the following: - (1) Power Operations >1.0 tiCi/gm 1-131
- RED path on F-0.4, - (2) Startup equivalent and entry into INTEGRITY - (3) Hot Shutdown conditions of Tech. Spec.
- Primary system leakage - (4) Hot Standby section 3.4.16.b.
>46 gpm Mode Applicability:
- RCS subcooling <EOP - (1) Power Operations figure MIN SUBCOOLING - (2) Startup due to RCS leakage - (3) Hot Shutdown
- Containment radiation - (4) Hot Standby monitor R-29/30 reading
>1 OR/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
EPIP 1-0:9 2.2 Failed Fuel Detectors GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 2.2.3 2.2.2 2.2.1 Letdown line monitor R-9 Letdown line monitor R-9 Letdown line monitor R-9
>10R/hr >1 OR/hr. >2R/hr AND Tave >500°F AND Mode Applicability: Mode Applicability:
any of the following: - (1) Power Operations - (1) Power Operations
- RED path on F-0.4, - (2) Startup - (2) Startup INTEGRITY - (3) Hot Shutdown - (3) Hot Shutdown
- Primary system leakage - (4) Hot Standby
>46gpm
- RCS subcooling <EOP figure MIN SUBCOOLING due to RCS leakage
- Containment radiation monitor R-29/30 reading
>10R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
EPIP 1-0:10 2.3 Containment Radiation SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 2.3.3 2.3.2 2.3.1 Containment radiation Containment radiation Containment radiation monitor R-29/30 reading monitor R-29/30 reading monitor R-29/30 reading
>1000R/hr >100R/hr >1 OR/hr due to RCS leakage.
Mode Applicability: Mode Applicability: Mode Applicability:
- (1) Power Operations - (1) Power Operations - (1) Power Operations
- (2) Startup - (2) Startup - (2) Startup
- (3) Hot Shutdown - (3) Hot Shutdown - (3) Hot Shutdown
- (4) Hot Standby - (4) Hot Standby - (4) Hot Standby Attachment 1
EPIP 1-0:11 2.4 Refueling Accidents or Other Radiation Monitors GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 2.4.2 2.4.1 Confirmed sustained Spent fuel pool ( reactor cavity alarm on any of the during Refueling) water level following radiation cannot be restored and monitors resulting from maintained above the spent fuel an uncontrolled fuel pool low water level alarm setpoint handling process. Mode Applicability:
- R-2 Containment Area - All Monitor
- R-5 Spent Fuel Pit
- R-12 Containment Noble Gas Mode Applicability:
- All 2.4.3 Report of visual observation of irradiated fuel uncovered.
Mode Applicability:
-All Attachment 1
EPIP 1-0:12 3.0 REACTOR COOLANT SYSTEM 3.1 RCS Leakage ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 3.1.2 3.1.1 3.1.3 RVLIS cannot be maintained Primary system leakage Unidentified or pressure
>77% with no RCPs running >46gpm boundary leakage OR Mode Applicability: greater than 1Ogpm
- (1) Power Operations OR With the Reactor Vessel head removed, it - (2) Startup Identified leakage greater is reported that water - (3) Hot Shutdown than 25gpm level in the Reactor - (4) Hot Standby Mode Applicability:
Vessel is dropping in an - (1) Power Operations uncontrolled manner and - (2) Startup core uncovery is likely - (3) Hot Shutdown Mode Applicability: - (4) Hot Standby
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby
- (5) Cold Shutdown
- (6) Refueling Attachment 1
EPIP 1-0:13
's') Drmrij tn eirnnrIRrv Le3kaae GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 13.4.
3.2.2 Unisolable release of Unisolable release of secondary side to atmosphere secondary side to (See 3.1.2 above) with primary to secondary atmosphere with primary leakage greater than to secondary leakage 0.1gpm in the affected S/G
>46 gpm.
Mode Applicability:
Mode Applicability:
- (1) Power Operations
- (1) Power Operations
- (2) Startup
- (2) Startup
- (3) Hot Shutdown
- (3) Hot Shutdown
- (4) Hot Standby
- (4) Hot Standby 3.2.3 Unisolable release of secondary side to atmosphere with primary to secondary leakage >0.1 gpm in the affected AND EITHER
- Coolant activity
>300 giCi/gm of 1-131 equivalent OR
- Letdown line monitor R-9
>10 R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby I
Attachment 1
EPIP 1-0:14 3.3 RCS Subcooling ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 3.3.1 RCS subcooling <EOP figure MIN SUBCOOLING due to RCS leakage Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
EPIP 1-0:15 4.0 CONTAINMENT 4_1 Cnnt~inment Intearitv Status GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 4.1.4 4.1.2 4.1.1 Safety injection signal due to Rapid uncontrolled Both doors open on LOCA with less than decrease in containment containment airlock minimum operable pressure following initial OR containment heat increase due to LOCA. Inability to close containment removal equipment of OR pressure relief or purge valves Loss of primary coolant which results in a radiological RECIRC SPRAY inside containment with release pathway to the CNMT FANS PUMPS containment pressure or environment PRESS OPER REQ'D sump level response not OR
<28 psig 2 N/A consistent with LOCA Cl or CVI valve(s) not closed
>_28 psig 2 1 conditions. when required which results in
<2 2 Mode Applicability: a radiological release pathway AND - (1) Power Operations to the environment one or more of the following - (2) Startup OR fuel clad loss indicators: - (3) Hot Shutdown Rapid uncontrolled pressure
- Coolant activity >300 gCi/gm - (4) Hot Standby decrease following initial of 1-131 equivalent (Continued on next page) increase due to steam line
- Containment radiation break.
monitor (R-29/30) reading Mode Awplicability:
>100R/hr - (1) Power Operations
- Letdown monitor R-9 reading - (2) Startup
>1 OR/hr - (3) Hot Shutdown
- RED path in F-0.2, CORE - (4) Hot Standby COOLING Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby (Continued on next page)
_______________________ A. 1. 4 Attachment'
EPIP 1-0:16 4.1 Containment Integrity Status SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 1 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 4.1.5 4.1.3 EITHER EITHER:
Rapid uncontrolled decrease CI or CVI valve(s) not in containment pressure closed when required following initial increase due to following confirmed LOCA LOCA OR OR Loss of primary coolant inside Inability to isolate any primary containment with containment system discharging outside pressure or sump level containment AND response not consistent with LOCA conditions Radiological release pathway AND to the environment exists as a one or more of the following result.
fuel clad damage indicators: Mode ARplicability:
- ORANGE or RED path in - (1) Power Operations F-0.2, CORE COOLING - (2) Startup
- RED path in F-0.3, HEAT - (3) Hot Shutdown SINK - (4) Hot Standby
- Coolant activity
>3001g Ci/gm of 1-131 equivalent
- Containment radiation monitor R-29/R-30 reading
>100R/hr
- Letdown line monitor R-9 reading >10R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby (Continued on next page) I______________ 1 Afteho-Mant I hm~I Aff~e
EPIP 1-0:17 4.1 Containment Integrity Status SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 4.1.6 EITHER Cl or CVI valve(s) not closed when required following confirmed LOCA OR Inability to isolate any primary system discharging outside containment AND Radiological release pathway to environment exists as a result AND one or more of the following fuel clad damage indicators:
- ORANGE or RED path in F-0.2, CORE COOLING
- RED path in F-0.3, HEAT SINK
- Coolant activity
>300g Ci/gm of 1-131 equivalent
- Containment radiation monitor reading >100R/hr
- Letdown monitor R-9 reading >10R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4)
Hot Standbyq ___________________________________________ .1 I Attachment 1
EPIP 1-0:18 4.2 Steam Generator Tube Rupture with Secondary Release ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 4.2.2 4.2.1 Unisolable secondary side line Unisolable secondary side line break with S/G tube rupture as break with S/G tube rupture as identified in E-3 "Steam identified in E-3 "Steam Generator Tube Rupture". Generator Tube Rupture" AND Mode Applicability:
one or more of the following - (1) Power Operations fuel clad damage indicators: - (2) Startup
- ORANGE or RED path in - (3) Hot Shutdown
- (4) Hot Standby F-0.2, CORE COOLING
- RED path in F-0.3, HEAT SINK
- Coolant activity
>300 gCi/gm of 1-131 equivalent
- Containment radiation monitor R-29/30 reading
>1OOR/hr
- Letdown monitor R-9 reading >10R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
EPIP 1-0:19 4.3 Combustible Gas Concentrations GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 4.3.1
>4% hydrogen concentration in containment Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
EPIP 1-0:20 5.0 RADIOACTIVITY RELEASE/ AREA RADIATION S.... iB 4.
5.1 tlTuefll Moi torsIUI I-- CTFIT I.
U U. U. L V
___________________I_ l~ t A II 1FA vL UI II VLL GENERAL EMERGENCY Nl I t.- /A1'I_./- ClVIlr"n L. l'- DDC'C'IEfl TC'I FPIP 1-2 PROCEED TO EPIP 1-4 I PROCEED PKUULL)-Cr~I-)
T , TnPI -IRCEDTI r, 1Pr1
.1 .4 P1 5.1.3 5.1.2 I-,, I 1 5.1.4 A valid reading on one or A valid reading on one or more A valid reading on one or more of the following monitors for A valid reading on one or more more of the following monitors of the following monitors for of the following monitors for >60 minutes unless sample for >15 minutes
>15 minutes
>15 minutes analysis can confirm release
- R12A7 6.OOE+0 gCi/cc - R12A7 6.OOE-1 ltCi/cc rates are less than two times
- R12A7 6.00E+1 ý,Ci/cc - R14A7 5.33E-2 [LCi/cc
- R14A7 5.33E-1 pCi/cc release rate limits within the 60
- R14A7 5.33E0 VCi/cc - R15A7 1.15E+-0 pCi/cc minute time limit.
- R15A9 1.15E+1 pCi/cc
- R15A9 1.15E+2 pCi/cc - R18 Offscale High with no - R1 11.72E5 cpm during
- R31/32 reading with the - R31/32 reading with the isolation containment purge following condition:
following condition: - R20A Offscale High - R12 7.80E6 cpm during 1 ARV 1.90E+2 mR/hr 1 A RV 1.90E+1 mR/hr 1 Safety 9.51 E0 mR/hr - R20B Offscale High containment purge 1 Safety 9.51 E+1 mR/hr - R21 Offscale High with no - R13 2.20E4 cpm 2 Safeties 4.76E0 mR/hr 2 Safeties 4.76E+1 mR/hr isolation - R14 6.40E5 cpm 3 Safeties 3.17E+1 mR/hr 3 Safeties 3.17E0 mR/hr
- R22 Offscale High with no - R15 2.94E5 cpm 4 Safeties 2.38E+1 mR/hr 4 Safeties 2.38E0 mR/hr unless dose assessment can isolation - R18 3.60E5 cpm with no unless dose assessment can - R31/32 reading with the isolation confirm releases at the site confirm releases at the site bou ndary are below the following condition: - R20A 4.08E4 cpm boundary are below the 1 ARV 1.90E0 mR/hr - R20B 5.20E3 cpm following within the 15 minute following within the 15 minute limit 1 Safety 9.51 E-1 mR/hr - R21 5.00E4 cpm with no limit 2 Safeties 4.76E-1 mR/hr isolation
- 500 mR CDE thyroid 3 Safeties 3.17E-1 mR/hr - R22 9.20E4 cpm with no
- 5000 mR CDE thyroid 4 Safeties 2.38E-1 mR/hr isolation
- 1000 mR/hr external exposure - 100 mR/hr external exposure rate unless dose assessment can - R31/32 reading 0.2 mR/hr rate confirm releases at the site with 1 ARV or 1 Safety open.
- 5000 mR/hr thyroid exposure - 500 mR/hr thyroid exposure rate for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of inhalation boundary are below Mode Applicability:
for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of inhalation - 10 mR TEDE or - All Mode Applicability: Mode Applicability:
- All - 10 mR/hr external exposure
- All rate within the 15 minute limit Mode Applicability:
- All
_____________________ ~I_
I _ _ _ _ _ _ _ _ _ _
Attachment 1
EPIP 1-0:21 5.2 Dose Projections/ Environmental Measurements/Release Rates GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT 1 PROCEED TO EPIP 1-3 1 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 5.2.5 5.2.4 5.2.2 0,.4.1 Dose projections or field Confirmed sample Confirmed sample Dose projections or field analysis for gaseous or surveys resulting from actual analysis for gaseous or surveys resulting from actual liquid release rates in or imminent release which liquid release rates in or imminent release which excess of two times release indicate dose rates in excess excess of two hundred indicate doses/dose rates in rate limits for >60 min of 10OmR/hr external exposure times release rate limits for excess of 10OOmR/hr external >15 min Mode Applicability:
exposure rate at the Site rate at the Site Boundary or - All beyond Mode Applicability:
Boundary or beyond OR - All OR Dose projections or field 5.2.3 Dose projections or field surveys resulting from actual Dose projections or field surveys resulting from actual or imminent release which surveys resulting from actual or imminent release which indicate >5OOmR/hr thyroid or imminent release which indicate >5000mR/hr thyroid exposure dose rate at the Site indicate >10mR/hr external exposure dose rate at the Site Boundary or beyond exposure rate at the Site Boundary or beyond OR OR Boundary or beyond Dose projections or field OR Dose projections or field surveys resulting from actual Dose projections or field surveys resulting from actual or imminent release which surveys resulting from actual or imminent release which indicate >1000mR TEDE dose indicate >100mR TEDE dose or imminent release which at the Site Boundary at the Site Boundary indicate >1 OmR TEDE dose or beyond or beyond the Site Boundary or beyond OR OR Dose projections or field Dose projections or field Mode Applicability:
surveys indicate >5000mR surveys resulting from actual - All CDE thyroid dose at the Site or imminent release which Boundary or beyond. indicate >500mR CDE thyroid dose at the Site Boundary or Mode Applicability: beyond.
- All Mode Applicability:
- All ________________________________ I Attachment 1
EPIP 1-0:22 5.3 Area Radiation Levels GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 5.3.2 5.3.1 Sustained area radiation Any sustained direct area levels > 15 mR/hr in radiation monitor readings either Control Room > 100 times alarm or OR off-scale high resulting from Central Alarm Station and an uncontrolled process.
Secondary Alarm Station Mode Applicability:
Mode Applicability: - All
- All 5.3.3 Sustained abnormal area radiation levels > 8 R/hr within any of the following areas:
- Containment
- Auxiliary Building
- Turbine Building
- Emergency Diesel Bldg.
- Screen house
- Standby Auxiliary Feedwater Building AND Access is required to establish or maintain Cold Shutdown Mode Applicability:
-All I Attachment 1
EPIP 1-0:23 6.1 Loss of AC Power Sources ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY TO EPIP 1-2 PROCEED TO EPIP 1-1 6.1.5 PROCEED TO EPIP 1-4 6.1.4 PROCEED TO EPIP 1-3 6.1.2 PROCEED 6.1.1 Loss of both trains of AC Loss of both trains of AC Loss of ability to supply Loss of all safeguards power to the safeguard busses for greater busses for greater than 15 bus AC power trains from offsite circuits AND EITHER: than 15 minutes minutes Mode Applicability: Mode Appicability: 751 and 767 for greater than power restoration to any 15 minutes safeguards train is not likely in - (1) Power Operations - (5) Cold Shutdown
- (2) Startup - (6) Refueling Mode Applicability:
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> - All OR - (3) Hot Shutdown - (D) Defueled Actual or imminent entry into - (4) Hot Standby 6.1.3 ORANGE or RED path Available safeguards train on F-0.2, CORE AC power reduced to COOLING only one of the following Mode Applicability: sources for >15 minutes.
- (1) Power Operations
- EDG 1A (14/18)
- (2) Startup
- EDG 1B (16/17)
- (3) Hot Shutdown
- Station Auxiliary
-(4)Hot Standby Transformer 12A
- Station Auxiliary Transformer 12B Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
EPIP 1-0:24 6.2 Loss of DC Power Sources SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 6.2.2 6.2.1
<108vdc bus voltage <1 08vdc bus voltage indications on 125vdc indications on 125vdc batteries 1A AND 1B for >15 batteries 1A AND 1B for minutes. >15 minutes.
Mode Applicability: Mode Applicability:
- (1) Power Operations - (5) Cold Shutdown
- (2) Startup - (6) Refueling
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
EPIP 1-0:25 7.0 EQUIPMENT FAILURES 7.1 Technical Specification Requirements GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 7.1.1 Plant is not brought to the required operating mode within Technical Specifications LCO Required Action Completion Time Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
EPIP 1-0:26 7.2 Safety Failures or Control Room Evacuation SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 _
PROCEED TO EPIP 1-4 7.2.5 7.2.2 Turbine failure generated Report of main turbine failure Entry into AP-CR.1 "Control resulting in casing Room Inaccessability" missiles results in any visible structural damage to plant penetration or damage to AND turbine seals or generator Control core cooling of vital equipment.
Mode Applicability seals cannot be established Mode Applicability:
per AP-CR.1 "Control - (1) Power Operations
- (2) Startup - (1) Power Operations Room Inaccessibility" - (2) Startup within 20 minutes - (3) Hot Shutdown
- (4) Hot Standby - (3) Hot Shutdown Mode Applicability: - (4) Hot Standby
- (1) Power Operations 7.2.3
- (2) Startup Entry into AP-CR.1 "Control
- (3) Hot Shutdown Room Inaccessability"
- (4) Hot Standby Mode Applicability:
- (5) Cold Shutdown
- (1) Power Operations
- (6) Refueling
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby
- (5) Cold Shutdown
- (6) Refueling 7.2.4 Reactor coolant temperature cannot be maintained <200'F Mode Applicability:
- (5) Cold Shutdown
- (6) Refueling
__________________ I Attachment 1
EPIP 1-0:27 7.3 Loss of Indications/Communication Capability ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 7.3.4 7.3.3 7.3.1 Unplanned loss of annunciators Unplanned loss of annunciators Loss of annunciators or or indications on any of the or indications on any of the indications on any of the following Control Room Panels following Control Room Panels following Control Room Panels for greater than 15 minutes for greater than 15 minutes
-A
-A -A
-AA
-AA -AA
-B
-B -B
-C
-D -C -C
-E -D -D
-F -E -E
-G -F -F AND -G -G Complete loss of ability AND AND to monitor any critical increased surveillance is increased surveillance is safety function status required for safe plant required for safe plant AND operation operation A plant transient in AND EITHER Mode Applicability:
progress - A plant transient in - (1) Power Operations Mode Applicability: progress - (2) Startup
- (1) Power Operations OR - (3) Hot Shutdown
- (2) Startup - PPCS is unavailable - (4) Hot Standby I Mode Applicability: 7.3.2
- (3) Hot Shutdown
- (4) Hot Standby - (1) Power Operations Loss of all communications
- (2) Startup capability affecting the
- (3) Hot Shutdown ability to either:
- (4) Hot Standby - perform routine operations OR
- Notify offsite agencies or personnel Mode Applicability:
- All Attachment 1
EPIP 1-0:28 8.0 HAZARDS 8.1 Security Threats ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY TO EPIP 1-2 PROCEED TO EPIP 1-1 8.1.4 PROCEED TO EPIP 1-4 8.1.3 PROCEED TO EPIP 1-3 8.1.2 PROCEED 8.1.1 Intrusion into plant Protected Bomb device or other indication Security event which Intrusion into plant security Area by an adversary of attempted sabotage results in: vital area by an adversary discovered within plant OR OR
- Loss of plant control Protected Area Any security event which Any security event which from the control room OR represents actual or likely represents an actual or OR Notification of any credible site failures of plant systems substantial degradation of the
- Loss of remote specific security threat by the needed to protect the public level of safety of the plant.
shutdown capability Security Shift Supervisor Mode Applicability- Mode App cabilitv:
Mode Applicability: or outside agency (NRC,
- All - All - All military or law enforcement Mode Applicability:
- All Attachment I
EPIP 1-0:29 8.2 Fire or Explosion ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 8.2.2 8.2.1 Fire or explosion in any of the Confirmed fire in any of the following plant areas which following plant areas not results in extinguished within 15 minutes EITHER of control room notification visible damage to plant - Intermediate Building equipment or structures - TSC needed for safe shutdown - Service Building OR - Contaminated Storage Loss of a safety system Building
- Intermediate Building - Control Building
-TSC - Containment Building
- Service Building - Auxiliary Building
- Contaminated Storage - Turbine Building Building - Emergency Diesel
- Control Building Building
- Containment Building - Standby Auxiliary
- Auxiliary Building Feedwater Building
- Turbine Building - Screen House
- Emergency Diesel Mode Applicability:
Building - All
- Standby Auxiliary Feedwater Building
- Screen House Mode Applicability:
- All Attachment 1
EPIP 1-0:30 0o..3 IV ll u VI-a -- vld ; l SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-1 DCImntft=n TCo IPIP 1-4 PROCEED TO EPIP 1-3 1 PROCEED TO EPIP 1-2 8.3.1 0.0.-+@ Vehicle crash into or Vehicle crash or projectile projectile which impacts impact which precludes personnel access to or plant structures or systems damages equipment in the within Protected Area following plant vital areas Boundary
- Control Building Mode Applicability:
- Containment Building - All
- Auxiliary Building 8.3.2
- Intermediate Building Report by plant personnel of
- Emergency Diesel Building an explosion within Protected
- Standby Auxiliary Area Boundary resulting in Feedwater Building visible damage to permanent
- Screen House structures or equipment Mode Applicability: Mode Applicability:
- All - All 8.3.5 8.3.3 Report or detection of toxic or Report or detection of toxic or flammable gases within the flammable gases that could following plant areas, in enter or have entered within concentrations that will be life the Protected Area Boundary threatening to plant personnel in amounts that could affect or precludes access to the health of plant personnel or equipment needed for safe safe plant operation plant operations OR
- Control Building Report by local, county or
- Containment Building state officials for potential
- Auxiliary Building evacuation of site personnel
- Intermediate Building based on offsite event
- Emergency Diesel Building Mode Applicability:
- Standby Auxiliary - All Feedwater Building
- Screen House Mode Applicability:
- All ILLdLIllhIIIL
__________________________________ A A44L.......4 4I Attacililmil I
EPIP 1-0:31 8.4 Natural Events GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 8.4.4 8.4.1 Earthquake felt in plant by Earthquake felt in plant by any plant operations personnel any plant operations personnel AND AND Confirmation of earthquake of Confirmation of earthquake of an intensity greater than 0.08g an intensity greater than 0.01 g per ER-SC.4 "Earthquake per ER-SC.4 "Earthquake Emergency Plan" Emergency Plan" Mode Applicability: Mode Applicability:
- All - All 8.4.5 8.4.2 Sustained winds >75mph Report by plant personnel of OR tornado striking within plant Tornado strikes one of the Protected Area Boundary following plant vital areas Mode Applicability:
- Control Building - All
- Containment Building (Continued on next page)
- Auxiliary Building
- Intermediate Building
- Emergency Diesel Building
- Standby Auxiliary Feedwater Building
- Screen House Mode Applicability:
- All (Continued on next page)
Attachment 1
EPIP 1-0:32 8.4 Natural Events SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 8.4.6 8.4.3 Any natural event which results Deer Creek flooding over in a report of visible structural entrance road bridge handrail damage or assessment by OR control room personnel of Lake level >252 ft actual damage to equipment OR needed for safe plant operation Screen House Suction in any of the following plant Bay water level <19 feet or areas:
- 17.5 feet by manual level
- Control Building measurement
- Containment Building Mode Applicability:
- Auxiliary Building - All
- Intermediate Building
- Emergency Diesel Building
- Standby Auxiliary Feedwater Building
-Screen House Mode Applicability:
- All 8.4.7 Flood water accumulating on screen house operating floor OR Lake level >253 ft OR Screen House Suction Bay water level _<16 feet or
- 14.5 feet by manual level measurement Mode Applicability:
- All Attachment 1
EPIP 1-0:33 9.0 OTHER SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 PROCEED TO EPIP 1-4 9.1.5 9.1.3 9.1.1 9.1.7 In the opinion of the Shift Any event, which in the Any event, which in the In the opinion of the Shift Supervisor or Emergency opinion of the Shift opinion of the Shift Supervisor Supervisor or Emergency Coordinator, events are in Supervisor or Emergency or Emergency Coordinator, Coordinator, events are in progress which indicate actual Coordinator, that could cause that could lead to or has led to progress which indicate or likely failures of plant or has caused actual a potential degradation of the actual or imminent core systems needed to protect the substantial degradation of the level of safety of the plant damage and the potential public. Any releases are not level of safety of the plant Mode Applicability:
for a large release of expected to result in Mode Applicability: - All radioactive material in exposures which exceed - All 9.1.2 excess of EPA PAGs outside the site boundary EPA PAGs 9.1.4 Any event, which in the Mode Applicability: Mode Applicability: Any event, which in the opinion of the Shift
- All - All opinion of the Shift Supervisor Supervisor or Emergency 9.1.6 or Emergency Coordinator, Coordinator, that could lead 9.1.8 Any event, which in the Any event, which in the that could lead or has led to a to or has led to a potential loss opinion of the Shift opinion of the Shift Supervisor loss or potential loss of either of containment (Attachment 3)
Supervisor or Emergency or Emergency Coordinator, fuel clad or RCS barrier Mode Applicability:
Coordinator, that could or has that could or has led to either: (Attachment 3) - (1) Power Operations led to a loss of any two fission - Loss or potential loss of Mode Applicability: - (2) Startup product barriers and loss or both fuel clad and RCS - (1) Power Operations - (3) Hot Shutdown potential loss of the third barrier (Attachment 3) - (2) Startup - (4) Hot Standby (Attachment 3) OR - (3) Hot Shutdown Mode Applicability: - Loss or potential loss of - (4) Hot Standby
- (1) Power Operations either fuel clad and RCS
- (2) Startup barrier in conjunction
- (3) Hot Shutdown with a loss of containment
- (4) Hot Standby (Attachment 3)
Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1
A1TACHMENT 2 DEFINITIONS Actuate - To put into operation; to move into action; commonly used to refer to automated, multi-faceted operations. "Actuate ECCS".
Adversary - As applied to security EALs, an individual whose intent is to commit sabotage, disrupt station operations or otherwise commit a crime on station property.
Adverse Meteorology - Low wind speed and low dispersion of effluents.
Alert - Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.
Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
Available The state or condition of being ready and able to be used (placed into operation) to accomplish the stated (or implied) action or function. As applied to a system, this requires the operability of necessary support systems (electrical power supplies, cooling water, lubrication, etc).
Can/Cannot be The current value or status of an identified parameter relative to that determined specified can/cannot be ascertained using all available indications (direct and indirect, singly or in combination).
Can/Cannot be - The value of the identified parameter(s) is/is not able to be kept maintained above/below specified limits. This determination includes making an above/below evaluation that considers both current and future system performance in relation to the current value or trend of the parameter(s). Neither implies that the parameter must actually exceed the limit before the action is taken nor that the action must be taken before the limit is reached.
Can/Cannot be - The value of the identified parameter(s) is/is not able to be returned to restored above/below above/below specified limits after having passed those limits. This determination includes making an evaluation that considers both current and future systems performances in relation to the current value and trend of the parameter(s). Does not imply any specific time interval but does not permit prolonged operation beyond a limit without taking the specified action.
As applied to loss of electrical power sources (ex.:power cannot be restored to any vital bus in <4 hrs) the specified power source cannot be returned to service within the specified time. This determination includes making an evaluation that considers both current and future restoration capabilities. Implies that the declaration should be made as soon as the determination is made that the power source cannot be restored within the specified time.
Classified Identify an EAL that corresponds to plant conditions
Close - To position a valve or damper so as to prevent flow of the process fluid.
- To make an electrical connection to supply power Confirm/Confirmation - To validate, through visual observation or physical inspection, that an assumed condition is as expected or required, without taking action to alter the "as found" configuration.
Control - Take action, as necessary, to maintain the value of a specified parameter within applicable limits; to fix or adjust the time, amount, or rate of; to regulate or restrict.
Core Failure - Fission product release to containment atmosphere that results in a reading of > 1000 REM/HR on containment area monitor R-2, R-29 or R-30.
- Use of the New York State Radiological Emergency Data Form in Declared procedure EPIP 1-5 to notify offsite agencies of a classified event.
Decrease - To become progressively less in size, amount, number, or intensity.
Discharge - Removal of a fluid/gas from a volume or system.
ECCS - High and low pressure safety injection
- Accumulators Enter - To go into.
Establish - To perform action necessary to meet a stated condition. "Establish communication with the Control Room."
Evacuate - To remove the contents of; to remove personnel from an area.
Exceeds - To go beyond a stated or implied limit, measure, or degree.
Exist - To have being with respect to understood limitations or conditions.
Facility - The Protected Area of the plant. The area within the security fence Failed Fuel - An increase in primary coolant activity reflected by an unexplained increase on failed fuel monitor (R-9) which exceeds its high alarm setpoint. If R-9 reading unavailable or unreliable, the failed fuel condition would be verified by a primary sample analysis.
Failure - A state of inability to perform a normal function.
Fire - The observance of flames or if any doubt exists due to excessive smoke, inaccessible location, a fire should be assumed to be present.
General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
Hazards - Aircraft crash, explosion, missiles, toxic gas, flammable gas, or turbine blade failures.
if - Logic term which indicates that taking the action prescribed is contingent upon the current existence of the stated condition(s). If the identified conditions do not exist, the prescribed action is not to be taken and execution of operator actions must proceed promptly in accordance with subsequent instructions.
Increase - To become progressively greater in size, amount, number or intensity.
Indicate - To point out or point to; to display the value of a process variable; to be a sign or symbol.
Initiate - The act of placing equipment or a system into service, either manually or automatically. Activation of a function or protective feature (i.e. initiate a manual trip).
Injection - The act of forcing a fluid into a volume or vessel.
Inoperable - Not able to perform it's intended function.
Intrusion - The act of entering without authorization.
LOCA - Entry into E-1.
Loss - Failure of operability or lack of access to.
Loss of all - Total loss of wind speed, wind direction and temperature from the Meteorological primary weather tower onsite and of wind direction and wind speed Indications from the back up weather tower located at Station 13A (accessible using EPIP 2-2), and all off-site sources available to the on-shift RP Tech.
Loss of Secondary - Entry into E-1.
Coolant Maintain - Take action, as necessary, to keep the value of the specified parameter within the applicable limits.
Monitor - Observe and evaluate at a frequency sufficient to remain apprised of the value, trend, and rate of change of the specified parameter.
Notify - To give notice of or report the occurrence of; to make known to; to inform specified personnel; to advise; to communicate; to contact; to relay.
OBE - Operating Basis Earthquake. An earthquake having 0.08g peak ground acceleration.
Open To position a valve or damper so as to allow flow of the process fluid.
To break an electrical connection which removes a power supply from an electrical device.
To make available for entry or passage by turning back, removing, or clearing away.
Operable Able to perform it's intended function.
Perform To carry out an action; to accomplish; to affect; to reach an objective.
Periodically As plant conditions change.
Plant Building Turbine Building, Serv. Building, Containment, Aux. Building, Standby Aux. Feed Building or the Screen House, Contaminated Storage Building or Upper Radwaste Storage Building.
Primary System - The pipes, valves, and other equipment which connect directly to the reactor vessel or reactor coolant system such that a reduction in reactor coolant system pressure will effect a decrease in the steam or water pressure being discharged through an unisolated break in the system.
Radiation Monitor - Any permanent or temporary area or process monitor.
Remove - To change the location or position of.
Report - To describe as being in a specific state.
Require - To demand as necessary or essential.
Restore - Take the appropriate action required to return the value of an identified parameter to within applicable limits.
Rise - Describes an increase in a parameter as the result of an operator or automatic system.
Safe Shutdown - Minimum equipment required by Appendix "R" procedures.
Equipment Sample - To perform an analysis on a specified media to determine its properties.
SGTR - Entry into E-3.
Shutdown - To perform operations necessary to cause equipment to cease or suspend operation; to stop. "Shutdown unnecessary equipment."
Site Area Emergency - Events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.
Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels except near the site boundary.
Sustained - Prolonged. Not intermittent or of transitory nature.
Sustained Winds - The five minuted average based on a PPCS reading from the 150 foot or 250 foot Met Tower wind speed indicator.
SSE - Safe Shutdown Earthquake. An earthquake having 0.2g peak ground acceleration.
TEDE - Total Effective Dose Equivalent.
Thyroid Dose - Thyroid dose is assumed to be the same as Committed Dose Equivalent (CDE).
Trip - To de-energize a pump or fan motor; to position a breaker so as to interrupt or prevent the flow of current in the associated circuit; to manually activate a semi-automatic feature.
- To take action to cause shutdown of the reactor by opening the reactor trip breaker.
Total Loss of All - Total loss of Condensate, Mainfeed, all Auxiliary Feedwater and Standby Auxiliary Feedwater.
Feedwater Uncontrolled - An evolution lacking control but is not the result of operator action.
Unexplained - A condition where parameters/condition exist that are not normal for current plant status and are not a result of operator action.
Unmonitored - A release of radioactive material to the environment which does not Release pass through an area or process monitor.
Unplanned - Not as an expected result of deliberate action.
Until - Indicates that the associated prescribed action is to proceed only so long as the identified condition does not exist.
Unusual Event - Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
Valid - Supported or corroborated on a sound basis.
Vent - To open an effluent (exhaust) flowpath from an enclosed volume; to reduce pressure in an enclosed volume.
Verify - To confirm a condition and take action to establish that condition if required. "Verify reactor trip, verify SI pumps running."
Vital Areas - Areas of the plant containing equipment or machinery that could affect the safe operation or shutdown of the plant.
Whole Body - Whole body dose is assumed to be the same as Total Effective Dose Dose Equivalent (TEDE).
EPIP 1-0:39 Attachn nent 3
)TENTIAL LOSS BARRIER LOSS/PC Fuel Claidding Loss Potential Loss Loss RED path in F-0.2, CORE COOLING ORANGE path in F-0.2, CORE COOLING Coolant activity > 300 pCi/cc of 1-131 RED path in F-0.3, HEAT SINK Core Exit Thermocouple Readings > 1200 °F Core Exit Thermocouple Readings > 700 OF Containment rad monitor reading >100 R/hr RVLIS <77% w/ no RCPs running Letdown Monitor (R-9) reading > 10 R/hr Emergency Coordinator Judgment Emergency Coordinator Judgment IS RC Loss Potential Loss RCS subcooling < EOP Fig. MIN SUBCOOLING due to RCS leakage RED path on F-0.4, INTEGRITY Unisolable secondary side line break with SG tube rupture as identified RED path on F-0.3, HEAT SINK in E-3 "Steam Generator Tube Rupture" Containment radiation monitor reading > 10 R/hr Primary system leakage > 46 gpm Emergency Coordinator Judgment Emergency Coordinator Judgment Page 1 of 2
EPIP 1-0:40 Attachment 3 BARRIER LOSS/POTENTAIL LOSS Containment 11 Lo Pnt~ntial Loss Loss Potential Loss Rapid uncontrolled decrease in Containment Pressure following initial RED path F-0.5, CONTAINMENT increase Loss of primary coolant inside containment with containment pressure or Either:
sump level response not consistent with LOCA conditions, i.e.
Core exit thermocouples >1200 'F unexpected changes occur in these parameters that are not explainable OR due to operator actions or automatic system actions.
Core exit thermocouples >700 'F with RVLIS <77% (no RCPs)
AND Restoration procedures not effective within 15 minutes Either:
Safety injection signal due to LOCA with < the minimum containment Cl or CVI isolation required and CI or CVI valve(s) not closed when cooling safeguards equipment operating:
required CNMT pressure <28 psig: 2 CNMT Recirc Fans OR 2 CNMT Spray Pumps Inability to isolate any primary system discharging outside containment CNMT pressure >28 psig:
OR AND 2 CNMT Recirc Fans Radiological release pathway to the environment exists and 1 CNMT Spray Pump Containment pressure 60 psig and increasing Release of secondary side to atmosphere with primary to secondary leakage greater than tech spec allowable of 0.1 GPM per steam generator
_>4 % hydrogen concentration in containment Both doors open on containment airlock OR Inability to close containment pressure relief or purge valves which results in a radiological release pathway to the environment OR Cl or CVI valve(s) not closed when required which results in a radiological release pathway to the environment Emergency Coordinator Judgment Containment radiation monitor reading >1000 R/hr Emergency Coordinator Judgment Page 2 of 2
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER J15 PROCEDURE No. EPIP 1-11 REV NO. 26 SURVEY CENTER ACTIVATION RESFE T ATER EFFE"CTIVE= DATE CATEGORY 1.0 THIS PROCEDURE CONTAINS 10 PAGES
EPIP 1-11:1 EPIP 1-11 SURVEY CENTER ACTIVATION
1.0 PURPOSE
The purpose of this procedure is to designate duties for individuals who report to the Survey Center.
2.0 RESPONSIBILITY
2.1 The first person to arrive is responsible for implementing this procedure.
2.2 The Survey Center Manager or the Assistant Survey Center Manager is responsible for activation of the Survey Center upon arrival.
3.0 REFERENCES
3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.2 Implementing References 3.2.1 EPIP 2-11, Onsite Surveys 3.2.2 EPIP 2-12, Offsite Surveys 3.2.3 EPIP 2-13, Iodine and Particulate Activity Determination from Air Samples 3.2.4 EPIP 3-3, Immediate Entry 3.2.5 EPIP 5-7, Emergency Organization 3.2.6 EPIP 1-18, Discretionary Actions for Emergency Conditions 3.2.7 RP-SUR-PER-DECON, Personnel, Decontamination 3.2.8 RP-JC-AMS-4, Routine Operation of the Eberline AMS-4 Air Monitor System 3.2.9 RPA-RW-SHIP-MTL, Shipment of Radioactive Material-General Guidance
4.0 PRECAUTIONS
NONE
5.0 PREREQUISITES
5.1 An Alert, Site Area Emergency or General Emergency has been declared in accordance with EPIP 1-0.
5.2 The Emergency Coordinator has requested that the Survey Center be activated.
EPIP 1-11:2
6.0 ACTIONS
NOTE: SELECTED PROCEDURES ARE LOCATED IN A BINDER INSIDE THE SURVEY CENTER. ADDITIONAL PROCEDURES THAT MAY BE NEEDED CAN BE OBTAINED FROM THE NUCLEAR TRAINING RESOURCE CENTER.
6.1 ARRIVING PERSONNEL NOTE: DEPENDING ON THE NUMBER OF ARRIVING PERSONNEL, STEPS MAY BE PERFORMED CONCURRENTLY TO MINIMIZE ACTIVATION TIME.
6.1.1 Sign in under appropriate position on the Survey Center sign in board and obtain position I.D. badge if applicable. Refer to instructions on tag board or procedure EPIP 5-7.
6.1.1.1 Survey Team instructions are located in EPIP 2-11 and EPIP 2-12.
6.1.2 During normal working hours, bring your assigned TLD with you to the Survey Center. During off hours, obtain an emergency TLD from the Survey Center Manager if your normal TLD is not available.
6.1.3 Log in on Dosimetry Log (Attachment 2) and obtain Dosimetry. Refer to EPIP 2-11 and EPIP 2-12 for dosimeter ranges for Survey Team members.
Survey Center personnel obtain 0-1500 mr dosimeters.
6.2 SURVEY CENTER MANAGER OR ASSISTANT:
6.2.1 Notify Emergency Coordinator (Ext. 3503) of your arrival.
6.2.2 Obtain Survey Center Keys and unlock equipment storage area door.
6.2.3 Ensure area monitor is operating and note reading. A reading of 1mR/hr or greater should be brought to the attention of the TSC Dose Assessment Manager so that a relocation plan can be formulated.
6.2.3.1 If radiation levels exceed 1 mR/hr, an audible and visual alarm is activated.
Silence the audible alarm. The visual alarm stays lit uintil the alarm condition clears.
6.2.3.2 If radiation level exceeds 50 mR/hr., an audible and visual alarm is activated.
Silence the audible alarm. The visual alarm stays lit until the alarm condition clears.
6.2.4 Ensure both Deskron II radios are ON and the volume is turned UP in the Survey Center.
EPIP 1-11:3 CAUTION IF DOSE RATES EXCEED 50 MREM/HR, ADVISE EMERGENCY COORDINATOR AND PREPARE FOR RELOCATION AFTER DISPATCH OF SURVEY TEAMS.
6.2.6 Conduct radiation survey of survey center and reception areas of both training buildings and the simulator and exterior building areas. Periodically, conduct contamination and radiation surveys of all training areas.
6.2.7 Place AMS-4 Air Monitor in operation, per RP-JC-AMS-4.
CAUTION IF AIRBORNE IODINE ACTIVITY IS GREATER THAN 1E-8 /pCi/cc, INFORM THE EMERGENCY COORDINATOR.
6.2.8 Take an air sample and analyze in accordance with EPIP 2-13.
6.2.9 If the Survey Center is not deemed habitable, the Survey Center Manager should inform the Dose Assessment Manager, and suggest relocation to an alternate survey team staging area such as: Warehouse west end of parking lot; Station 13A; Station 204 on Route 104; White house by the entrance to the plant access road; Manor House; RG&E Service Center on Plank Road just west of Route 250; Substation #230 - Atlantic Avenue, Walworth; and the Ontario Fire Department Exempt Hall on Route 104 between Route 350 and Knickerbocker Road.
6.2.10 If the Survey Center is to be relocated, contact the Maintenance Assessment Manager (at ext. 3628) to make arrangements to move the equipment to the alternate location. The equipment should include, but is not limited to:
- Radiological Survey Meters
- Air Samplers and filters
- TLD's
- Dosimeters
- Survey Maps
- Radios
- Cellular Phones
- Procedures
- Survey Team Boxes 6.2.11 Notify a Personnel Coordinator, from EPIP 5-7, that the Survey Center has been activated and to perform a personnel accountability as listed in Step 6.3.3.
6.2.12 Organize the Survey Teams:
- a. To assist in briefing the Survey Teams obtain the most current copy of the NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM (Part I) from the Survey Center fax machine (ext. 3612).
EPIP 1-11:4
- b. If the NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM (Part I), is not available , contact the TSC and obtain the following information to assist in briefing the survey teams.
- 1. Wind speed and direction.
- 2. Release in progress or has occurred.
- 3. Event classification.
- 4. Plant conditions.
- c. Post the event classification and weather data on the information board.
- d. Maintain a log of all Survey Center activities.
- e. Ensure arriving personnel sign in as Survey Team members, Communicator or Assistant Survey Center Managers.
- f. Assist the Survey Teams to prepare for dispatch.
- g. Ensure that the briefing covers the following items:
- Team identification
- Communications equipment and channel
- 3-way communications and use of phonetic alphabet
- Protective equipment (including use of KI)
- Authorized doses
- Survey instructions
- Survey equipment
- Type of date required
- Job safety including use of safety vests and yellow beacon (for offsite teams)
- h. Collect Survey Team Equipment/Team Data forms (Attachment 3) from Survey Teams and insure data is transferred to the appropriate attachments located in EPIP procedures (e.g., Survey Center Dosimetry Log, EPIP 1-11, Attachment 2; EPIP Instrument Response Check, EPIP 2-11, Attachment 16 or EPIP 2-12, Attachment 21).
- i. Notify the TSC Dose Assessment Manager when the Survey Teams are ready to be dispatched.
- j. Fax a list of the members of each Survey Team and their cellular phone numbers to the TSC Dose Assessment Manager.
6.2.13 Confirm with TSC Dose Assessment Manager the need to frisk evacuees. If it decided to frisk evacuees, allow personnel who need to respond to the EOF or JENC to have front of the line privilege.
6.2.14 If arriving personnel are required to staff the TSC assist personnel requiring site access by referring to EPIP 3-3, Immediate Entry.
- a. Notify Security at Secondary Alarm Station (Ext. 3267) of TSC members (by name) who will need access to the site.
- b. Advise those going to the TSC of dose rates in the area.
EPIP 1-11:5
- c. Provide directions for site access route and safety precautions.
6.2.15 Ensure decontamination facilities are set up.
- a. Switch the decontamination shower and deep sink drains from the sewer system to the holding tank by shutting and locking valve "S"and unlocking and opening valve 'T' located to the right of the shower.
- b. Set up receptacles, step-off pads and barriers to route traffic through the facility.
- c. Operate the decontamination facility with RP section guidance in accordance with RP-SUR-PERS-DECON.
NOTE: PERIODICALLY, CHECK THE WATER LEVEL IN THE TANK BY LIFTING THE TANK COVER TO ENSURE THAT THE TANK IS NOT OVERFILLED WHILE IN USE.
- d. When the holding tank high level alarm sounds (local alarm 1-1/2 feet from top of tank) notify the RP/Chemistry Manager or his designee.
CAUTION ENSURE THAT THE DECONTAMINATION SHOWER AND DEEP SINK ARE NOT USED DURING SAMPLING AND /OR PUMPING. HANG "DO NOT USE" SIGNS ON SHOWER AND DEEP SINK.
- e. After a tank sample has been taken and analyzed, the RP/Chemistry Manager or his designee will determine if the tank will be pumped to the sewer system through a manhole located approximately 50 feet west of the holding tank or transferred to the Ginna radioactive waste system by tanker truck.
CAUTION THE SURVEY CENTER MANAGER SHOULD NOTIFY THE SIMULATOR BUILDING OCCUPANTS IF OCCUPIED OR SEND SOMEONE TO THE SIMULATOR BUILDING DURING THE PUMPING OPERATION TO THE SEWER SYSTEM TO CHECK THE SUMP PUMPS ARE OPERATING PROPERLY TO HANDLE THE ADDITIONAL WATER BEING PUMPED FROM THE DECON SHOWER HOLDING TANK.
- f. After the holding tank has been pumped, restore decontamination operations.
- g. After decontamination activities have been completed and the shower and deep sink have been smear-surveyed clean and released, restore the drain lineup to the sewer system. Shut and lock valve 'T' and unlock and open valve "S".
- h. Ensure all evolutions have been entered in the Survey Center Manager's log.
EPIP 1-11:6 6.2.16 Notify TSC Administration/Communication Manager of accountability.
6.2.17 Inform the RP/Chemistry Manager (Ext. 3507) that the Environmental Laboratory should be set up to process samples collected by the survey teams. Have RP personnel set up lab using Attachment 1.
6.2.18 Segregation of samples
- a. When survey teams return have them drop their samples off in the roped off area outside the Survey Center.
- b. Insure all sample labels are filled out and legible.
- c. Perform a survey of each sample returned. Place a label on the sample with the dose rate measured.
- d. Segregate the samples into samples that read:
(a) greater than or equal to 200mR/hr (b) less than 200mR/hr NOTE: INITIAL SAMPLES THAT ARE COLLECTED THAT HAVE ACTIVITY SHOULD BE ANALYZED USING THE RP COUNT EQUIPMENT.
- e. Notify the RP/Chemistry Manager that samples need to be counted or to make arrangements to ship them to a contact counting facility.
Place these samples in an area that will not contribute to the exposure of personnel in the Survey Center.
6.2.19 Conduct post-job brief when Survey Teams return to the Survey Center and document in the log.
6.2.20 Following termination of event, ensure the Dosimetry Log (Attachment 2) is forwarded to Dosimetry for entry into the RADOSE Dose Management System (RDMS).
6.3 PERSONNEL COORDINATOR:
6.3.1 Notify Survey Center Manager of your arrival.
6.3.2 Establish a means of constant communications with the Survey Center Manager.
EPIP 1-11:7 6.3.3 Assure accountability of personnel outside the plant fence; but on company property, such as:
NOTE: GROUNDS CREW CAN ASSIST IN NOTIFICATIONS OF PERSONNEL ON COMPANY PROPERTY OUTSIDE THE FENCE. CALL KEITH MERKEL (PAGER: 525-5772) OR NORM BURKETT (PAGER: 528-9513) FOR ASSISTANCE.
- a. Simulator Building d. Manor House (ext. 3744)
(ext. 6668, 6646 or 6641) e. Offsite Warehouse b, Training Center (ext. 6600) (ext. 3292 or 3288)
- c. Grounds Crew f. Station 13A Area (White House 315-524-5309) 6.3.4 Report completion of accountability to the Survey Center Manager.
6.3.5 Notify personnel outside the plant fence, but on company property to the emergency classification level, and direct them to standby for further instructions.
6.3.6 Direct evacuating personnel to appropriate assembly areas as required or as directed by Emergency Coordinator or Survey Center Manager.
6.3.7 Release evacuating personnel from assembly areas as required or as directed by Emergency Coordinator or Survey Center Manager.
6.3.8 Maintain control of evacuated personnel and additional personnel throughout the emergency.
7.0 ATTACHMENTS
- 1. Environmental Laboratory Operations.
- 2. Survey Center Dosimetry Log.
EPIP 1-11:8 Attachment 1, Rev. 26 Page 1 of 2 ENVIRONMENTAL LABORATORY OPERATIONS (To be performed by Radiation Protection Personnel)
Preparing the Environmental Laboratory to receive samples:
- 1. Samples will be transported from the Survey Center to the Environmental Laboratory.
Place radioactive materials signs on the doors to the Environmental Laboratory and the count room. Rope off the west end of the Environmental Laboratory for sample storage.
Remove any environmental samples stored in that area to prevent cross contamination.
- 2. Consult with the Survey Center Manager to determine the best route to transport the samples:
- a. If samples are transported inside thru the building, personnel may be exposed by the samples or contamination may be spread in the building. A route should be cleared prior to transport and surveyed for contamination afterwards.
- b. If samples are transported outside, there may be snow or rain to degrade the samples or there may be contamination deposited on the ground from a release.
Place step-off pads down where personnel will re-enter the building. Perform surveys at that point to ensure that contamination has not been brought into the building.
Transport of the samples from the Survey Center to the Environmental Laboratory.
- 1. Ensure that the personnel transporting the samples are wearing dosimetry.
- 2. Place the samples to be transported into a clean plastic bag to prevent the spread of contamination.
- 3. Move the samples to the Environmental Laboratory.
- 4. Perform a survey of the route (smears or direct frisk) to ensure that contamination was not spread.
Analyzing samples in the Environmental Laboratory
- 1. Laboratory operations should be conducted using the appropriate Radiation Protection procedures for the Environmental Laboratory.
- 2. Inform the RP/Chemistry Manager when results are available from the Gamma Spectroscopy System. The TSC/EOF personnel can view the results from the facilities via modem.
EPIP 1-11:9 Attachment 1, Rev. 26 Page 2 of 2
- 3. If data needs to be faxed to the TSC/EOF use the fax machine in the Survey Center.
Moving the samples to an offsite laboratory.
- 1. Ensure that the samples are properly packaged, labeled and marked for activity in accordance with procedure RPA-RW-SHIP-MTL.
- 2. Laboratory operations at the offsite laboratory should be conducted using their procedures for analyzing samples.
EPIP 1-11:10 Attachment 2, Rev. 26 Page 1 of 1 SURVEY CENTER DOSIMETRY LOG TIME DOSIMETER READING NAME TLD DOSIMETER NUMBER NUMBER IN OUT IN OUT TOTAL J. 4 4- I I t
- 1. 4 4- I I I t
- 4. 4- + I t I 1 4. + I I 1- t 1 4- 4 4- I t t 4 4 4 t I t I 1 + I 1 t I 4- 1 t t t t I I. I I t
_________ +/- I 1 4 + I I
_________ 4 4- 1 + 1 I 4 J + I 4- I 1 1 4.
- I 4- 1 1 I + 4 1 1 1 1 i + -t t i I I
__________ i. .4 1 4- 1 4- 1-
- 4. .4 I + I I- t
-I- 1 4 + I 1- 4-Forwarded to Dosimetry: Dose Entered:
Date: Date:
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER:2Q PROCEDURE NO. EPIP 2-5 REV. NO. 14 EMERGENCY DOSE PROJECTIONS - PERSONAL COMPUTER METHOD RES%7N--IBLE MAT ER 6s ll29'l EFFECTIVE DATE Category 1.0 This procedure contains 10
EPIP 2-5:1 EPIP 2-5 EMERGENCY DOSE PROJECTIONS - PERSONAL COMPUTER METHOD 1.0 PURPOSE The purpose of this procedure is to provide a personal computer-based method for performing projections of downwind dose rates and doses. Such information is needed to decide upon protective actions to be recommended to limit the exposure of the general public and emergency workers.
2.0 RESPONSIBILITY The TSC or EOF Dose Assessment Manager is responsible for implementing this procedure.
3.0 REFERENCES
3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.1.2 EPA-400, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (1991) 3.1.3 Ginna UFSAR, Chapter 15 3.1.4 Regulatory Guide 1.109 3.1.5 Vertechs Corporation, EOF8, Estimated Offsite Dose Assessment Program Documentation Binder 3.2 Implementing References 3.2.1 EPIP 2-1, Protective Action Recommendations 3.2.2 EPIP 2-2, Obtaining Meteorological Data and Forecasts and Their Use in Emergency Dose Assessment 3.2.3 EPIP 2-3, Emergency Release Rate Determination 3.2.4 EPIP 2-4, Emergency Dose Projections - Manual Method 3.2.5 EPIP 1-0, Ginna Station Event Evaluation and Classification 3.2.6 EPIP 2-17, Hypothetical (Pre-Release) Dose Estimates 4.0 PRECAUTIONS None.
EPIP 2-5:2 5.0 PREREQUISITES 5.1 The following equipment and data sources are available for use in performing computerized dose projections:
5.1.1 Plant Process Computer System (PPCS) - EVENT 2 Report.
5.1.2 Personal Computer in TSC and EOF (for obtaining 15-minute meteorological data averages from Ginna primary weather tower).
5.1.3 Back-up wind speed and direction indicators at Station 13A (accessible from TSC or EOF Personal Computer) and National Weather Service.
5.1.4 Field readings from survey teams, including gamma dose rate and air sample measurements taken in the release plume.
5.1.5 Personal Computer for performing dose projection routines detailed in this procedure.
DOSE ASSESSMENT USE OF GINNA COMPUTER DATA NOTE: COMPARE ALL DOSE PROJECTIONS AGAINST EPIP 1-0, SECTION 5.2.
6.0 ACTIONS 6.1 Part "A" - Release Assessments 6.1.1 During a Ginna Refueling Outage, R12 could be an effluent monitor. Check with your technical support for this condition. If R12 is an effluent monitor and IS NOT on alarm or increasing, go to step 6.1.2. If R12 is an effluent monitor and IS on alarm or increasing, check:
Alarm EPIP 1-0 Section 5.1 and R12A5 - SPING Containment Vent LOW Range Gas Monitor Ei Yes o No R12A7 - SPING Containment Vent MID Range Gas Monitor o Yes ol No R12A9 - SPING Containment Vent HIGH Range Gas Monitor ol Yes o No Use the SPING sheet (Attachment 1) to determine which channel to use and enter the value in the DOWNCALC program (Go to step 6.1.2).
NOTE: R15 PROBLEMS USUALLY INDICATE THAT THERE IS A TUBE IN THE STEAM GENERATOR THAT IS LEAKING RADIOACTIVE REACTOR COOLANT SYSTEM WATER INTO THE NON-RADIOACTIVE STEAM PLANT WATER.
EPIP 2-5:3 6.1.2 R1 5 - Condenser Air Ejector Monitor. If R1 5 IS NOT on alarm continue to Step 6.1.3. If R15 IS on alarm check:
Alarm EPIP 1-0 Section 5.1 and R15A5 - SPING Condenser Air Ejector LOW Range Gas Monitor c] Yes o No R15A7 - SPING Condenser Air Ejector MID Range Gas Monitor o Yes o No R15A9 - SPING Condenser Air Ejector HIGH Range Gas Monitor o Yes o No Use the sping sheet (Attachment 1) to determine which channel to use and enter that value in the downcalc program. (Go to step 6.1.3).
NOTE: R14 PROBLEMS USUALLY INDICATE THAT THERE IS SOMETHING LEAKING IN THE AUXILIARY OR INTERMEDIATE BUILDINGS.
6.1.3 R14 - Plant Vent Gas Monitor. If R14 IS NOT on alarm go to step 6.1.4 If R14 IS on alarm check:
Alarm EPIP 1-0 Section 5.1 and R14A5 - SPING Plant Vent LOW Range Gas Monitor o Yes o No R14A7 - SPING Plant Vent MID Range Gas Monitor c] Yes o No R14A9 - SPING Plant Vent HIGH Range Gas Monitor o Yes o No Use the sping sheet (Attachment 1) to determine which channel to use and enter that value in the downcalc program. (Go to step 6.1.4).
NOTE: R31 AND R32 PROBLEMS USUALLY INDICATE THAT THERE IS A TUBE IN THE STEAM GENERATOR THAT IS LEAKING RADIOACTIVE REACTOR COOLANT SYSTEM WATER INTO THE NO-RADIOACTIVE STEAM PLANT WATER. AS LONG AS THE ARVS AND SAFETY VALVES ARE SHUT, THERE IS NO RELEASE.
6.1.4 R31 and R32 - "A" & "B" Steam Line Monitors. If R31 and R32 ARE NOT on alarm, go to step 6.2 for plant assessments. If R31 or R32 ARE on alarm, determine, from the event 2 printout, if any ARVs or Safety Valves are open. Also, compare R-31/32 readings to EPIP 1-0, Section 5.1. If the associated ARV or Safety Valve for the alarming monitor is open, enter the reading in the DOWNCALC program. (Go to step 6.3.) The event 2 report also lists a computer calculated 15 minute average of Ci/sec released. This can be directly entered into the DOWNCALC program also.
6.1.5 For unmonitored releases from containment, go to EPIP 2-17 to calculate the release rate.
6.2 Part "B" - Plant Assessments 6.2.1 Check R12 - Containment Gas Monitor. If R12 IS NOT on alarm or increasing then the containment atmosphere is clean of radioactivity. If R12 IS on alarm or increasing, then the Reactor Coolant System is leaking water out into the containment atmosphere. Go to step 6.2.2.
6.2.2 Check R9 - Letdown Monitor. If R9 IS on alarm or increasing then the Reactor Fuel is leaking into the Reactor Coolant System water. Go to Step 6.2.4.
EPIP 2-5:4 6.2.3 Ifyou have reached this step the plant and reactor, most probably, are in a stable condition and no release is occurring. Ifthe plant is in an outage, check with your Technical Group to learn about any unusual conditions that could pose special problems.
6.2.4 Check R29 and R30 - Containment HIGH Range Area Monitors.
Check and compare the readings. If R29 or R30 read
>100 R/hr, declare a Site Area Emergency (EAL#2.3.2). If R29 or R30 read >1000 R/hr, declare a General Emergency (EAL#2.3.3). Continue to check R29 and R30 for increases due to degraded plant conditions.
6.3 Dose Calculations Using Personal Computer 6.3.1 If using the computers at RG&E, log in to corporate desktop using "User: Ginna",
"Password: lakela".
6.3.1.1 Select the EOF8 icon to start session information.
6.3.1.2 Choose "new session".
6.3.1.3 Enter "session date" in MM/DD/YY format. Enter "session time" in HHMM format.
6.3.1.4 Enter your name.
6.3.1.5 Enter a short description of the event.
6.3.1.6 Enter a reactor shutdown date and time if the reactor is shutdown. Ifthe reactor is not shutdown, do not enter any data.
6.3.1.7 Select the "save" button. A message should appear in the upper right portion of the screen. Click anywhere on the screen to clear the "save" message.
6.3.2 Downwind dose calculations 6.3.2.1 Select the downcalc button along the left side of the screen.
6.3.2.2 Review the release flowrates. Contact Operations personnel to determine current flowrates. On the initial calculation, if Operations is busy, use the normal flowrates in the program so the initial assessment is not delayed. Select the normal or emergency flowrates. Adjust the values as necessary. Select OK when done.
Ensure TSC/EOF Dose Assessment and offsite responders are using the same flowrates.
NOTE: TO SCROLL THROUGH FIELDS, PRESS THE TAB KEY.
6.3.2.3 Enter the shutdown date and time if the reactor is shutdown. If the reactor is not shutdown, then press tab to scroll through these 2 fields.
6.3.2.4 Enter the calculation date and the calculation time.
6.3.2.5 To use the last saved values, click on the button labeled "use the last saved values".
If new data is to be used, continue.
EPIP 2-5:5 6.3.2.6 Enter the temperature at 250 feet.
6.3.2.7 Enter the temperature at 33 feet.
NOTE: THE WIND SPEED INDICATOR AT THE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLY TO 50 MILES PER HOUR.
6.3.2.8 Enter the wind speed at 33 feet.
NOTE: IF "WHAT IF" CALCULATIONS ARE DESIRED, REFER TO EPIP 2-17.
6.3.2.9 If a radioiodine value for the containment vent (R10A) or plant vent (R10B) has been calculated using the "ventconc" program, enter the values for the appropriate monitor. If no value has been calculated, the program will use the default radioiodine release rate based on the noble gas concentration.
6.3.2.10 Enter the value (in mR/hr) if R-31 is in alarm condition and is a release path.
6.3.2.11 Enter the value in (in mR/hr) if R-32 is in alarm condition and is a release path.
6.3.2.12 Enter value (in uCi/cc from R-12A) if R-12 is in alarm condition and is a release path.
6.3.2.13 Enter value (in uCi/cc from R-14A) if R-14 is in alarm condition.
6.3.2.14 Enter value (in uCi/cc from R-15A) if R-15 is in alarm condition and is a release path.
6.3.2.15 Enter date and time of data.
6.3.2.16 Enter exposure duration, if the release duration is known. If the release duration is unknown, enter the default of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
NOTE: THE SITE BOUNDARY IS 0.3 MILES FROM THE REACTOR.
6.3.2.17 Enter "X" miles to 5.0. If PARs have been issued, ensure that 5 miles is adequate for evacuation. This can be changed in later assessments for other areas of interest.
6.3.2.18 Select the "save and report" button on the bottom of the screen.
6.3.2.19 Review the file name and select OK.
6.3.2.20 Review the data, then print the report and exit.
CAUTION: DO NOT PRINT THE "EMERG DATA FORM" WITH NIA OR ZEROS (0) IN ALL OF THE RELEASE POINTS.
6.3.2.22 Select "emerg data form (part II)". Report will print. Give this report to the Dose Assessment Manager. This report should be reviewed and faxed to RG&E, Wayne County, Monroe County and New York State.
EPIP 2-5:6 6.3.2.23 Return to step 6.3.2.2 for more downwind calculations. To perform other calculations, select "exit" from the top of the screen.
6.3.3 Survey Team Data Dose Projections 6.3.3.1 Select the sample button from the left hand side of the screen.
6.3.3.2 Enter the shutdown date and time if the reactor is shutdown. If the reactor is not shutdown, then press enter to scroll through these 2 fields.
6.3.3.3 Enter the calculation date and the calculation time.
6.3.3.4 Enter the team number, color or other identification.
6.3.3.5 Enter the team location where the sample was obtained.
6.3.3.6 Enter the date and time that the sample was started.
6.3.3.7 Enter the date and time that the sample was stopped.
6.3.3.8 Enter the units of measurement of the air sample.
6.3.3.9 Enter the air sample flow rate at the start of the sample.
6.3.3.10 Enter the air sample flow rate when the sample was stopped.
6.3.3.11 Enter the count rate (CPM) of the iodine cartridge.
6.3.3.12 Enter the count rate (CPM) of the particulate filter.
6.3.3.13 Enter the background count rate (CPM) in the area that the sample was counted.
(This should be performed outside of the plume).
6.3.3.14 The bottom right of the screen will show you:
- radioiodine concentration in the air (in uCi/cc) radioactive particulate in the air (in uCi/cc) the dose rate (in REM/hr) to a child's thyroid from the radioiodine concentration in the air.
6.3.3.15 Select the "save and report" button on the bottom of the screen.
6.3.3.16 Enter description of reason for calculation and select ok.
6.3.3.17 Review the data, then print the report and exit.
6.3.3.18 Select "exit" from the top of the screen.
6.3.3.19 Select the "backcalc" button along the left side of the screen.
6.3.3.20 Enter the shutdown date and time if the reactor is shutdown. If the reactor is not shutdown, then press enter to scroll through these 2 fields.
EPIP 2-5:7 6.3.3.21 Enter the calculation date and the calculation time.
6.3.3.22 Enter the temperature at 250 feet.
6.3.3.23 Enter the temperature at 33 feet.
NOTE: THE WIND SPEED INDICATOR AT THE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLY TO 50 MILES PER HOUR.
6.3.3.24 Enter the wind speed at 33 feet.
6.3.3.25 Enter the team number, color or other identification.
6.3.3.26 Enter the team location where the sample was obtained.
6.3.3.27 Enter the distance (in miles) away from the Ginna Plant.
6.3.3.28 Enter the sample date and sample time.
6.3.3.29 Enter the closed window dose rate that the survey team reported at the sample location. This dose rate will be in R/hr or mR/hr. (DO NOT use the background CPM value of the radioiodine analysis. That was a different screen that you have already completed.)
6.3.3.30 Enter the radioiodine concentration (in uCi/cc) from the SAMPLE program printout.
6.3.3.31 Enter A & B points of interest.
6.3.3.32 You have now projected doses from the point where your survey team collected sample data.
6.3.3.33 Select the "save and report" button on the bottom of the screen.
6.3.3.34 Review the file name and select OK.
6.3.3.35 Review the data, then print the report and exit.
6.3.3.36 Select "report".
6.3.3.37 Select "emerg data form (part II)". Report will print. Give this report to the Dose Assessment Manager. This report should be reviewed and faxed to RG&E, Wayne County, Monroe County and New York State.
6.3.3.38 Return to step 6.3.2 for more survey team calculations. To perform other calculations, select "exit" from the top of the screen.
6.4 Use of RASCAL for determination of exposure due to field samples.
6.4.1 Start RASCAL by clicking on the icon labeled "Shortcut to STDose3". Click OK.
6.4.2 Select "Event Type"
EPIP 2-5:8 6.4.2.1 Select "Nuclear Power Plant Reactor" then OK.
6.4.3 Select "Event Location" 6.4.3.1 Under Site Names select "Ginna" then OK 6.4.4 Select "Source Term" 6.4.4.1 Select "Effluent Release Concentrations" then OK.
6.4.4.2 Input the measurement location (i.e. plant vent, air ejector).
6.4.4.3 Under Release Period 1, Enter:
- Start date and time
- Stop date and time
- Effluent Flow Rate and select the correct flowrate unit on the right hand side.
Also on the right hand side, change the "Effluent Concentrations in:" to the units in the sample results.
6.4.4.4 Enter the radionuclides and the concentrations.
6.4.4.5 Select OK when all of the data has been entered.
6.4.4.6 Select "Release Path".
6.4.4.7 Release height should be zero.
6.4.4.8 Enter the release start date and time.
6.4.4.9 Enter the release end date and time then OK.
6.4.5 Select "Meteorology".
6.4.5.1 Select "Actual Observations and Forecasts" then "Create New".
6.4.5.2 Ensure Station is "GINN" then select "Enter Data".
6.4.5.3 Enter the date, time, wind direction, wind speed, Stability, precipitation and 33 ft temp.
6.4.5.4 Select OK.
6.4.5.5 Select "Create RASCAL Input".
6.4.5.6 Under "Save File as", name the file using the Ginna then a number (i.e. 1,2,3) then OK.
6.4.5.7 Select "View Meteorology" 6.4.5.8 Select "Observations" and review the data to ensure only the center data point has an arrow.
EPIP 2-5:9 6.4.5.9 Select "Done".
6.4.5.10 Select "Exit".
6.4.5.11 Select "Return" 6.4.5.12 Select OK 6.4.6 Select "Calculate Doses" 6.4.6.1 Under Distance Calculations select
- Close-in + out to 10 miles"
- "Defaults" 6.4.6.2 Under Building Wake correction select "on" 6.4.6.3 Input the date and time that calculations should end (typically 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after release start) 6.4.6.4 Enter case description then OK 6.4.7 Save the case using the button on the bottom left part of the screen 6.4.8 Print Results by using the Print button on the right hand side of the screen.
7.0 ATTACHMENTS 7.1 SPING Functional Ranges
SPING FUNCTIONAL RANGES 12 R-14A9 (High Range) 12 R-14A7 (Mid Range) 15 12 R-14A5 (Low Range )
15
=r CD 4
. m I I I I II U'1 I I I i I LLJ I I E-7 I
E-6 i
E-5 i
E-4 i i E-3 E-2 E-1 i
E+O E+1 E+2 E+3 0* .0 E-8 CA) uCi/cc SPING.008
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER __
PROCEDURE NO. EPIP 2-9 REV. NO. 5 ADMINISTRATION OF POTASSIUM IODIDE (KI)
EFFECTIVE DATE CATEGORY 1.0 THIS PROCEDURE CONTAINS 5 PAGES
EPIP 2-9:1 EPIP 2-9 ADMINISTRATION OF POTASSIUM IODIDE (KI) 1.0 PURPOSE iodide This procedure is to provide guidelines for the administration and use of potassium (KI).
2.0 RESPONSIBILITY is 2.1 The Dose Assessment Manager or the Radiation Protection and Chemistry Manager responsible for determining the need for potassium iodide(KI).
of the 2.2 The administration of potassium iodide shall be performed only after the approval Emergency Coordinator.
3.0 REFERENCES
3.1 Developmental References of 3.1.1 NCRP Report No. 55 "Protection of the Thyroid Gland in the Event of Releases Radioiodine."
3.1.2 Federal Register Vol. 47 28158, June 29, 1982.
3.1.3 THYROBLOCK, Instruction Sheet, Wallace Laboratories.
3.1.4 Nuclear Emergency Response Plan 3.1.5 New York State Radiological Emergency Preparedness Plan.
3.2 Implementing References None.
4.0 PRECAUTIONS options, 4.1 The use of KI should be considered in conjunction with other available protective including respiratory protective devices and limited stay-times.
4.2 The use of potassium iodide (KI) is voluntary.
EPIP 2-9:2 4.3 KI should not be administered to personnel who know they are allergic to iodide or have dermatitis herpetiformis or hypocomplementenic vasculitis..
I 4.4 Individuals with multinodular goiter, grave's disease and autoimmune thyroiditis should be treated with caution especially if dosing extends beyond a few days.
is the 4.5 An important factor in obtaining satisfactory blockage of acute radioiodine uptakes time of iodide administration after exposure to radioiodine. It is preferable to administer KI before or shortly after the start of exposure to achieve blockage of 90 percent or more.
A substantial benefit (e.g. a block of 50%) is attainable only during the first 3 - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the after the start of exposure. However, since the majority of radioiodine has entered thyroid gland by 10 -12 hours after exposure, little benefit may be expected by blocking beyond this time.
4.6 For chronic radioiodine exposure, KI will, of course, be useful at any time during the shortly exposure and hence should still be administer even if the drug was not given before or after the release of radioactivity.
prior to 4.7 Do not administer KI which has passed its expiration date. Check expiration date issuance.
will only 4.8 Distribution of KI to the general public is the responsibility of New York State, and be issued to the general public if approved by the New York State Department of Health.
5.0 PREREQUISITES 5.1 Any of the following conditions exist:
5.1.1 Thyroid dose to an individual(s) is projected to be greater than 10 rem.
5.1.2 Plant conditions indicate the potential for a large release of radioiodine.
6.0 ACTIONS 6.1 KI Determination 6.1.1 Dose Assessment Manager or Radiation Protection and Chemistry Manager:
- a. Determine projected thyroid dose by using the Thyroid Graph (Attachment 1).
- b. If thyroid dose is greater than 10 rem, obtain authorization from the Emergency Coordinator.
EPIP 2-9:3 CAUTION DO NOT ADMINISTER KI WITHOUT THE APPROVAL OF THE EMERGENCY COORDINATOR.
- c. A supply of KI tablets is available at the following locations:
- 2. Control Room
- 3. Survey Center
- 4. Emergency Operations Facility 6.2 KI Administration 6.2.1 Use Thyro-Block Instructions (Attachment 2) as guidance.
6.2.2 Advise all personnel that the use of KI is voluntary.
CAUTION KNOW THE ONLY PEOPLE WHO SHOULD NOT TAKE KI ARE PEOPLE WHO THEY ARE ALLERGIC TO IODIDE.
TO DO NOT ADMINISTER KI WHICH HAS PASSED ITS EXPIRATION DATE PRIOR ISSUANCE.
activated.
6.2.3 Notify the EOF Recovery Manager of the decision to Administer KI if EOF 6.2.4 Administer one KI tablet (130 mg. tablet) to each person.
6.2.5 Notify the RG&E Medical Services or the Plant Physician if KI tablets have been issued, and request assistance in follow-up administration of KI and personnel thyroid (215) 243-2990 evaluations. Consider contacting Radiation Management Consultants at for additional medical expertise.
7.0 ATTACHMENTS
- 1. Thyroid Graph.
- 2. Thyro-Block Instructions.
EPIP 2-9:4 Attachment 1, Rev. 5 Page 1 of 1 THYROID GRAPH
EPIP 2-9:5 Attachment 2, Rev. 5 Page 1 of 1 THYRO-BLOCK INSTRUCTIONS Ifyou take potassium iodide, it will fill up your thyroid gland. This THYRO-BLOCK reduces the chance that harmful radioactive iodine will enter the TABLETS thyroid gland.
(POTASSIUM IODIDE TABLETS, USP)
(Pronounced poe-:TASS-e-um EYE-oh-dyed) WHO SHOULD NOT TAKE POTASSIUM IODIDE (Abbreviated: KI) The only people who should not take potassium iodide are people who know they are allergic to iodide. You may take potassium TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC HEALTH iodide even if you are taking medicines for a thyroid problem (for OFFICIALS TELL YU. INA RADIATION EMERGENCY, example, a thyroid hormone or antithyroid drug). Pregnant and RADIOACTIVE IODINE COULD BE RELEASED INTO THE AIR. nursing women and babies and children may also take this drug.
POTASSIUM IODIDE (A FORM OF IODINE) CAN HELP PROTECT YOU. HOW AND WHEN TO TAKE POTASSIUM IODIDE IFYOU ARE TOLD TO TAKE THIS MEDICINE, TAKE IT ONE Potassium iodide should be taken as soon as possible after public TIME EVERY 24 HOURS. DO NOT TAKE IT MORE OFTEN. health officials tell you. You should take one dose every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
MORE WILL NOT HELP YOU AND MAY INCREASE THE RISK More will not help you because the thyroid can "hold" only limited OF SIDE EFFECTS. DO NOT TAKE THIS DRUG IF YOU KNOW amount of iodine. Larger doses will increase the risk of side YOU ARE ALLERGIC TO IODIDE. (SEE SIDE EFFECTS BELOW.) effects. You will probably be told not to take the drug for more than 10 days.
INDICATIONS SIDE EFFECTS THYROID BLOCKING IN A RADIATION EMERGENCY ONLY. Usually, side effects of potassium iodide happen when people take higher doses for a long time. You should be careful no to take DIRECTIONS FO USE more than the recommended dose or take it longer than you are Use only as directed by State or local public health authorities int he told. Side effects are unlikely because of the low dose and the event of a radiation emergency. short time you will be taking the drug.
DOSE Possible side effects include skin rashes, swelling of the salivary Tablets: ADULTS AND CHILDREN 1 YEAR OF AGE OR glands, and "iodism" (metallic taste, burning mouth, and throat, sore OLDER: One (!) Tablet once a day. Crush for teeth and gums, symptoms of a head cold, and sometimes stomach small children. upset and diarrhea).
BABIES UNDER YEAR OF AGE: One-half (1/2) tablet once a day. Crush first. A few people have an allergic reaction with more serious symptoms. These could be fever and joint pains, or swelling of Take for 10 days unless directed otherwise by State or local public parts of the face and body and at times severe shortness of breath health authorities. requiring immediate medical attention.
Store at controlled room temperature between 150 and 30'C (500 to Taking iodide may rarely cause overactivity of the thyroid gland, 0
85 F). Keep container tightly closed and protect from light. underactivity of the thyroid gland, or enlargement of the thyroid gland (goiter).
WARNING WHAT TO DO IF SIDE EFFECTS OCCUR Potassium iodide should not be used by people allergic to iodide.
Keep out of the reach of children. In case of overdose or allergic Ifthe side effects are severe or if you have an allergic reaction, reaction, contact a physician or the public health authority. stop taking potassium iodide. Then, if possible, call a doctor or public health authority for isntructions.
DESCRIPTION HOW SUPPLIED Each white, round, scored, monogrammed THRO-BLOCK TABLET contains 130 mg of potassium iodide. Other ingredients: THYRO-BLOCK TABLETS (Potassium Iodide Tablets, USP) are magnesium stearate, microcrystalline cellulose, silica gel, and white, round, one side scored, other side debossed 472 sodium thiosulfate. WALLACE, each containing 130 mg potassium iodide. Available in bottles of 14 tablets (NDC 0037-0472-20).
HOW POTASSIUM IODIDE WORKS Certain forms of iodine help your thyroid gland work right. Most WALLACE LABORATORIES people get the iodine they needs from foods, like iodized salt or Division of fish. The thyroid can "store" or hold only a certain amount of iodine. CARTER-WALLACE Cranbury, New Jersey 08512' In a radiation emergency, radioactive iodine may be released in the IN-0472-03 Rev. 5/94 air. This material may be breathed or swallowed. It may enter the thyroid gland and damage it. The damage would probably not show itself for years. Children are most likely to have thyroid damage.
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER ___
PROCEDURE No. EPIP 2-11 REV. NO. 19 ONSITE SURVEYS ROEPIT<LES GER o0/i5-h)2 EFFECTIVE DATE CATEGORY 1.0 THIS PROCEDURE CONTAINS 32 PAGES
EPIP 2-11:1 EPIP 2-11 ONSITE SURVEYS
1.0 PURPOSE
To describe the procedure to be followed for the conduct of onsite radiological surveys.
2.0 RESPONSIBILITY
2.1 The onsite survey team members are responsible for implementing this procedure.
2.2 The Survey Center Manager or Dose Assessment Manager is responsible for briefing, dispatch and control of the team as described in EPIP 2-7, Management of Emergency Survey Teams.
3.0 REFERENCES
3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.1.2 RP-SUR-POST-LABEL, Radiological Surveys and Area Postings 3.2 Implementing References 3.2.1 EPIP 2-8, Voluntary Acceptance of Emergency Radiation Exposure 3.2.2 EPIP 2-9, Administration of Potassium Iodide (KI).
3.2.3 EPIP 2-13, Iodine and Particulate Activity Determination from Air Samples.
3.2.4 EPIP 2-7, Management of Emergency Survey Teams.
3.2.5 EPIP 5-2, Onsite Emergency Response Facilities and Equipment Periodic Inventory Checks and Tests.
3.2.6 EPIP 1-11, Survey Center Activation
4.0 PRECAUTIONS
4.1 If the seal on the Onsite Survey Team footlocker is broken, use the equipment list inside the footlocker to inventory equipment (Equipment list from EPIP 5-2).
EPIP 2-11:2 4.2 Maintain communications contact at regular intervals with the TSC Radio Operator when performing surveys especially when significant changes to dose rates occur as described in this procedure.
5.0 PREREQUISITES
None
6.0 ACTIONS
6.1 Equipment Check/Team Preparation 6.1.1 Assemble the following equipment which is not stored in the survey footlocker:
- a. Personal thermoluminescent dosimeter (TLD) for each team member.
- b. Gilian low volume air sampler with filter holder or equivalent.
Verify the battery charge status by observing the battery voltage displayed on the battery charger. Press the button on the battery charger (for #1, 2, 3, 4, or 5) that corresponds with the air sampler that you are checking.
NOTE: IF AN AIR SAMPLER DOES NOT HAVE THE MINIMUM VOLTAGE LISTED BELOW, IT MAY NOT RUN FOR AN ADEQUATE LENGTH OF TIME. LEAVE THE AIR SAMPLER ON THE CHARGER UNTIL THE REQUIRED VOLTAGE IS REACHED. IF THE AIR SAMPLER HAS BEEN CHARGING FOR GREATER THAN 8 HOURS AND HAS NOT REACHED THE REQUIRED VOLTAGE, REMOVE IT FROM SERVICE.
- A Gilian HFS-1 13A should read 4.50v or greater on the charger.
- A Gilian HFS-513A should read 5.80v or greater on the charger.
- A Gilian Gilair-5 should read 5.80v or greater on the charger.
- c. Eberline RO-20 dose rate meter or equivalent.
- d. Eberline RM-25 Frisker or equivalent.
6.1.2 Log information required on the Survey Team Equipment/Team Data Form, Attachment 17, located on each box, and turn in to Survey Center Manager prior to departure.
EPIP 2-11:3 6.1.3 Check operation of the following equipment using the Equipment Check and Operation Instructions (Attachment 1):
NOTE: IF EQUIVALENT EQUIPMENT IS UTILIZED ENSURE EQUIPMENT CHECK AND OPERATION INSTRUCTIONS ARE PERFORMED IN ACCORDANCE WITH THE APPROPRIATE RADIATION PROTECTION PROCEDURES.
- a. Hand-held radio with extra battery pack and 9 AA batteries. (Attachment 1)
NOTE: SURVEY METERS ARE RESPONSE CHECKED PRIOR TO USE, DAILY WHILE IN USE, AND PRIOR TO STORING THEM AFTER USE. USE ATTACHMENT 16 TO RECORD DAILY CHECKS AND PRIOR TO STORING METERS.
- a. Eberline RM-25 Frisker (Attachment 2)
- c. Eberline Model RO-20 dose rate meter (Attachment 3)
- d. Gilian low volume air sampler (Attachment 4)
- e. VAS-2 Earmark "Loud Mouth" Voice Amplification System (Attachment 5)
NOTE: THE PLANT HAS 2 FOUR WHEEL DRIVE VEHICLES AVAILABLE FOR ADVERSE WEATHER CONDITIONS.
(CONTACT MAINTENANCE MANAGER IN TSC.)
6.1.4 Load survey equipment in equipment bags and back packs and inform Survey Center Manager you are ready for departure. Obtain meteorological and plant status information. Document Team readiness on Survey Team Attachment Form (Attachment 15).
6.1.5 Log time, date and survey team members on survey map.
6.1.6 Establish radio communication with Technical Support Center Radio Operator and advise of teams departure.
6.1.7 When taking air samples, log time, date, flow rate and start time of low volume air sampler on air sample envelopes and RG&E Emergency Survey Team Data Sheet (Attachment 14).
6.1.8 If directed by the Dose Assessment Manager, don protective clothing and full face masks with charcoal filters and VAS-2 Earmark "loud mouth" voice amplifier.
EPIP 2-11:4 6.2 Team Briefing 6.2.1 Survey Center Manager or Dose Assessment Manager brief the Survey Team Members.
6.2.2 Ensure that the briefing covers the following items:
- a. Team Identification
- b. Communications Equipment and Channel
- c. 3-way communications and use of the phonetic alphabet
- d. Protective Equipment (including use of KI)
- e. Authorized doses
- f. Survey Instructions
- g. Survey Equipment
- h. Type of Data Required
- i. Job Safety Briefing 6.2.3 If dose authorization is required, implement EPIP 2-8, Voluntary Acceptance of Emergency Radiation Exposure.
6.2.4 If potassium iodide (KI) administration is required, take one KI tablet at this time in accordance with EPIP 2-9, Administration of Potassium Iodide (KI).
6.3 Survey 6.3.1 Perform surveys using the appropriate Survey Instructions (Attachment 6,7,8,9 and 10).
6.3.2 Follow the Survey Route for your team designation (Attachment 11 or 12).
EPIP 2-11:5 CAUTION DO NOT ENTER AREAS WHERE RADIATION LEVELS ARE GREATER THAN 2 REM/HR UNLESS DIRECTED BY THE HEALTH PHYSICIST.
THE DOSE LIMITATION OF THE SURVEY TEAM IS LIMITED TO 1 REM (TEDE) UNLESS THE HEALTH PHYSICIST OR EMERGENCY COORDINATOR AUTHORIZES A HIGHER LIMIT.
A ONETIME DOSE LIMIT OF 75 REM (TEDE) MAY BE USED TO SAVE THE LIFE OF AN INDIVIDUAL ON A VOLUNTARY BASIS.
A ONETIME DOSE LIMIT OF 25 REM (TEDE) MAY BE USED TO INSURE EQUIPMENT IS OPERATIONAL OR SECURED IN ORDER TO PREVENT A GREATER POSSIBLE HAZARD TO THE GENERAL PUBLIC.
6.3.3 At each assigned report point, the team should report the following information to the Radio Operator:
- a. Location
- b. Completed Actions
- c. Results of Surveys NOTE: REMEMBER TO CHECK THE SCALE BEFORE RECORDING READINGS ON A SURVEY MAP OR REPORTING READINGS TO DOSE ASSESSMENT.
- d. Request for additional instructions 6.3.4 Upon completion of Survey Route, inform radio operator at Technical Support Center. The Dose Assessment Manager may assign an additional survey route or direct you to return to the Survey Center.
6.3.5 Document route completion on Survey Team Attachment Form (Attachment 15).
6.4 Decontamination/Sample Return 6.4.1 Inform Survey Center Manager of team return to the Survey Center.
6.4.2 Perform a personnel frisk of team personnel in accordance with Attachment 8.
Document results on Survey Team Attachment Form (Attachment 15).
EPIP 2-11:6 6.4.3 If any contamination greater than 100 CPM above background is found, contact the Survey Center Manager for decontamination instructions.
6.4.4 Give all air sample filters, survey maps, data records and attachment forms to the Survey Center Manager. Ensure all information is complete and samples are properly labeled.
6.4.5 Dispose of contaminated and potentially contaminated waste in designated containers.
6.4.6 Perform a contamination survey of equipment in accordance with Attachment 8.
Re-stock and inventory the Survey Team Equipment Footlocker. Stow equipment in its designated location.
6.4.7 Return radio system, portable air sampler, frisker and dose rate meter to the Survey Center Equipment Area and place on charge as appropriate. Response check survey meter (s) prior to returning to storage. Notify the Survey Center Manager if any meter(s) do not response check properly.
6.4.8 Return dosimeters and sign-out on dosimeter log sheet from EPIP 1-11.
6.4.9 If directed by the Dose Assessment Manager, receive a whole body count to check for internal contamination.
7.0 ATTACHMENTS
EQUIPMENT CHECK AND OPERATING INSTRUCTIONS
- 1. Radio System
- 2. Eberline RM-25 Frisker
- 3. Eberline model RO-20 Dose Rate Meter
- 4. Gilian Low Volume Air Sampler
- 5. VAS-2 Earmark "Loud Mouth" Voice Amplification System SURVEY INSTRUCTIONS
- 6. General Area Radiation Survey
- 7. Survey to Determine Presence of Beta Radiation-Plume Survey
- 8. Contamination Survey
- 9. Taking Air Samples
- 10. Changing Filters at Fixed Environmental Stations
EPIP 2-11:7
- 11. Survey Route (Onsite East)
- 12. Survey Route (Onsite West)
- 13. Onsite Survey Map
- 14. RG&E Emergency Survey Team Data Sheet
- 15. Survey Team Attachment Form
- 16. EPIP Instrument Response Check
- 17. Survey Team Equipment/Team Data Form
EPIP 2-11:8 Attachment 1, Rev. 19 Page 1 of 2 RADIO SYSTEM (HAND-HELD PORTABLE)
EQUIPMENT CHECK AND OPERATION
- 1. Remove radio from the charger rack.
- 2. Switch on the transceiver by turning the power switch/volume control clockwise until it clicks.
- 3. Adjust the volume by turning the power switch/volume control knob to the desired volume.
NOTE: CHANNEL IDENTIFICATION IS INDICATED ON THE DISPLAY LOCATED ON THE TOP OF THE RADIO.
- 4. Turn the channel selector switch to the General Maintenance frequency.
- 5. Transmit a test message for a communications check using the 3-way communications protocol given below:
- a. The general procedure for communication on the radio should be as follows:
- 1. During a drill or exercise, all information transmitted via radio shall be proceeded with 'This is a drill/exercise."
- 2. The message should include the name or title of the receiver, name or title of the sender and the message text.
Example: 'This is a drill. Technical Support Center, this is the Alpha Survey Team. We are starting our primary route, over."
- 3. Message acknowledgment by the receiver to include the name or title of the sender and the title of the acknowledging receiver. The acknowledging receiver should paraphrase or repeat back the message.
Example: "This is a drill. Alpha Survey Team, this is the Technical Support Center. I understand you are starting your primary route, over."
EPIP 2-11:9 Attachment 1, Rev. 19 Page 2 of 2
- 4. Sender confirmation - confirmation of the acknowledgment.
Example: 'This is a drill. Technical Support Center, this is the Alpha Survey Team. That is correct."
- 2. When communicating alpha-numeric information, such as survey team designation or meter readings, where the sender or receiver may encounter background noise or static, the phonetic alphabet should be used.
- 3. If the receiver does not understand the message, they are expected to ask the sender to repeat or rephrase the message. If the receiver acknowledges the message incorrectly, the sender should correct the receiver by saying "that is not correct" and repeating the message.
- 4. Confirmation of the acknowledgment by the sender is imperative. The absence of the confirmation step could result in a mis-communication because the receiver may have misheard the message and repeats back erroneous information. A lack of response by the sender could be interpreted as a silent confirmation that the repeat back is correct.
NOTE: THERE MAY BE TIMES THAT TSC OR EOF WILL BE RECEIVING COMMUNICATIONS FROM A TEAM THAT YOU CANNOT HEAR. IF THIS HAPPENS, THE RADIO OPERATOR WILL TELL YOU TO WAIT OR STANDBY. AFTER HE HAS COMPLETED HIS TRAFFIC, HE WILL ASK YOU TO TRANSMIT YOUR INFORMATION.
- 6. To transmit: depress the push-to-talk switch on the side of the radio. Speak in a normal voice into the speaker/mike.
- 7. To receive: release the push-to-talk switch.
- 8. When you have been directed to secure your survey team, turn the radio off and place it in the charger located in the Survey Center Equipment area.
EPIP 2-11:10 Attachment 2, Rev. 19 Page 1 of 1 EBERLINE RM-25 FRISKER EQUIPMENT CHECK
- 1. Disconnect power cord from the back of the meter. Ensure "TEST ON" toggle switch is off.
- 2. Ensure that an HP-260 pancake probe or equivalent is connected to the Detector connector on the front of the instrument.
- 3. Turn range switch to HV position. Meter should read the high voltage indicated on the calibration sticker.
- 4. Press Battery Test button on the back, lower left side of the meter. Meter should read in the green Battery Check area.
- 5. Turn range switch to Alarm position. Set alarm with HV/Alarm toggle switch to desired alarm point.
- 6. Perform instrument response check. Obtain source from safe and verify meter reading corresponds to reading on attached card. Log on response check log (Attachment 17), whether response check was satisfactory or not, and submit to Survey Center Manager.
- 7. Turn range switch to OFF when not in use.
EQUIPMENT OPERATIONS
- 1. Turn range switch to X1.
- 2. Place response switch in the Slow Response position.
- 3. Adjust the volume control so that the audio indication (a click) can be heard.
- 4. Set Alarm to 500 (maximum scale reading).
- 5. The range switch should be adjusted such that the highest reading gives a mid scale deflection.
- 6. All readings must be multiplied by the range switch setting, i.e. (X1, X1 0, X1 00, X1K).
- 8. Check battery level frequently when using the meter of battery power.
- 9. Upon completion of the survey, return meter to the Survey Center Equipment Area and response check. Turn the meter off and return to storage if response check is satisfactory. Notify the Survey Center Manager if the instrument does not response check properly. Unit should be recharged before the next use.
EPIP 2-11:11 Attachment 3, Rev. 19 Page 1 of 2 EBERLINE MODEL RO-20 DOSE RATE METER EQUIPMENT CHECK
- 1. Turn function switch to Battery 1 position. Ensure meter reading is in green Battery Check arc.
- 2. Turn function switch to Battery 2 position. Ensure meter reading is in green Battery Check arc.
- 3. If either of these checks are unsatisfactory, turn survey meter in to Survey Center Manager.
- 4. Turn function switch to Zero position. Check that meter reads zero. If not, set it to zero with the Zero knob.
- 5. Set the function switch to the 5 mR/hr. Range. Obtain response check source from the safe and verify that the meter reading corresponds to the reading on the source card. Use the open window reading. Log on response check log (Attachment 17), whether response check was satisfactory or not, and submit to Survey Center Manager.
- 6. Turn meter off when not in use.
EQUIPMENT OPERATION
- 1. Turn function switch to Battery 1 position. Ensure meter reading is in green Battery Check arc.
- 2. Turn function switch to Battery 2 position. Ensure meter reading is in green Battery Check arc.
- 3. If either of these checks are unsatisfactory, turn survey meter in to Survey Center Manager.
- 4. Set function switch to the desired range of operation. The switch position selected is the full scale reading of that range.
- 5. When surveying an area of unknown radiation, always start the survey at the higher scales and move to a lower scale until readings are between 10% and 90% of that scale.
NOTE: REMEMBER TO CHECK THE SCALE SETTING BEFORE RECORDING READINGS ON A SURVEY MAP OR REPORTING READINGS TO DOSE ASSESSMENT.
EPIP 2-11:12 Attachment 3, Rev. 19 Page 2 of 2
- 6. For low light conditions, set the Light toggle switch to either On for continuous illumination or Momentary for momentary illumination. When not needed, ensure Light switch if returned to the Off position to conserve batter power.
- 7. Upon completion of the survey, return meter to the Survey Center Equipment Area and response check. Turn the meter off and return to storage if the response check is satisfactory. Notify Survey Center Manager if the meter does not response check satisfactorily.
EPIP 2-11:13 Attachment 4, Rev. 19 Page 1 of 2 GILIAN HFS-113A AIR SAMPLER, GILIAN HFS-513A AIR SAMPLER GILIAN GILAIR-5 AIR SAMPLER EQUIPMENT CHECK OF GILIAN AIR SAMPLERS
- 1. Perform all sampler checks prior to use as follows:
- a. Verify calibration is current by checking the calibration sticker.
NOTE: THE PARTICULATE FILTER IS INSTALLED WITH THE TEXTURED SIDE FACING OUT. THE SILVER ZEOLITE CARTRIDGE HAS ARROWS ON ITS SIDE TO INDICATE THE DIRECTION OF THE SAMPLE FLOW.
- 2. Ensure the sample head is attached to the sampler inlet. Install new filters in the sample head.
OPERATION OF THE GILIAN HFS-113A AND GILIAN HFS-513A
- 1. Ensure filter cartridge contains a GY-130 Silver Zeolite cartridge and particulate filter.
Ensure sample head is connected to the sampler.
CAUTION MASTER ON/OFF SWITCH MUST BE ON FOR UNIT TO OPERATE. MASTER ON/OFF SWITCH ALSO RESETS TIME DISPLAY.
- 2. At start of the sampling period record start time. PRESS TEST button and record time in digital display and flow of 4.0 LPM on sample envelope and on RG&E Emergency Survey Team Data Sheet, Attachment 14. Turn unit on using ON/OFF switch located to the right of the digital display.
CAUTION IF A FAULT CONDITION EXISTS, UNIT SHUTS DOWN AFTER 15-30 SECONDS INTO A FAULT CONDITION.
- 3. If the FAULT LED is lit, this was activated by either an under voltage, over current, or over pressure (restricted flow) condition beyond the units capability. The motor stops and the time is latched. By pressing the TEST button, the sample time (in minutes) at which the fault occurred will be displayed indicating a valid sample period.
EPIP 2-11:14 Attachment 4, Rev. 19 Page 2 of 2
- 4. At end of the sampling period, turn pump off using ON/OFF switch located to the right of digital display. Press TEST button, record time in digital display, stop time and all other pertinent information on sample envelope and Attachment 14.
- 5. Sample volume in liters equals the flow rate in liters per minute multiplied by minutes the sampler operated. The sampler has a fixed flow rate of 4 liters per minute. If the unit was operated for thirty minutes, the sample volume would equal 120 liters (4 x 30 = 120).
- 6. Handle completed samples in accordance with Attachment 9 'Taking Air Samples".
OPERATION OF THE GILIAN GILAIR-5
- 1. Turn the power switch to the ON position.
- 2. Record the start time and the run time on the digital display and a flow of 4.0 LPM on sample envelope and on RG&E Emergency Survey Team Data Sheet, Attachment 14.
- 3. During use, periodically check the unit to ensure that it does not have a fault condition.
NOTE: A LIT FAULT LED MAY BE CAUSED BY:
- UNDER VOLTAGE
° OVER CURRENT
- OVER PRESSURE (RESTRICTED FLOW).
- 4. If the FAULT LED comes on during sampling, perform the following:
- a. Check the digital display to determine how long the sample ran.
- b. Determine the fault condition if possible and correct.
- c. If the condition causing the fault is corrected and work is continuing, turn the unit off to reset it, and then restart it. Be sure to add the previous run time to the total run time of the sample.
If the cause of the fault cannot be determined, remove the unit from service.
- 5. At the end of the sampling period, look at the digital display and note the total run time of the air sampler. Turn the sampler OFF. Record the run time from the display, stop time and all of the other pertinent information on Attachment 14.
- 6. Sample volume in liters equals the flow rate in LPM multiplied by the minutes the air sampler was operated. If the unit was operated for thirty minutes, the sample volume would equal 120 liters (4LPM x 30 minutes = 120 liters).
EPIP 2-11:15 Attachment 5, Rev. 19 Page 1 of 3 VAS - 2 EARMARK "LOUD MOUTH" VOICE AMPLIFICATION SYSTEM The "Loud Mouth" System is designed to provide voice amplification for individuals wearing respiratory protection devices.
EQUIPMENT CHECK Earmark Throat Microphone Model TM-1
- 1. Figure 1 (attached) shows the proper "at rest" position for the microphone. If it is necessary to reform the spring tension, hold the microphone, starting two inches behind the microphone head, between the thumb and forefinger and bend the cable slightly while progressing down the cable until the end of the spring is reached. Check the diameter of the coil and repeat if necessary. Note that the microphone head should tilt up from a flat surface about 1/4 inch. If necessary, form the spring to give this dimension.
- 2. Batteries: A 9-volt Alkaline Battery is the required power source. The battery is located in the amplifier unit. To replace the batteries, remove the cover plate to the battery compartment. Pull plastic tab, remove and replace the battery.
Note: Small terminal (+) in first.
EQUIPMENT OPERATION
- 1. Ensure microphone cable is securely connected to jack on voice amplifier.
- 2. The microphone is designed to be located on the right side of the throat (see figure 2). The microphone must lay flat on the neck and press firmly into the throat.
- 3. Securely fasten amplifier unit to belt.
CAUTION WHEN COMMUNICATING THROUGH RADIO, TELEPHONE, ETC., SPEAK PRECISELY. KEEP SPEAKER AT LEAST 12" FROM THROAT MIC. KEEP THE MEANS OF COMMUNICATION 12" FROM THE THROAT MIC. HOLD MEANS OF COMMUNICATION OFF TO SIDE OF SPEAKER. IF ANY FEEDBACK IS APPARENT, LOWER VOLUME.
EPIP 2-11:16 Attachment 5, Rev. 19 Page 2 of 3
- 4. To operate unit, turn volume control clockwise, the TALK slide switch has two (2) positions; up is the standby mode and down is the talk mode. Slide TALK switch to down position to talk. Adjust volume to desired level with VOLUME control.
- 5. Turn unit off by turning volume control counter clockwise as fast as it will turn.
Leave talk switch in the standby position.
EPIP 2-11:17 Attachment 5, Rev. 19 Page 3 of 3 EQUIPMENT CHECK AND OPERATION INSTRUCTIONS Wel On a flat surface the mic should rest about 1/4" above said surface When mic is laid on a flat surface it should form a circle 2 to 2 /" in distance. Depending on user size. If it has been stretched to form a larger circle the inbuilt spring wire should be reformed to produce the diameters indicated.
This insures proper throat pressure for optimum sound quality.
Fig. 1 Mic to press on right side of wearers voice box.
Fig. 2
EPIP 2-11:18 Attachment 6, Rev. 19 Page 1 of 1 GENERAL AREA RADIATION SURVEY
- 1. A general radiation area survey should be conducted while moving between defined survey points, and at the specific survey points.
- 2. The survey should be conducted using a Eberline RO-20 dose rate meter or equivalent.
- 3. Normally, radiation readings are taken at 3 feet with the Beta window closed.
- 4. Record results on a survey map.
CAUTION IF RADIATION LEVELS ARE GREATER THAN 100 MR/HR, COMPLETE THE SURVEY AND RETREAT TO A LOWER DOSE AREA PRIOR TO REPORTING RESULTS TO KEEP YOUR EXPOSURE ALARA.
- 5. If a reading of 1 mr/hr or greater is detected, stop and conduct a survey for Beta radiation in accordance with Attachment 7. Record results on the RG&E Emergency Survey Team Data Sheet, Attachment 14 and immediately report the results of the survey to the Radio Operator.
EPIP 2-11:19 Attachment 7, Rev. 19 Page 1 of 1 SURVEY TO DETERMINE PRESENCE OF BETA RADIATION PLUME SURVEY
- 1. If the General Area Radiation Survey indicates a reading of 1 mr/hr or greater, or if the "plume" is suspected to be in your area, a survey to detect the presence of Beta radiation should be conducted:
- 2. Using a Eberline RO-20 dose rate meter, conduct the following surveys:
- a. With a meter held at waist level (3 feet):
Beta shield open Beta shield closed Difference #1 = (opened reading - closed reading)
- b. With the meter held at ground level (3 inches)
Beta shield open Beta shield closed Difference #2 = (open reading - closed reading)
- 3. If either difference #1 or difference #2 from Step 2 is positive, this is an indication that Beta radiation is present.
- a. If both difference #1 and #2 are positive, this is an indication that you are in the plume.
- b. If only difference #2 is positive, this is an indication of ground contamination.
- 4. Record survey results on RG&E Emergency Survey Team Data Sheet, Attachment 14.
- 5. Report the results of the survey to the Radio Operator and await further instructions from the Dose Assessment Manager.
EPIP 2-11:20 Attachment 8, Rev. 19 Page 1 of 2 CONTAMINATION SURVEY COLLECTING AND COUNTING SMEAR SAMPLES NOTE: DO NOT TOUCH METER PROBE TO ANY SURFACE BEING SURVEYED. PROBE CONTAMINATION MAY RESULT.
BACKGROUND COUNT RATE SHOULD BE BELOW 200 CPM TO BE SENSITIVE ENOUGH TO DETECT LOW LEVELS OF CONTAMINATION.
PERSONNEL FRISK
- 1. Obtain a RM-25 with a HP-260 pancake probe or equivalent frisker.
- 2. Check the background count rate.
- 3. Slowly pass the meter probe over a person (i.e., within 1/2 inch from the person) moving it at a rate of 1 to 2 inches per second.
- 4. Listen to the audible count rate and watch the meter for any increases.
- 5. Resurvey areas showing an increased count rate.
- 6. When contamination is suspected, hold the detector over that area for 15 seconds to obtain the gross count rate.
- 7. Subtract the background count rate from the gross count rate. This is the net count rate in CPM.
- 8. Notify the Survey Center Manager if the net count rate is greater than 100 CPM.
DIRECT FRISK SURVEY (OBJECTS)
- 1. Obtain a RM 25 with a HP-260 pancake probe or equivalent frisker.
- 2. Check the background count rate.
- 3. Slowly pass the meter probe over an object or area surface (i.e., within 11/22 inch from it) moving it at a rate of 1 to 2 inches per second.
- 4. Listen to the audible count rate and watch the meter for any increases.
- 5. Resurvey areas showing an increased count rate.
EPIP 2-11:21 Attachment 8, Rev. 19 Page 2 of 2
- 6. When contamination is suspected, hold the detector over that area for 15 seconds to obtain the gross count rate.
- 7. Subtract the background count rate from the gross count rate. This is the net count rate in CPM.
- 8. Notify the Survey Center Manager if the net count rate is greater than 250 CPM.
SMEAR SURVEY
- 1. Obtain cloth smear with adhesive backing mounted on waxed paper.
- 2. Obtain a RM-25 with a HP-260 pancake probe or equivalent frisker.
- 3. Check the background count rate.
- 4. Mark the smears with sequential numbers (e.g., 1,2,3,....).
- 5. Holding the smear paper between the thumb and index and middle fingers and 2
applying medium pressure, smear an area 100 cm (approximately 4 inches by 4 inches). A 16-inch "S"pattern can also be used.
- 6. Record the smear location by writing the smear number on the map and circling it.
- 7. Hold the smear paper within 1/2 inch of the meter probe until the meter indication stabilizes. This is the gross count in CPM.
- 8. Subtract the background count rate from the gross count rate. This is the net count rate in CPM.
Record the net count as CPM/1 00 cm in the smears table of the map next to 2
9.
corresponding smear number.
NOTE: THIS NOTICE DOES NOT APPLY TO ENVIRONMENTAL SMEARS
- 10. Notify the Survey Center Manager if the net count rates exceed 1000 CPM/100 cm 2.
- 11. Return completed contamination surveys and smears to the Survey Center Manager.
EPIP 2-11:22 Attachment 9, Rev. 19 Page 1 of 1 TAKING AIR SAMPLES
- 1. Air samples are drawn using the following equipment:
- a. LOW VOLUME - Using a Gilian HFS-1 13A low volume air sampler draw approximately 120 liters of air through a particulate filter and a GY-130 silver zeolite cartridge. This will take approximately 30 minutes.
- 2. Record the sample date, time, location (either survey point number or road intersection), and initials on the sample envelope and on RG&E Emergency Survey Team Data Sheet (Attachment 14).
- 3. Using clean, disposable gloves, remove the particulate filter and silver zeolite cartridge from the sample holder and place in the sample envelope.
- 4. Remove the disposable gloves and discard in a plastic bag. Treat as potentially contaminated material.
- 5. Return the sample to the Survey Center for gross analysis at the completion of your assigned route or when directed by the Dose Assessment Manager.
EPIP 2-11:23 Attachment 10, Rev. 19 Page 1 of 2 CHANGING FILTERS AT FIXED ENVIRONMENTAL STATIONS
- 1. Record the following information on the sample envelope left from the previous filter change:
- a. Date
- b. Time
- c. System Vacuum (inches)
- d. Gas meter reading (cubic feet)
- e. Total hour meter reading (record in column marked "OFF")
- f. Initials of person changing filters
- 2. Turn pump off.
- 3. Using clean, disposable gloves, remove the filter holder at the quick disconnect joint.
- 4. Unscrew the outside retaining ring and remove the particulate filter from the holder and place in the sample envelope.
- 5. If a charcoal or zeolite cartridge was used, transfer the information from the particulate filter envelope to a new envelope and place the cartridge in the envelope.
NOTE: PARTICULATE FILTER IS INSTALLED WITH TEXTURED SIDE FACING OUT. SILVER ZEOLITE CARTRIDGE HAS ARROW ON SIDE TO INDICATE DIRECTION OF SAMPLE FLOW.
- 6. Reassemble the filter holder installing a new GY-1 30 silver zeolite cartridge and a particulate filter.
- 7. Reconnect the filter holder to the pump at the quick disconnect joint.
- 8. Remove disposable gloves and place in a plastic bag. Treat as potentially contaminated material.
- 9. Turn the pump on.
EPIP 2-11:24 Attachment 10, Rev. 19 Page 2 of 2
- 10. Record the following information onto two new envelopes. Mark one envelop "GY-1 30 silver zeolite".
- a. Station number
- b. Date
- c. Time
- d. System vacuum (inches)
- e. Gas meter reading (cubic feet)
- f. Total hour meter reading (record in the "ON" column)
- g. Initials of person starting sampler
- 11. Place the new envelopes inside the monitor cabinet.
- 12. Bring the envelopes containing the removed cartridge and filter to the Survey Center at the completion of your assigned route or when directed by the Dose Assessment Manager.
EPIP 2-11:25 Attachment 11, Rev. 19 Page 1 of 1 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
SURVEY ROUTE (ONSITE EAST)
- 1. Proceed north and east from the Survey Center surveying between the Training Center East building and Deer Creek. (see Attachment 13).
- 2. Turn south across the lawn and proceed to environmental station #4 and change the filter and cartridge per instructions in Attachment 10.
- 3. Proceed southeast to Manor House driveway, follow driveway to where it turns north, proceed east out of the trees into orchard.
- 4. Go through orchard, then turn north and proceed to environmental station #3 and change the filter and cartridge per instructions in Attachment 10.
- 5. Proceed west across field and through woods to Manor House driveway.
- 6. Go north on Manor House driveway to the lake shore.
- 7. Proceed east to environmental station #2 and change the filter and cartridge per instruction in Attachment 10.
- 8. Proceed west along the lake shore to the plant fence.
- 9. Proceed along the plant fence to the Guard House.
- 10. Report to the Radio Operator that the survey route has been completed noting any unusual radiological conditions and are awaiting further instructions.
EPIP 2-11:26 Attachment 12, Rev. 19 Page 1 of 1 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
SURVEY ROUTE (ONSITE WEST)
- 1. Proceed west from the Survey Center to the plant access road (see Attachment 13).
- 2. Continue north across the bridge to environmental station #5 and change the filter and cartridge per instructions in Attachment 10.
- 3. Proceed west along Deer Creek and the parking lot to environmental station #6 and change the filter and cartridge per instructions in Attachment 10.
- 4. Proceed west approximately 100 yards.
- 5. Turn north towards the hill, to the northwest corner of the plant fence.
- 6. Proceed south along the plant fence to environmental station #7 and change the filter and cartridge per instructions in Attachment 10.
- 7. Continue along the plant fence to the Guard House.
- 8. Report to Radio Operator that the survey route has been completed noting any unusual radiological conditions and are awaiting further instructions.
Date: Time:
a GINNA STATION I Onsite East Route: Team Name I I I I I ON-SITE SURVEY MAP
- 1. 2.
g .1 I Onsite West Route: Team Name I I 4 A4
'7"R I 1 1. 2.
I I 4 Air Monitoring Station
£ I O Thermoluminescent Dosimeter Locations I
I I
I I
I I
I-N .-4 w-a b
M
-I Co Hiles
__C -
-4 0*
B .B** .0S .64 .0nO 4.
EPIP 2-11:28 Attachment 14, Rev. 19 Page 1 of 2 RG&E EMERGENCY SURVEY TEAM DATA SHEET
- 1. DATA FROM: oRG&E o WAYNE COUNTY o MONROE COUNTY
- 2. A. DATE: B. TIME: C. DATA SHEET NO.:
D. TEAM:
E. LOCATION:
A. SURVEY UNITS: (CIRCLE ONE) CPM MICRO-R/HR MR/HR R/HR 3.
B. SURVEY METER: (CIRCLE ONE) CDV-700 CDV-715 EBERLINE RO-20 BICRON METER NO.
- 4. WAIST LEVEL (3 FEET) READINGS:
A.. OPEN WINDOW B. CLOSED WINDOW
- 5. GROUND LEVEL (3 INCHES) READINGS:
A.. OPEN WINDOW B. CLOSED WINDOW
- 6. AIR SAMPLING COLLECTION TIMES:
A. TIME ON: B. TIME OFF: C. MINUTES RUN:
- 7. AIR SAMPLING FLOWRATES:
A. LPM START: B. LPM END: C. LPM AVERAGE:
- 8. PARTICULATE CPM: SURVEY METER SERIAL NO.
A. CONTACT: B. 1"
- 9. IODINE CPM:
A. CONTACT: B. 1"
- 10. BACKGROUND CPM:
- 11. COMMENTS AND ADDITIONAL DATA:
0 THIS IS A DRILL T A THIS IS NOT A DRILL
EPIP 2-11:29 Attachment 14, Rev. 19 Page 2of 2 NOTE: THIS DOES NOT NEED TO BE FILLED OUT FOR TRANSMISSION TO OTHER AGENCIES.
RADIOIODINE:
(8.50 E-8) @ 1' (CPM SAMPLE - CPM BACKGROUND) (4.13 E-8) ON CONTACT = _ UCI/CC (MINUTES RUN) (LPM AVERAGE) RADIOIODINE PARTICULATE:
(9.83 E-9) @ 1" (CPM SAMPLE - CPM BACKGROUND) (3.47 E-9) ON CONTACT = UCI/CC (MINUTES RUN) (LPM AVERAGE) PARTICULATE RADIOIODINE DOSE CONVERSION CHILD THYROID (CDE) DOSE RATE FACTORS (REM/HR PER UCI/CC)
HR DCF HR DCF (UCI/CC) (DCF) = REM/HR 1 5.4E5 7 9.3E5 CHILD THYROID 2 6.4E5 8 9.3E5 3 7.3E5 9 1.0E6 4 8.0E5 10 1.1E6 5 8.7E5 11 1.1E6 6 8.7E5 12 1.1E6 PERFORMED BY:
NAME DATE/TIME CHECKED BY:
NAME DATE/TI ME 11 THIS IS A DRILL T A THIS IS NOT A DRILL
EPIP 2-11:30 Attachment 15, Rev. 19 Page 1 of 1 SURVEY TEAM ATTACHMENT FORM SURVEY TEAM:
INITIALS METER REMARKS NOT USE THIS FORM TO DOCUMENT INFORMATION REGARDING SURVEY TEAM COVERAGE DOCUMENTED ON SURVEY MAPS OR FORMS.
EPIP 2-11:31 Attachment 16, Rev. 19 Page 1 ol RAD. PROTECTION & CHEMISTRY Category: EPIP INSTRUMENT RESPONSE CHECK EPIP Instruments DATE:
Subject:
Date:
Reviewed:
nfQl= DAT = MI::TFI=:PQI FRISKERS Model Serial # Response Tech Model Serial # Response/Alarm Tech Check Sat. Initials Check Sat. Initials YorN YorN 1
2 2 3 3 4 4 5 5 6 6 7 7 8 8 9 9 10 10 11 11 12 12 13 13 14 14 _ _ _
EPIP 2-11:32 Attachment 17, PageRev.
1 of191 Survey Team Equipment / Team Data Cell Phone # Date / Time Team T Team Team Member#1 Team Member#2 TLD #
TLD #
0-1500 mR 0-1500 mR Dosimeter #
Dosimeter # Initial Reading Final Reading Initial Reading _Final Reading 0-10 R 0-10 R Dosimeter #
Dosimeter # Initial Reading Final Reading Initial Reading Final Reading Scott A - ID #
Scott A--ID # MI Meter / Frisker Data Meter Serial # Calibration Response Check Battery Check Flow Check Date Y or N RO -20 ____
I RM-25 ____
RADECO GILIAN _ ......
Comments:
ROCHESTER GAS & ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER ,k PROCEDURE NO. EPIP 2-12 REV. NO. 22 OFFSITE SURVEYS EFFECTIVE DATE CATEGORY 1.0 THIS PROCEDURE CONTAINS 49 PAGES
EPIP 2-12:1 EPIP 2-12 OFFSITE SURVEYS 1.0 PURPOSE To describe the procedure to be followed for the conduct of offsite radiological surveys.
2.0 RESPONSIBILITY 2.1 The offsite survey team leader is responsible for implementing this procedure.
2.2 The Emergency Survey Center Manager or Dose Assessment Manager is responsible for briefing, dispatch, and control of the team as described in EPIP 2-7, Management of Emergency Survey Teams.
3.0 REFERENCES
3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.1.2 RP-SUR-POST-LABEL, Radiological Surveys and Area Postings.
3.1.3 PCN 944253 to EPIP 2-12, position statement subject "Action Level for smears taken by Survey Teams during Emergency Response", dated 5/24/94.
3.2 Implementing References 3.2.1 EPIP 2-8, Voluntary Acceptance of Emergency Radiation Exposure.
3.2.2 EPIP 2-9, Administration of Potassium Iodide (KI).
3.2.3 EPIP 2-13, Iodine and Particulate Activity Determination From Air Samples 3.2.4 EPIP 2-7, Management of Emergency Survey Teams 3.2.6 EPIP 5-1, Offsite Emergency Response Facilities and Equipment Periodic Inventory Checks and Tests 3.2.7 EPIP 5-2, Onsite Emergency Response Facilities and Equipment Periodic Inventory Checks and Tests
EPIP 2-12:2 4.0 PRECAUTIONS 4.1 If the seal on the offsite survey team footlocker is broken, use the equipment list inside the footlocker to inventory equipment (equipment list from EPIP 5-2 for Ginna Teams, EPIP 5-1 for EOF Teams).
4.2 Maintain communications contact at regular intervals with the Radio Operator when performing surveys, especially when significant changes in dose rates occur as described in this procedure.
5.0 PREREQUISITES None.
6.0 ACTIONS 6.1 Equipment Check/Team Preparation NOTE: RAPID DEPLOYMENT SURVEY TEAM USES ATTACHMENT 22.
6.1.1 Assemble the following equipment which is not stored in the survey team footlocker:
- a. Personal thermoluminescent dosimeter (TLD) for each team member.
NOTE: EOF Survey Teams do not need Environmental TLDs.
- c. Magnetic mount for Motorola GM 300 mobile radio.
- d. Gilian low volume air sampler with filter holder or equivalent.
Verify the battery charge status by observing the battery voltage displayed on the battery charger. Press the button on the battery charger (for #1, 2, 3, 4, or 5) that corresponds with the air sampler that you are checking.
EPIP 2-12:3 NOTE: IF AN AIR SAMPLER DOES NOT HAVE THE MINIMUM VOLTAGE LISTED BELOW, IT MAY NOT RUN FOR AN ADEQUATE LENGTH OF TIME. LEAVE THE AIR SAMPLER ON THE CHARGER UNTIL THE REQUIRED VOLTAGE IS REACHED. IF THE AIR SAMPLER HAS BEEN CHARGING FOR GREATER THAN 8 HOURS AND HAS NOT REACHED THE REQUIRED VOLTAGE, REMOVE IT FROM SERVICE AND GIVE IT TO THE SURVEY CENTER MANAGER.
- A Gilian HFS-1 13 should read 4.50v or greater on the charger.
- A Gilian HFS-513 should read 5.80v or greater on the charger.
- A Gilian Gilair-5 should read 5.80v or greater on the charger.
- e. Eberline RM-25 Frisker with HP-260 pancake probe or equivalent.
- f. Eberline RO-20 dose rate meter or equivalent.
- g. RADECO H-809C Portable High Volume Air Sampler with filter holder
- h. Cellular Mobile Telephone Bicron Micro REM meter (Required by EOF Survey Team ONLY) 6.1.2 Log information required on the Survey Team Equipment/Team Data Form, to Attachment 23, located on each box and turn in to Survey Center Manager prior departure.
6.1.3 Check operation of the following equipment using the Equipment Check and Operation Instructions (Attachments 1-8):
NOTE: IF EQUIVALENT EQUIPMENT IS UTILIZED, ENSURE EQUIPMENT CHECK AND OPERATION INSTRUCTIONS ARE PERFORMED IN ACCORDANCE WITH THE APPROPRIATE RADIATION PROTECTION PROCEDURES.
- a. Radio system (Attachment 1)
- b. Cellular Mobile Telephone (Attachment 2)
NOTE: SURVEY METERS ARE RESPONSE CHECKED PRIOR TO USE, DAILY WHILE IN USE AND PRIOR TO STORING THEM AFTER USE. USE ATTACHMENT 21 TO RECORD DAILY CHECKS AND PRIOR TO STORING METERS.
- c. Eberline RM-25 Frisker (Attachment 3)
EPIP 2-12:4
- d. Eberline Model RO-20 dose rate meter (Attachment 4)
- f. Gilian low volume air sampler (Attachment 6)
- g. RADECO H809C high volume air sampler (Attachment 7)
- h. Model VAS-2 Earmark "Loud Mouth" Voice Amplification System (Attachment 8)
NOTE: THE PLANT HAS TWO (2) FOUR-WHEEL DRIVE VEHICLES AVAILABLE FOR ADVERSE WEATHER CONDITIONS.
(CONTACT MAINTENANCE MANAGER IN THE TSC.)
6.1.4 Obtain transportation and check vehicle for contamination by performing a direct frisk survey in accordance with Attachment 11.
6.1.5 If the vehicle survey indicates surface contamination greater than 250 cpm above background, contact the Survey Center Manager for instructions.
6.1.6 Load survey equipment into vehicle, and inform Survey Center Manager you are ready for departure. Participate in a pre-job brief when meteorological and plant status information are given as per step 6.2. Document readiness on Survey Team Attachment Form (Attachment 20).
6.1.7 Log time, date, and names of survey team members on survey map.
NOTE: EOF SURVEY TEAMS CONTACT EOF DOSE ASSESSMENT RADIO OPERATOR.
6.1.8 Establish radio communication with Technical Support Center Radio Operator and advise of team departure using 3-way communications and the phonetic alphabet where applicable.
6.1.9 When taking air samples, log time, date, flow rate, start time, and initials on air sample envelope(s) and RG&E Emergency Survey Team Data Sheet(s),
Attachment 19.
6.1.10 If directed by the Dose Assessment Manager, don protective clothing, full face masks with charcoal filters, and VAS-2 Earmark "Loud Mouth" Voice amplifier.
6.2 Team Briefing 6.2.1 Survey Center Manager or the Dose Assessment Manager brief the Survey Team members.
EPIP 2-12:5 6.2.2 Ensure that the briefing covers the following items:
- a. Team identification
- b. Communications equipment and channel
- c. 3-way communications and use of the phonetic alphabet where applicable
- d. Protective equipment (including use of KI)
- e. Authorized doses
- f. Survey instructions
- g. Survey equipment
- h. Type of data required
- i. Job safety briefing including traffic/vehicle safety 6.2.3 If dose authorization is required, implement EPIP 2-8, Voluntary Acceptance of Emergency Radiation Exposure.
6.2.4 If potassium iodide (KI) administration is required, take one KI tablet at this time in accordance with EPIP 2-9, Administration of Potassium Iodide (KI).
6.3 Survey CAUTION DO NOT ENTER AREAS WHERE RADIATION LEVELS ARE GREATER THAN 2 R/HR UNLESS DIRECTED BY THE HEALTH PHYSICIST.
THE DOSE LIMITATION OF THE SURVEY TEAM IS LIMITED TO 1 REM (TEDE) UNLESS THE HEALTH PHYSICIST OR EMERGENCY COORDINATOR AUTHORIZES A HIGHER LIMIT.
A ONETIME DOSE LIMIT OF 75 REM (TEDE) MAY BE USED TO SAVE THE LIFE OF AN INDIVIDUAL ON A VOLUNTARY BASIS.
A ONETIME DOSE LIMIT OF 25 REM (TEDE) MAY BE USED TO INSURE EQUIPMENT IS OPERATIONAL OR SECURED IN ORDER TO PREVENT A GREATER POSSIBLE HAZARD TO THE GENERAL PUBLIC.
EPIP 2-12:6 NOTE: A YELLOW BEACON (OFFSITE BOXES ONLY) AND SAFETY VESTS ARE INCLUDED IN THE BOXES TO BE USED FOR BETTER VISIBILITY FROM A SAFETY STANDPOINT. THEY ARE NOT REQUIRED BUT ARE RECOMMENDED FOR USE BY TEAMS ON THE ROAD.
6.3.1 Perform surveys using the appropriate Survey Instructions (Attachments 9, 10, 11, 12,13,14).
6.3.2 Follow the Survey Route Instructions (Attachments 15, 16, 17, or 18 ) for your team designation. Drive designated routes at 15 miles/hour.
6.3.3 At each assigned report point the team should report the following information to the Radio Operator:
- a. Location
- b. Completed Actions
- c. Results of Surveys NOTE: REMEMBER TO CHECK THE SCALE SETTING BEFORE RECORDING READINGS ON A SURVEY MAP OR REPORTING READINGS TO DOSE ASSESSMENT.
- d. Request for additional instructions 6.3.4 If radio contact cannot be established, or transmission interference occurs, report by cellular phone using telephone numbers given on the instructions for Radio System - Motorola GM 300 Mobile (Attachment 1) or Cellular Telephone (Attachment 2).
6.3.5 Upon completion of Primary Survey Route, inform the radio operator at Technical Support Center or Emergency Operations Facility. The Dose Assessment Manager will assign an Alternate Survey Route, have the team stand by at a designated location and wait further instructions, or direct the team to return to the Survey Center. Document completion on Survey Team Attachment Form (Attachment 20).
6.4 Decontamination/Sample Return 6.4.1 Inform Survey Center Manager when the team returns to the Survey Center.
6.4.2 Perform a contamination survey of team personnel in accordance with Attachment 11 . Document results on Attachment 20.
6.4.3 If any contamination greater than 100 CPM above background is found, contact the Survey Center Manager for decontamination instructions.
6.4.4 Conduct a vehicle contamination survey by direct frisk in accordance with Attachment 11. Document results on Attachment 20.
EPIP 2-12:7 6.4.5 If any contamination greater than 250 cpm above background is found, contact the Survey Center Manager for decontamination instructions.
6.4.6 Contact Survey Center Manager for instructions for where to return samples, survey maps, data records and attachment forms. Ensure all information is complete and samples are properly labeled.
6.4.7 Dispose of contaminated and potentially contaminated waste in designated containers.
NOTE: EOF SURVEY TEAMS SHALL PERFORM STEPS 6.4.8 THROUGH STEP 6.4.11 AFTER RETURNING TO EOF SURVEY TEAM EQUIPMENT AREA.
6.4.8 Re-stock and inventory the Survey Team Equipment Footlocker. Stow equipment in its designated location.
6.4.9 Return radio system, cellular phones, portable air sampler, radiation count rate meter, and dose rate meter to the Survey Center Equipment Area and place on charge as appropriate. Response check all survey meters prior to returning to storage. Notify Survey Center Manager if any meters do not response check properly.
6.4.10 Return dosimeters and sign-out on dosimeter log sheet.
6.4.11 If directed by the Dose Assessment Manager, receive a whole body count to check for internal contamination.
7.0 ATTACHMENTS EQUIPMENT CHECK AND OPERATION INSTRUCTIONS
- 1. Radio system - Motorola GM 300
- 2. Cellular Telephone
- 3. Eberline RM-25 Frisker
- 4. Eberline Model RO-20 Dose Rate Meter
- 5. Bicron Micro REM Meter
- 6. Gilian Low Volume Air Sampler
- 7. RADECO H809C High Volume Air Sampler
- 8. VAS-2 Earmark "Loud Mouth" Voice Amplification System
EPIP 2-12:8 SURVEY INSTRUCTIONS
- 9. General Area Radiation Survey
- 10. Survey to Determine Presence of BETA Radiation - Plume Survey
- 11. Contamination Surveys
- 12. Installation of TLD
- 13. Taking Air Samples
- 14. Changing Filters at Fixed Environmental Stations SURVEY ROUTE INSTRUCTIONS
- 15. OFFSITE EAST
- 16. OFFSITE WEST
- 17. EOF Survey Route #1
- 18. EOF Survey Route #2
- 19. RG&E Emergency Survey Team Data Sheet
- 20. Survey Team Attachment Form
- 21. EPIP Instrument Response Check
- 22. Rapid Deployment Survey Team Instructions
- 23. Survey Team Equipment/Team Data Form
EPIP 2-12:9 Attachment 1, Rev. 22 Page 1 of 3 RADIO SYSTEM - MOTOROLA GM 300 Equipment Check:
- 1. Ensure the vehicle's metal roof is free of ice and snow.
CAUTION DO NOT ATTEMPT TO MOVE THE ANTENNA BY SLIDING IT. YOU WILL SCRATCH THE SURFACE OF THE VEHICLE. ALWAYS REMOVE THE MOUNT BY LIFTING FROM THE REAR!
- 2. Hold the magnetic mount antenna in the palm of your hand with the antenna wire pointed towards the rear of the vehicle and the base of the mount at an angle of about 45 degrees to the vehicle roof.
- 3. Position the front edge of the mount in the approximate center of vehicle roof.
- 4. Lower the mount onto the vehicle roof. It will be held in place by the magnetic force.
- 5. Route the antenna lead wire into the vehicle between the 2nd door jam. With any amount of weather stripping the lead should not be damaged.
- 6. Route the antenna wire in the vehicle so that it does not interfere with operation of the vehicle.
- 7. Connect the antenna by inserting the antenna connection into the connector on the back side of the radio and tighten the locking screw in place.
- 8. Plug the power jack into automobile power receptacle.
- 9. Turn the ON/OFF-VOLUME knob clockwise (CW) until it clicks. The LED lights will show the last status of the radio and a start-up tone will be heard.
- 10. Adjust the volume as necessary.
- 11. Select the desired frequency by depressing the channel select up or down button located on the front left side of the LED display.
EPIP 2-12:10 Attachment 1, Rev. 22 Page 2 of 3
- 12. Normally use Channel #1 (General Maintenance frequency) You are now ready to receive messages from other radios in your system.
- 13. Transmit a test message for a communications check using the 3-way communications protocol given below:
- a. The general procedure for communication on the radio should be as follows:
- 1. During a drill or exercise, all information transmitted via radio shall be proceeded with "This is a drill/exercise."
- 2. The message should include the name or title of the receiver, name or title of the sender and the message text.
Example: "This is a drill. Technical Support Center, this is the Alpha Survey Team. We are starting our primary route, over."
- 3. Message acknowledgment by the receiver to include the name or title of the sender and the title of the acknowledging receiver. The acknowledging receiver should paraphrase or repeat back the message.
Example: "This is a drill. Alpha Survey Team, this is the Technical Support Center. I understand you are starting your primary route, over."
- 4. Sender confirmation - confirmation of the acknowledgment.
Example: "This is a drill. Technical Support Center, this is the Alpha Survey Team. That is correct."
- b. When communicating alpha-numeric information, such as survey team designation or meter readings, where the sender or receiver may encounter background noise or static, the phonetic alphabet should be used.
- c. If the receiver does not understand the message, they are expected to ask the sender to repeat or rephrase the message. If the receiver acknowledges the message incorrectly, the sender should correct the receiver by saying "that is not correct" and repeating the message.
EPIP 2-12:11 Attachment 1, Rev. 22 Page 3 of 3
- d. Confirmation of the acknowledgment by the sender is imperative. The absence of the confirmation step could result in a mis-communication because the receiver may have misheard the message and repeats back erroneous information. A lack of response by the sender could be interpreted as a silent confirmation that the repeat back is correct.
NOTE: THERE MAY BE TIMES THAT THE TSC OR EOF WILL BE RECEIVING COMMUNICATIONS FROM A TEAM THAT YOU CANNOT HEAR. IF THIS HAPPENS, THE RADIO OPERATOR WILL TELL YOU TO WAIT OR STANDBY. AFTER HE HAS COMPLETED HIS TRAFFIC, HE WILL ASK YOU TO TRANSMIT YOUR INFORMATION.
- 14. To transmit, depress the push-to-talk switch on the microphone. Speak in a normal voice across the microphone.
- 15. To receive, release the push-to-talk switch.
- 16. If radio contact cannot be made, report using a cellular telephone. Call one of these numbers:
Ginna/TSC Survey Team Coordinator (716) 771-3128 Survey Center (716) 771-3331 or (716) 771-3207 EOF Dose Assessment (716) 262-5799 or (716) 771-2164
- 17. When you have been directed to secure your survey team, turn the radio off, disconnect the antenna plug from the radio and remove the magnetic mount antenna from the vehicle by lifting up at the rear of the mount.
- 18. Return the radio and the magnetic mount antenna to the appropriate survey team equipment area.
EPIP 2-12:12 Attachment 2, Rev. 22 Page 1 of 2 CELLULAR MOBILE TELEPHONE Equipment Check
- 1. Remove telephone from charging unit, if on charger.
- 2. Turn the unit on by pressing top red button on for several seconds.
NOTE: EOF SURVEY TEAM(S) CALL DOSE ASSESSMENT RADIO OPERATOR AT 262-5799.
- 3. Call Survey Center at 771-3331 to test unit.
- 4. To place a call, press the appropriate number buttons and verify the number displayed is correct.
- 5. Press the top green button to activate the call.
- 6. Press the top red button to end the test call.
- 7. Turn the unit off by pressing the top red button for several seconds unless you will be using the unit soon. This will conserve battery power.
Equipment Operation NOTE: THE UNIT CAN BE OPERATED BY PLUGGING THE CHARGING CORD INTO A POWER OUTLET IN A VEHICLE OR ON ITS OWN INTERNAL BATTERY. IF POWER IS SUPPLIED BY BATTERY, THE UNIT WILL FUNCTION IN THE STANDBY MODE (POWER ON) FOR APPROXIMATELY 170 HOURS, AND IN THE OPERATING MODE (CALL-CONNECTED) FOR APPROXIMATELY 3 HOURS.
- 1. Turn the unit on by pressing the top red button for several seconds.
- 2. To place a call, press appropriate number buttons followed by the top green.
button.
- 3. To receive a call, press the top green button while phone is ringing.
- 4. To end a call, press the top red button for several seconds.
EPIP 2-12:13 Attachment 2, Rev. 22 Page 2 of 2
- 5. Use the following numbers to report information:
Ginna/TSC (716) 771-3128 Survey Team Coordinator Survey Center (716) 771-3331 or (716) 771-3207 EOF Dose Assessment (716) 262-5799 or (716) 771-2164
- 6. To turn the unit off, press the top red button for several seconds The display screen on the handset will go blank.
EPIP 2-12:14 Attachment 3, Rev. 22 Page 1 of 2 EBERLINE RM-25 FRISKER Equipment Check
- 1. Disconnect power cord from back of meter.
- 2. Ensure that an HP-260 pancake probe or equivalent is connected to the Detector connector on the front of the instrument.
- 3. Turn range switch to HV position. Meter should read in the high voltage indicated on the calibration sticker.
- 4. Press Battery Test button on the back, lower left side of the meter. Meter should read in the green Battery Check area.
- 5. Turn range switch to Alarm position. Set alarm with HV/Alarm toggle switch to desired alarm point.
- 6. Perform instrument response check. Obtain source and verify meter reading corresponds to reading on attached card. Log on response check log (Attachment 23), whether response check was satisfactory or not, and submit to Survey Center Manager.
- 7. Turn range switch to OFF when not in use.
Equipment Operation
- 1. Turn range switch to X1.
- 2. Place response switch in the Slow Response position.
- 3. Adjust the volume control so that the audio indication (a click) can be heard.
- 4. Set Alarm to 500 (maximum scale reading).
- 5. The range switch should be adjusted such that the highest reading gives a mid scale deflection.
- 6. All readings must be multiplied by the range switch setting i.e. (X1, X1 0, X1 00, X1K).
EPIP 2-12:15 Attachment 3, Rev. 22 Page 2 of 2
- 8. Check battery level frequently when using the meter on battery power.
NOTE: EOF TEAMS RETURN EQUIPMENT TO EOF.
- 9. Upon completion of the survey, return meter to the Survey Center equipment area and response check the meter. Turn the meter off and return to storage if the response check is satisfactory. Notify the Survey Center Manager if the instrument does not response check properly. Unit should be recharged before the next use.
EPIP 2-12:16 Attachment 4, Rev. 22 Page 1 of 2 EBERLINE MODEL RO-20 DOSE RATE METER Equipment Check
- 1. Turn function switch to Battery 1 position. Ensure meter reading is in green Battery Check arc.
- 2. Turn function switch to Battery 2 position. Ensure meter reading is in green Battery Check arc.
- 3. If either of these checks are unsatisfactory, turn survey meter into Survey Center Manager.
- 4. Turn function switch to Zero position. Check that meter reads zero. If not, set it to zero with Zero knob.
- 5. Set the function switch to the 5 mR/hr range. Obtain response check source from the safe and verify that the meter reading corresponds to the reading on the source card. Use the open window reading. Log on response check log (Attachment 23), whether response check was satisfactory or not, and submit to Survey Center Manager.
- 6. Turn meter off when not in use.
Equipment Operation
- 1. Turn function switch to Battery 1 position. Ensure meter reading is in green Battery Check arc.
- 2. Turn function switch to Battery 2 position. Ensure meter reading is in green Battery Check arc.
- 3. If either of these checks are unsatisfactory, return survey meter to Survey Center Manager.
- 4. Set function switch to the desired range of operation. The switch position selected is the full scale reading of that range.
- 5. When surveying an area of unknown radiation, always start the survey at the higher scales and move to a lower scale until reading are between 10% and 90% of that scale.
EPIP 2-12:17 Attachment 4, Rev. 22 Page 2 of 2 NOTE: REMEMBER TO CHECK THE SCALE SETTING BEFORE RECORDING READINGS ON A SURVEY MAP OR REPORTING READINGS TO DOSE ASSESSMENT.
- 6. For low light conditions, set the Light toggle switch to either On for continuous illumination or Momentary for momentary illumination. When not needed, ensure Light switch is returned to the Off position to conserve battery power.
- 7. Upon completion of the survey, return meter to the Survey Center Equipment Area and response check. Turn the meter off and return to storage if the response check is satisfactory. Notify Survey Center Manager if the meter does not response check satisfactorily.
EPIP 2-12:18 Attachment 5, Rev. 22 Page 1 of 1 BICRON MICRO REM METER Equipment Check
- 1. Turn meter control switch to the BATT position and ensure meter reading is in BAT O.K. band. If not, change batteries with 2 new 9V alkaline batteries. Then if meter reading is not in BAT O.K. band, tag and remove instrument from service.
band. Ifnot, tag and remove instrument from service.
- 3. Turn meter control switch to appropriate range position. Perform instrument response check and verify that meter reading correspond to reading on attached card. Log meter reading on response check log.
Equipment Operation
- 1. Turn meter control switch to appropriate range position.
- 2. Observe reading and multiply reading by the selected switch multiplier.
- 3. The following are switch multiplier positions: xl 000, xl 00, xl 0, xl, x.1.
- 4. Upon completion of the survey, return to the equipment storage area and response check the meter. Turn the meter OFF and return to storage if the response check is satisfactory. Notify the Dose Assessment Manager ifthe instrument does not response check properly.
EPIP 2-12:19 Attachment 6, Rev. 22 Page 1 of 2 GILIAN HFS-113A AIR SAMPLER, GILIAN HFS-513A AIR SAMPLER, GILIAN GILAIR-5 AIR SAMPLER Equipment Check of Gilian Air Samplers
- 1. Perform air sampler checks prior to use as follows:
Verify calibration is current by checking the calibration sticker.
NOTE: THE PARTICULATE FILTER IS INSTALLED WITH THE TEXTURED SIDE FACING OUT. THE SILVER ZEOLITE CARTRIDGE HAS ARROWS ON ITS SIDE TO INDICATE THE DIRECTION OF THE SAMPLE FLOW.
- 2. Ensure the sample head is attached to the sampler inlet. Install new filters in the sample head.
Operation of the Gilian HFS-113A and Gilian HFS-513A
- 1. Ensure filter cartridge contains a GY-1 30 Silver Zeolite cartridge and particulate filter.
Ensure sample head is connected to a sampler.
CAUTION MASTER ON/OFF SWITCH MUST BE ON FOR UNIT TO OPERATE. MASTER ON/OFF SWITCH ALSO RESETS TIME DISPLAY.
- 2. At start of sampling period record start time. PRESS TEST button and record time in digital display and flow of 4.0 LPM on sample envelopes and on RG&E Emergency Survey Team Data Sheet Attachment 19.
Turn unit on using on/off switch located to the right of the digital display.
CAUTION IF A FAULT CONDITION EXISTS, THE UNIT SHUTS DOWN AFTER 15-30 SECONDS.
- 3. If the FAULT LED is lit; this was activated by either an undervoltage, overcurrent, or overpressure (restricted flow) condition beyond the units capability. The motor stops and the time is latched. By pressing the TEST button, the time (in minutes) into period.
sampling at which the fault occurred will be displayed indicating a valid sample
EPIP 2-12:20 Attachment 6, Rev. 22 Page 2 of 2
- 4. At end of sampling period, turn pump off using ON/OFF switch located to right of digital display. Press TEST button, record time in digital display, stop time and all other pertinent information on sample envelope and Attachment 19.
- 5. Sample volume in liters equals the flow rate in liters per minute multiplied by minutes Ifthe the sampler operated. The sampler has a fixed flow rate of 4 liters per minute.
unit was operated for thirty minutes, the sample volume would equal 120 liters (4 x 30
=
120).
Operation of the Gilian Gilair-5
- 1. Turn the power switch to the ON position.
on
- 2. Record the start time and the run time on the digital display and a flow of 4.0 LPM 19.
sample envelope and on RG&E Emergency Survey Team Data Sheet, Attachment
- 3. During use, periodically check the unit to ensure that it does not have a fault condition.
NOTE: A lit FAULT LED may be caused by:
- under voltage
- over current
- over pressure (restricted flow)
- 4. If the FAULT LED comes on during sampling, perform the following:
- a. Check the digital display to determine how long the sample ran.
- b. Determine the fault condition if possible and correct.
unit
- c. Ifthe condition causing the fault is corrected and work is continuing, turn the off to reset it and then restart it. Be sure to add the previous run time to the total run time of the sample.
- d. If the cause of the fault cannot be determined, remove the unit from service.
time of
- 5. At the end of the sampling period, look at the digital display and note the total run stop the air sampler. Turn the sampler OFF. Record the run time from the display, time and all of the other pertinent information on Attachment 19.
the air
- 6. Sample volume in liters equals the flow rate in LPM multiplied by the minutes Per Minute. Ifthe sampler was operated. The sampler has a fixed flow rate of 4 Liters (4 LPM x unit was operated for thirty minutes, the sample volume would equal 120 liters 30 min. = 120 liters).
EPIP 2-12:21 Attachment 7, Rev. 22 Page 1 of 2 RADECO H809C HIGH VOLUME AIR SAMPLER Equipment Check
- 1. Ensure power switch on air sampler is off.
and red
- 2. Ensure battery charger is not plugged in and on the 12 volt position. The black clips of battery charger shall not be touching.
- 3. Separate clips of battery charger and clamp onto cabinet.
- 4. Connect air sampler power cables to the battery charger, RED clip to positive and BLACK clip to negative.
- 5. Plug in battery charger.
- 6. Turn power switch on air sampler on.
filters in
- 7. Check flow meter on air sampler. Flow meter should be off scale high with no place.
- 8. Turn power switch on air sampler off.
- 9. Unplug battery charger and disconnect air sampler power cables.
EQUIPMENT OPERATION FROM VEHICLE
- 1. Ensure power switch on air sampler is OFF.
CAUTION KEEP HANDS AND EQUIPMENT AWAY FROM ROTATING PARTS ON THE VEHICLE ENGINE.
clip to
- 2. Connect RED power clip to positive post of vehicle battery and BLACK power vehicle ground (engine block, chassis, etc.).
OUT.
NOTE: PARTICULATE FILTER IS INSTALLED WITH TEXTURED SIDE FACING SILVER ZEOLITE CARTRIDGE HAS ARROW ON SIDE TO INDICATE DIRECTION OF SAMPLE FLOW.
- 3. Ensure the filter assembly contains a GY-130 silver zeolite cartridge and a particulate filter.
rate
- 4. Turn air sampler on and record the sample date, time, location, and air flow Data (normal is 30 1pm) on a sample envelope and RG&E Emergency Survey Team Sheet, Attachment 19.
- 5. Run sampler for approximately 6 minutes.
EPIP 2-12:22 Attachment 7, Rev. 22 Page 1 of 2 RADECO H809C HIGH VOLUME AIR SAMPLER (Cont'd.)
- 6. Record air flow rate of air sampler in Ipm and time sampler is turned off.
- 7. Turn air sampler off.
- 8. Disconnect BLACK power clip from vehicle ground, and disconnect RED power clip from positive post of vehicle battery.
EPIP 2-12:23 Attachment 8, Rev. 22 Page 1 of 3 VAS-2 EARMARK "LOUD MOUTH" VOICE AMPLIFICATION SYSTEM The "Loud Mouth" System is designed to provide voice amplification for individuals wearing respiratory protection devices.
Equipment Check Earmark Throat Microphone Model Tm-1
- 1. Figure 1 (attached) shows the proper "at rest" position for the microphone. If it is necessary to reform the spring tension, hold the microphone, starting two inches behind the microphone head, between the thumb and forefinger and bend the cable slightly while progressing down the cable until the end of the spring is reached. Check the diameter of the coil and repeat if necessary. Note that the microphone head should tilt up from a flat surface about 1/4 inch. If necessary, form the spring to give this dimension.
- 2. Batteries: A 9-volt Alkaline Battery is the required power source. The battery is located in the amplifier unit. To replace battery, remove cover plate to battery compartment. Pull plastic tab, remove and replace battery.
NOTE: Small terminal (+) in first.
Equipment Operation
- 1. Ensure microphone cable is securely connected to jack on voice amplifier.
- 2. The microphone is designed to be located on the right side of the throat (see figure 2). The microphone must lay flat on the neck and press firmly into the throat.
- 3. Securely fasten amplifier unit to belt.
CAUTION WHEN COMMUNICATING THROUGH RADIO, TELEPHONE, ETC., SPEAK PRECISELY. KEEP SPEAKER AT LEAST 12" FROM THE THROAT MIC.
KEEP THE MEANS OF COMMUNICATION 12" FROM THE THROAT MIC.
HOLD THE MEANS OF COMMUNICATION OFF TO THE SIDE OF THE SPEAKER. IF ANY FEEDBACK IS APPARENT, LOWER VOLUME.
EPIP 2-12:24 Attachment 8, Rev. 22 Page 2 of 3
- 4. To operate unit, turn volume control clockwise. The TALK slide switch has two (2) positions; up is the standby mode, and down is the talk mode. Slide TALK switch to down position to talk. Adjust VOLUME to desired level with volume control.
- 5. Turn unit off by turning volume control counter clockwise as far as it will turn. Leave talk switch in the standby position.
EPIP 2-12:25 Attachment 8, Rev. 22 Page 3 of 3 EQUIPMENT CHECK AND OPERATION INSTRUCTIONS On a flat surface the mic should rest about 1/4" above said surface When mic is laid on a flat surface it should form a circle 2 to 2 1/2 " in distance. Depending on user size. If it has been stretched to form a larger circle the inbuilt spring wire should be reformed to produce the diameters indicated.
This insures proper throat pressure for optimum sound quality.
Fig. 1 Mic to press on right side of wearers voice box.
Fig. 2
EPIP 2-12:26 Attachment 9, Rev. 22 Page 1 of 1 GENERAL AREA RADIATION SURVEY
- 1. A general radiation area survey should be conducted while moving between defined survey points, and at the specific survey points.
- 2. The survey should be conducted using a Eberline RO-20 dose rate meter or equivalent.
- 3. Normally, radiation readings are taken at 3 feet with the Beta window closed.
- 4. Record results on a survey map.
CAUTION IF RADIATION LEVELS ARE GREATER THAN 100 MR/HR, COMPLETE THE SURVEY AND RETREAT TO A LOWER DOSE AREA PRIOR TO REPORTING RESULTS TO KEEP YOUR EXPOSURE ALARA.
- 5. If a reading of 1 mr/hr or greater is detected, stop and conduct a survey for Beta radiation in accordance with Attachment 10. Record results on the RG&E Emergency Survey Team Data Sheet, Attachment 19 and immediately report the results of the survey to the Radio Operator.
EPIP 2-12:27 Attachment 10, Rev. 22 Page 1 of 1 SURVEY TO DETERMINE PRESENCE OF BETA RADIATION PLUME SURVEY
- 1. If the General Area Radiation Survey indicates a reading of 1 mr/hr or greater, or if the "plume" is suspected to be in your area, a survey to detect the presence of Beta radiation should be conducted.
- 2. Using a Eberline RO-20 dose rate meter, conduct the following surveys:
- a. With a meter held at waist level (3 feet):
Beta shield open Beta shield closed Difference #1 = (open reading - closed reading)
- b. With the meter held at ground level (3 inches):
Beta shield open Beta shield closed Difference # 2 = (open reading - closed reading)
- 3. If either difference #1 or difference #2 from Step 2 is positive, this is an indication that Beta radiation is present.
- a. If both difference # 1 and # 2 are positive, this an indication that you are in the plume.
- b. If only difference # 2 is positive, this is an indication of ground contamination.
- 4. Record survey results on RG&E Emergency Survey Team Data sheet, Attachment 19.
- 5. Report the results of the survey to the Radio Operator and await further instructions from the Dose Assessment Manager.
EPIP 2-12:28 Attachment 11, Rev. 22 Page 1 of 2 CONTAMINATION SURVEYS NOTE: DO NOT TOUCH THE METER PROBE TO ANY SURFACE BEING SURVEYED. PROBE CONTAMINATION MAY RESULT.
The background count rate should be below 200 CPM to be sensitive enough to detect low levels of contamination.
Personnel Frisk
- 1. Obtain a RM-25 with a HP-260 pancake probe or equivalent frisker.
- 2. Check the background count rate.
- 3. Slowly pass the meter probe over a person (i.e., within 1/2 inch from the person) moving it at a rate of 1 to 2 inches per second.
- 4. Listen to the audible count rate and watch the meter for any increases.
- 5. Resurvey areas showing an increased count rate.
- 6. When contamination is suspected, hold the detector over that area for 15 seconds to obtain the gross count rate.
- 7. Subtract the background count rate from the gross count rate. This is the net count rate in CPM.
- 8. Notify the Survey Center Manager, if the net count rate is greater than 100 CPM.
Direct Frisk Survey (Objects) i1. Obtain a RM-25 with a HP-260 pancake probe or equivalent frisker.
- 2. Check the background count rate.
- 3. Slowly pass the meter probe over an object or area surface (i.e., within 1/2 inch from it) moving it at a rate of 1 to 2 inches per second.
- 4. Listen to the audible count rate and watch the meter for any increases.
- 5. Resurvey areas showing an increased count rate.
- 6. When contamination is suspected, hold the detector over that area for 15 seconds to obtain the gross count rate.
EPIP 2-12:29 Attachment 11, Rev. 22 Page 2 of 2
- 7. Subtract the background count rate from the gross count rate. This is the net count rate in CPM.
- 8. Notify the Survey Center Manager if the net count rate is greater than 250 CPM.
Smear Survey
- 1. Obtain cloth smears with adhesive backing mounted on waxed paper.
- 2. Obtain a RM-25 with a HP-260 pancake probe or equivalent frisker.
- 3. Check the background count rate.
- 4. Mark the smears with sequential numbers (e.g., 1,2,3,.....
- 5. Holding the smear paper between the thumb and index and middle fingers and 2
applying medium pressure, smear an area 100 cm (approximately 4 inches by 4 inches). A 16-inch "S"pattern can also be used.
- 6. Record the smear location by writing the smear number on the map and circling it.
- 7. Hold the smear paper within 1/2 inch of the meter probe until the meter indication stabilizes. This is the gross count in CPM.
- 8. Subtract the background count rate from the gross count rate. This is the net count rate in CPM.
Record the net count rate as CPM/100 cm in the smears table of the map next to 2
9.
the corresponding smear number.
NOTE: THIS NOTICE DOES NOT APPLY TO ENVIRONMENTAL SMEARS.
- 10. Notify the Survey Center Manager if the net count rates exceed 1000 CPM/1 00 cm 2 .
- 11. Return completed contamination surveys and smears to the Survey Center Manager.
EPIP 2-12:30 Attachment 12, Rev. 22 Page 1 of 1 INSTALLATION OF TLD
- 1. Specific locations for TLD's will be listed on the survey route instructions or will be given by the Dose Assessment Manager.
- 2. Hammer a nail through non-sealing plastic into a utility pole at the specified location. The nail should be positioned on the pole at head height and facing the site.
Ensure the TLD window is oriented facing the site.
- 3. Record the location (either survey point number or road intersections), utility pole number, date, time, and TLD number on the back of the survey map.
EPIP 2-12:31 Attachment 13, Rev. 22 Page 1 of 2 TAKING AIR SAMPLES
- 1. Air samples are drawn using either of the following equipment:
- a. HIGH VOLUME - Using a RADECO H809C high volume air sampler or Buck Lapel Air Sampler, draw approximately 180 liters of air through a particulate filter and a GY-130 silver zeolite cartridge. This will take approximately 6 MINUTES.
- b. LOW VOLUME - Using a Gilian HFS-1 13A low volume air sampler, draw approximately 120 liters of air through a particulate filter and a GY-130 silver zeolite cartridge. This will take approximately 30 MINUTES.
- 2. Record the sample date, time, and location (either survey point number or road intersections) on a sample envelope and on RG&E Emergency Survey Team Data sheet, Attachment 19. Take radiation readings as per Attachment 10 and record on Attachment 19.
- 3. Determine the background radiation level using the Eberline RM-25 Frisker and HP-260 pancake probe or equivalent. Record the reading on Attachment 19. If background reading is greater than 200 CPM, move to lower background area prior to taking readings. If background of 200 cpm cannot be located, contact Dose Assessment for further instructions.
CAUTION IF FILTERS ARE READING OFF SCALE, MOVE PROBE APPROXIMATELY 1" FROM FILTER. REPORT AND LOG DATA AS BEING TAKEN AT 1"
- 4. Using clean disposable gloves, remove the particulate filter and measure the activity level using an Eberline RM-25 Frisker and HP-260 pancake probe or equivalent. DO NOT TOUCH THE PROBE WINDOW TO THE PARTICULATE FILTER. Record the gross cpm reading on Attachment 19 and place the particulate filter in the envelope.
- 5. Remove the GY-130 silver zeolite cartridge from the sample holder and measure the activity on the inlet side of the cartridge filter. DO NOT TOUCH THE PROBE WINDOW TO THE CARTRIDGE. Record the gross reading on Attachment 19 and place the cartridge in the envelope.
- 6. Remove the disposable gloves and discard in a plastic bag. Treat as potentially contaminated material.
- 7. Report the sample collection information from Attachment 19 to the Radio Operator.
EPIP 2-12:32 Attachment 13, Rev. 22 Page 2 of 2 NOTE: DO NOT PERFORM CALCULATIONS UNLESS REQUESTED BY THE DOSE ASSESSMENT MANAGER.
- 8. Field calculations of the airborne activity level may be performed as follows:
- a. Sample volume in liters equals the flow rate (30 1pm) times the number of minutes the sampler operated
- b. Radioiodine (GY-130 cartridge)
CAUTION IF THE CARTRIDGE CONTACT READING IS OFFSCALE, DETERMINE THE IODINE ACTIVITY FOR THE HP-260 PROBE ONE INCH (ONE CARTRIDGE THICKNESS) AWAY FROM THE INLET SIDE OF THE CARTRIDGE, USING EQUATION b.2. OTHERWISE, USE EQUATION b.1.
@ contact 1. (CPM Sample - CPM Background)(4.13 E-8) = uCi/cc (Volume of Sample in Liters) Radioiodine
@ 1" 2. (CPM Sample - CPM Background)(8.50 E-8) = _ uCi/cc (Volume of Sample in Liters) Radioiodine
- c. Particulate CAUTION IF THE FILTER CONTACT READING IS OFFSCALE, DETERMINE THE PARTICULATE ACTIVITY FOR THE HP-260 PROBE ONE INCH AWAY FROM THE INLET SIDE OF THE FILTER, USING EQUATION c.2.
OTHERWISE, USE EQUATION c.1.
SURVEY INSTRUCTIONS
@ contact 1. (CPM Sample - CPM Background)(3.47 E-9) = __uCi/cc (Volume of Sample in Liters Particulate
- 2. (CPM Sample -CPM Background)(9.83 E-9) = uCi/cc
@ 1" (Volume in Sample in Liters Particulate
EPIP 2-12:33 Attachment 14, Rev. 22 Page 1 of 1 CHANGING FILTERS AT FIXED ENVIRONMENTAL STATIONS
- 1. Record the following information on the sample envelope left from the previous filter change:
- a. Date
- b. Time
- c. System Vacuum (inches)
- d. Gas meter reading (cubic feet)
- e. Total hour meter reading (record in column marked "OFF")
- f. Initials of person changing filters
- 2. Turn pump off.
- 3. Using clean disposable gloves, remove the filter holder at the quick-disconnect joint.
- 4. Unscrew the outside retaining ring and remove the particulate filter from the holder and place in the sample envelope.
- 5. If a charcoal or zeolite cartridge was used, transfer the information from the particulate filter envelope to a new envelope and place the cartridge in the envelope.
NOTE: PARTICULATE FILTER IS INSTALLED WITH TEXTURED SIDE FACING OUT.
SILVER ZEOLITE CARTRIDGE HAS ARROW ON SIDE TO INDICATE DIRECTION OF SAMPLE FLOW.
- 6. Reassemble the filter holder installing a new GY-1 30 silver zeolite cartridge and a particulate filter.
- 7. Reconnect the filter holder to the pump at the quick-disconnect joint.
- 8. Remove disposable gloves and place in a plastic bag. Treat as potentially contaminated material.
- 9. Turn the pump on.
- 10. Record the following information to two new envelopes. Mark one envelop "GY-130 silver zeolite".
- a. Station number
- b. Date
- c. Time
- d. System vacuum (inches)
- e. Gas meter reading (cubic feet)
- f. Total hour meter reading (record in the "ON" column)
- g. Initials of person starting sampler
- 11. Place the new envelopes inside the monitor cabinet.
- 12. Bring the envelopes containing the removed cartridge and filter to the Survey Center at the completion of your assigned route or when directed by the Dose Assessment Manager.
EPIP 2-12:34 Attachment 15, Rev. 22 Page 1 of 4 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
OFFSITE EAST PRIMARY SURVEY ROUTE NOTE: NUMBERS GIVEN IN PARENTHESES ARE PREDESIGNATED SURVEY POINTS.
NOTE: IF FIXED ENVIRONMENTAL STATION FILTERS ARE REQUESTED TO BE CHANGED, CHANGE THEM PER INSTRUCTIONS IN ATTACHMENT 14.
- 1. Travel East on Lake Road from the Training Center driveway to Knickerbocker Road.
Place a TLD near the intersection of Lake Road and Knickerbocker Road (2ESE) per instructions in Attachment 12.
- 2. Continue East on Lake Road to Fisher Road.
- 3. Go South on Fisher Road to Shepard Road. Place a TLD near the intersection of Fisher Road and Shephard Road (3ESE-2) per instructions in Attachment 12.
- 4. Continue South on Fisher Road to Seely Road. Place a TLD near the intersection of Fisher Road and Seely Road (4ESE) per instructions in Attachment 12.
- 5. Continue South on Fisher Road to Kenyon Road (4SE).
- 6. Go West on Kenyon Road to Furnace Road. Place a TLD near the intersection of Kenyon Road and Furnace Road per instructions in Attachment 12.
- 7. Continue West on Kenyon Road to Knickerbocker Road (3SSE).
- 8. Go North on Knickerbocker Road to Brick Church Road (2SE).
- 9. Place a TLD near the intersection of Knickerbocker Road and Brick Church Road (2SE) per instructions in Attachment 12.
- 10. Take a high volume air sample at Knickerbocker Road and Brick Church Road (2SE) per instructions in Attachment 13. Report the results.
- 11. Report to the Radio Operator that the survey route for the Offsite East Primary Route has been completed. Inform the Radio Operator of any unusual radiological conditions.
Inform the Radio Operator that you are awaiting further instructions.
EPIP 2-12:35 Attachment 15, Rev. 22 Page 2 of 4 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
OFFSITE EAST SECONDARY SURVEY ROUTE POINTS.
NOTE: NUMBERS GIVEN IN PARENTHESES ARE PREDESIGNATED SURVEY BE NOTE: IF FIXED ENVIRONMENTAL STATION FILTERS ARE REQUESTED TO CHANGED, CHANGE THEM PER INSTRUCTIONS IN ATTACHMENT 14.
- 1. From the intersection of Brick Church Road and Knickerbocker Road, go North to Lake Road.
- 2. Go East on Lake Road to the intersection of Lake Road and Route 21 in Pultneyville.
in
- 3. Place a TLD near the intersection of Lake Road and Route 21 (6E) per instructions Attachment 12.
- 4. Go South on Route 21 to Salmon Creek Road.
- 5. Place a TLD near the intersection of Salmon Creek Road and Eaton Road (6ESE-1) per instructions in Attachment 12.
per
- 6. Take a high volume air sample at Salmon Creek Road and Eaton Road (6ESE-1) instructions in Attachment 13. Report the results.
- 7. Go South on Salmon Creek Road to Ridge Road.
- 8. Place a TLD near the intersection of Salmon Creek Road and Ridge Road per instructions in Attachment 12.
Road.
- 9. Go West on Ridge Road to the intersection of Ridge Road and Knickerbocker
- 10. Take a high volume air sample at Route 104 and Knickerbocker Road (4SSE) per instructions in Attachment 13. Report the results.
- 11. Go North on Knickerbocker Road to Brick Church Road (2SE).
- 12. Report to the Radio Operator that the survey route for the Off site East Secondary Route has been completed. Inform the Radio Operator of any unusual radiological conditions. Inform the Radio Operator that you are awaiting further instructions.
EPIP 2-12:36 Attachment 15, Rev. 22 Page 3 of 4 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
OFFSITE EAST THIRD SURVEY ROUTE WINDS FROM THE EAST
- 1. From the intersection of Brick Church Road and Knickerbocker Road travel West to Ontario Center Road.
- 2. Go South on Ontario Center Road to Plank Road.
- 3. Go West on Plank Road to Five Mile Line Road.
- 4. Go North on Five Mile Line Road to Klein Road.
- 5. Go East on Klem Road to Whiting Road.
- 6. Go North on Whiting Road to Lake Road.
- 7. Go East on Lake Road to Knickerbocker Road.
- 8. Go South on Knickerbocker Road to Brick Church Road.
- 9. Report to the Radio Operator that the Survey Route for the Offsite East Third Route has been completed. Inform the Radio Operator of any unusual radiological conditions.
Inform the Radio operator that you are awaiting further instructions.
EPIP 2-12:37 Attachment 15, Rev. 22 Page 4 of 4 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
OFFSITE EAST THIRD SURVEY ROUTE WINDS FROM THE WEST
- 1. From the intersection of Brick Church Road and Knickerbocker Road travel North to Lake Road.
- 2. Go East on Lake Road to Townline Road.
- 3. Go South on Townline Road to Ridge Road.
- 4. Go West on Ridge Road to Route 21.
- 5. Go South on Route 21 to Walworth-Marion Road.
- 6. Go West on Walworth-Marion Road(Route 441) to Route 350.
- 7. Go North on Route 350 to Brick Church Road.
- 8. Go East on Brick Church Road to Knickerbocker Road.
- 9. Report to the Radio Operator that the Survey Route for the Offsite East Third Route has been completed. Inform the Radio Operator of any unusual radiological conditions.
Inform the Radio Operator that you are awaiting further instructions.
EPIP 2-12:38 Attachment 16, Rev. 22 Page 1 of 4 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
OFFSITE WEST PRIMARY SURVEY ROUTE NOTE: NUMBERS GIVEN IN PARENTHESES ARE PREDESIGNATED SURVEY POINTS.
NOTE: IF FIXED ENVIRONMENTAL STATION FILTERS ARE REQUESTED TO BE CHANGED, CHANGE THEM PER INSTRUCTIONS IN ATTACHMENT 14.
- 1. Travel West on Lake Road from the Training Center driveway to Lakeside Road.
- 2. Place a TLD near the intersection of Lake Road and Lakeside Road (2WSW) per instructions in Attachment 12.
- 3. Go South on Lakeside Road to the intersection of Berg Road.
- 4. Place a TLD near the intersection of Lakeside Road and Berg Road (3SSW-2) per instructions in Attachment 12.
- 5. Continue South on Lakeside Road to Ridge Road.
- 6. Go East on Ridge Road to Route 350.
- 7. Go North on Route 350 to Brick Church Road.
- 8. Travel West on Brick Church Road to Slocum Road.
- 9. Place a TLD near the intersection of Brick Church Road and Slocum Road (2SSW) per instructions in Attachment 12.
- 10. Take a high volume air sample at Brick Church Road and Slocum Road (2SSW) per instructions in Attachment 13. Report the results.
- 11. Report to the Radio Operator that the Survey Route for the Offsite West Primary Route has been completed. Inform the Radio Operator of any unusual radiological conditions.
Inform the Radio Operator that you are awaiting further instructions.
EPIP 2-12:39 Attachment 16, Rev. 22 Page 2 of 4 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
OFFSITE WEST - SECONDARY SURVEY ROUTE NOTE: NUMBERS GIVEN IN PARENTHESES ARE PREDESIGNATED SURVEY POINTS.
NOTE: IF FIXED ENVIRONMENTAL STATION FILTERS ARE REQUESTED TO BE CHANGED, CHANGE THEM PER INSTRUCTIONS INATTACHMENT 14.
- 1. From the intersection of Brick Church Road and Slocum Road travel North to Lake Road.
- 2. Go West on Lake Road to Route 250 (Webster Road).
- 3. Place a TLD near the intersection of Lake Road and Route 250 per instructions in Attachment 12.
- 4. Travel South on Route 250 to Schlegel Road.
- 5. Go East on Schlegel Road to Salt Road.
- 6. Place a TLD near the intersection of Schlegel Road and Salt Road (6WSW) per instructions in Attachment 12.
- 7. Take a high volume air sample at Schlegel Road and Salt Road (6WSW) per instructions in Attachment 13. Report the results.
- 8. Go South on Salt Road to Route 104.
- 9. Travel East on Ridge Road to County Line Road.
- 10. Travel South on County Line Road to Whitney Road.
- 11. Place a TLD near the intersection of County Line Road and Whitney Road per instructions in Attachment 12.
- 12. Go East on Whitney Road to Slocum Road.
- 13. Take a high volume air sample at Whitney Road and Slocum Road per instructions in Attachment
- 13. Report the results.
- 14. Continue on Whitney Road to Hennessey Road.
- 15. Go East on Hennessey Road to Route 350.
- 16. Go North on Route 350 to Brick Church Road.
- 17. Go West on Brick Church Road to Slocum Road.
- 18. Report to the Radio Operator that the Survey Route for the Offsite West Secondary Route has been completed. Inform the Radio Operator of any unusual radiological conditions. Inform the Radio Operator that you are awaiting further instructions.
EPIP 2-12:40 Attachment 16, Rev. 22 Page 3 of 4 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
OFFSITE WEST THIRD SURVEY ROUTE WINDS FROM THE EAST
- 1. From the intersection of Brick Church Road and Slocum Road travel North to Lake Road.
- 2. Go West on Lake Road to Route 250 (Webster Road).
- 3. Go South on Route 250 to Atlantic Avenue.
- 4. Go East on Atlantic Avenue to Route 350 (Ontario Center Road).
- 5. Go North on Route 350 to Paddy Lane.
- 6. Go West on Paddy Lane to Slocum Road.
- 7. Go North on Slocum Road to Brick Church Road.
Route
- 8. Report to the Radio Operator that the Survey Route for the Offsite West third conditions.
has been completed. Inform the Radio Operator of any unusual radiological Inform the Radio Operator that you are awaiting further instructions.
EPIP 2-12:41 Attachment 16, Rev. 22 Page 4 of 4 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
OFFSITE WEST THIRD SURVEY ROUTE WINDS FROM THE WEST
- 1. From the intersection of Brick Church Road and Slocum Road travel South to Paddy Lane.
- 2. Go East on Paddy Lane to Route 350 (Ontario Center Road).
- 3. Go South on Route 350 to Route 441.
- 4. Go East on Route 441 to Cory Corners Road.
- 5. Go North on Cory Corners Road to Ridge Chapel to Ridge Road.
- 6. Go East on Ridge Road to Salmon Creek Road.
- 7. Go North on Salmon Creek Road to Lake Road.
- 8. Go West on Lake Road to Slocum Road.
- 9. Go South on Lake Road to Brick Church Road.
- 10. Report to the Radio Operator that the Survey Route for the Offsite West Third Route has been completed. Inform the Radio Operator of any unusual radiological conditions.
Inform the Radio Operator that you are awaiting further instructions.
EPIP 2-12:42 Attachment 17, Rev. 22 Page 1 of 1 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
EOF SURVEY ROUTE #1 LONG ROUTE (EOF-1L)
- 1. Take 490 East to 590 North. (During rush-hour periods, consider using Culver to Atlantic Avenue as an alternate route.)
- 2. Take Browncroft Boulevard exit and head east to Creek Street. Head north on Creek Street to Empire Boulevard.
- 3. At Eastway Plaza, take a high volume air sample per instructions in Attachment 13.
- 4. From Eastway Plaza, continue north on Bay Road to Lake Road. Turn west on Lake Road and proceed to the Irondequoit Bay Outlet.
- 5. Head east on Lake Road to Bay Road. Head south on Bay Road to Route 104. Head west on Route 104, cross the lrondequoit Bay Bridge and continue on Route 104 West to the Culver Road exit. Head north on Culver Road to Sea Breeze to the lrondequoit Bay Outlet.
- 6. Head south on Sea Breeze Expressway to 590 South to Route 404 Webster exit. Head east on Empire Boulevard to Creek Street/Bay Road (Eastway Plaza.)
- 7. Report to Radio Operator that the EOF Survey Route #1 Long has been completed noting any unusual radiological conditions, and are awaiting further instructions.
SHORT ROUTE (EOF-1S)
- 1. Take East Avenue to Culver Road. Turn north on Culver Road and proceed to Empire Boulevard.
- 2. At Culver Road and Empire Boulevard, take a high volume air sample as per instructions in Attachment 13.
- 3. Proceed northwest on Waring Road to Norton Street. Turn west on Norton Street to Portland Avenue.
- 4. Proceed west on Portland Avenue to North Street. Head South on North Street to East Avenue.
- 5. Report to Radio Operator that the EOF Survey Route #1 Long has been completed noting any unusual radiological conditions, and are awaiting further instructions.
EPIP 2-12:43 Attachment 18, Rev. 22 Page 1 of 1 CAUTION DO NOT WAIT IN HIGH RADIATION FIELDS FOR INSTRUCTIONS FROM DOSE ASSESSMENT.
EOF SURVEY ROUTE #2 LONG ROUTE (EOF-2L)
- 1. Take 490 East to Route 441 (Linden Avenue) exit. Head east on Route 441 to Route 250.
- 2. At Penfair Plaza, take a high volume air sample per instructions in Attachment 13.
- 3. Continue east on Route 441 to Harris Road. Turn north on Harris Road to Atlantic Avenue (Route 286). Turn west on Atlantic Avenue to Route 250. Turn south on Route 250 and return to Penfair Plaza.
- 4. Report to Radio Operator that the EOF Survey Route #2Long has been completed noting any unusual radiological conditions, and are awaiting further instructions.
SHORT ROUTE (EOF-2S)
- 1. Take Monroe Avenue (Route 31) southeast to the 12 Corners.
- 2. At 12 Corners, take a high volume air sample per instructions in Attachment 13.
- 3. Head north on Winton Road to Main Street. Turn west on Main Street to Culver Road.
Turn south on Culver Road to East Avenue.
- 4. Report to Radio Operator that the EOF Survey Route #2 Short has been completed noting any unusual radiological conditions, and are awaiting further instructions.
EPIP 2-12:44 Attachment 19, Rev. 22 Page 1 of 2 RG&E EMERGENCY SURVEY TEAM DATA SHEET
- 1. DATA FROM: 0 RG&E 0 WAYNE COUNTY 0 MONROE COUNTY
- 2. A. DATE: B. TIME: C. DATA SHEET NO.:
D. TEAM:
E. LOCATION:
- 3. A. SURVEY UNITS: (CIRCLE ONE) CPM MICRO-R/HR MR/HR R/HR B. SURVEY METER: (CIRCLE ONE) CDV-700 CDV-715 EBERLINE RO-20 BICRON METER NO.
- 4. WAIST LEVEL (3 FEET) READINGS:
A.. OPEN WINDOW B. CLOSED WINDOW
- 5. GROUND LEVEL (3 INCHES) READINGS:
A.. OPEN WINDOW B. CLOSED WINDOW
- 6. AIR SAMPLING COLLECTION TIMES:
A. TIME ON: B. TIME OFF: C. MINUTES RUN:
- 7. AIR SAMPLING FLOWRATES:
A. LPM START: B. LPM END: C. LPM AVERAGE:
- 8. PARTICULATE CPM: SURVEY METER SERIAL NO.
A. CONTACT: B. 1"
- 9. IODINE CPM:
A. CONTACT: B. 1"
- 10. BACKGROUND CPM:
- 11. COMMENTS AND ADDITIONAL DATA:
[] THIS IS A DRILL 0A THIS IS NOT A DRILL
EPIP 2-12:45 Attachment 19, Rev. 22 Page 2 of 2 NOTE: THIS DOES NOT NEED TO BE FILLED OUT FOR TRANSMISSION TO OTHER AGENCIES.
RADIOIODINE:
(8.50 E-8) @ 1 (CPM SAMPLE - CPM BACKGROUND) (4.13 E-8) ON CONTACT = UCI/CC (MINUTES RUN) (LPM AVERAGE) RADIOIODINE PARTICULATE:
(9.83 E-9) @ 1" UCI/CC (CPM SAMPLE - CPM BACKGROUND) (3.47 E-9) ON CONTACT =
(MINUTES RUN) (LPM AVERAGE) PARTICULATE RADIOIODINE DOSE CONVERSION CHILD THYROID (CDE) DOSE RATE FACTORS (REM/HR PER UCI/CC)
HR DCF (UCI/CC) (DCF) = REM/HR HR DCF 1 5.4E5 7 9.3E5 CHILD THYROID 2 6.4E5 8 9.3E5 3 7.3E5 9 1.0E6 4 8.0E5 10 1.1 E6 5 8.7E5 11 1.1 E6 6 8.7E5 12 1.1E6 PERFORMED BY: DATE/TIME NAME CHECKED BY:
NAME DATE/TIME
[] THIS IS A DRILL T S THIS IS NOT A DRILL
EPIP 2-12:46 Attachment 20, Rev. 22 Page 1 of 1 SURVEY TEAM ATTACHMENT FORM SURVEY TEAM:
DATE TIME INITIALS METER REMARKS TYPE/NO.
I I- I J .8- 4 .9.
4- 4 1 I- I i i
_ _I_ _ 1 I_ 4-4 4 *I- I I 1 4 I I 4I 4 i
_ I__ I I. i 4 s i t 4 4 I 4- I 4 +
I I +
4 4 1- +
1 4- + -t I 4- 4 1 4 4- 4 I I. I I i 4- 1 I I USE THIS FORM TO DOCUMENT INFORMATION REGARDING SURVEY TEAM COVERAGE NOT DOCUMENTED ON SURVEY MAPS OR FORMS
EPIP 2-12:47 Attachment 21, Rev. 22 Page 1 of 1 RADIATION PROTECTION & CHEMISTRY Category: EPIP INSTRUMENT RESPONSE CHECK DATE:
Subject:
EPIP Instruments Date:
Reviewed:
FRISKERS DOSE RATE METERS Model Serial # Response/Alarm Tech Model Serial # Response Tech Check Sat. Initials Check Sat. Initials Yor N YorN 1 1 2 2 3 3 4 4 5 5 6 6 7 7 8 8 9 9 10 10 11 11 12 12 13 13 14 14
EPIP 2-12:48 Attachment 22, Rev. 22 Page 1 of 1 Rapid Deployment Survey Team Instructions
- 1. Assemble the following equipment:
- a. Personal thermoluminescent dosimeter (TLD) for each team member
- b. One 0-1500 mR dosimeter and one 0-10 R dosimeter for each team member. Sign in on dosimeter log sheet, Attachment 2 in EPIP 1-11.
- c. Motorola GM 300 mobile radio and magnetic mount antenna.
- d. Eberline RM-25 Frisker with HP-260 pancake probe or equivalent.
- e. Eberline RO-20 dose rate meter or equivalent.
- f. Cellular telephone
- g. Survey map of 10-mile EPZ
- h. Other equipment (eg., PC's, KI tablets, respirators, air sampler, etc.) as determined by Dose Assessment Manager.
- 2. Source response check survey meters and document on Attachment 21.
- 3. Obtain transportation and check vehicle for contamination by performing a direct frisk survey. Document results on Attachment 20.
- 4. Establish radio and cell phone communications with Technical Support Center (TSC) Radio Operator.
- 5. TSC Radio Operator will provide a team briefing and instructions to the Rapid Deployment Team from the Dose Assessment Manager.
- 6. The Rapid Deployment Team will be called back to the Survey Center when other survey teams are staffed and deployed to designated survey routes.
EPIP 2-12:49 Attachment 23, PageRev.
1 of221 Survey Team Equipment / Team Data Cell Phone # Date / Time_
Team A
Team Member#2 Team Member#1 TLD #
TLD #
0-1500 mR 0-1500 mR Dosimeter #
Dosimeter # Initial Reading Final Reading Initial Reading _Final Reading 0-10 R 0-10 R Dosimeter #
Dosimeter # Initial Reading Final Reading Initial Reading Final Reading
.*r~ntt A - 11D #
Scott A -ID # S~~~ ___ __ __ ___ __ __#
Meter / Frisker Data Meter Serial # Calibration Response Check Battery Flow RO -20 RM-25 RADECO .. .....
GILIAN Comments:
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER i-.
PROCEDURE NO. EPIP 2-18 REV. NO. 14 CONTROL ROOM DOSE ASSESSMENT EFFEs-/I DaTE EFFEdTIVE DATE Category 1.0 This procedure contains 7 pages
EPIP 2-18:1 EPIP 2-18 CONTROL ROOM DOSE ASSESSMENT 1.0 PURPOSE 1.1 The purpose of this procedure is to provide the Control Room personnel a method for performing initial projections of downwind dose rates and doses. Such information is needed to decide upon protective actions to be recommended to limit the exposure of the general public and emergency workers and Emergency Action Level (EAL) classification.
1.2 The initial whole body dose calculation will be limiting with respect to Emergency Classification and Protective Action Recommendation (PARs), based upon an assumed radioiodine to noble gas default ratio of 1 E-4.
2.0 RESPONSIBILITY 2.1 The On-Shift Radiation Protection technician is the primary individual responsible for implementing this procedure.
2.2 Shift Technical Advisors (STAs) and Operations personnel may implement this procedure in the event the On-Shift Radiation protection technician is unavailable during emergency conditions.
3.0 REFERENCES
3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.1.2 EPA-400, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (1991) 3.1.3 Ginna UFSAR, Chapter 15 3.1.4 Regulatory Guide 1.109 3.2 Implementing References 3.2.1 EPIP 1-0, Ginna Station Event Classification and Evaluation 3.2.2 EPIP 2-1, Protective Action Recommendations
EPIP 2-18:2 3.2.3 EPIP 2-2, Obtaining Meteorological Data and Forecasts and Their Use In Emergency Dose Assessment 4.0 PRECAUTIONS 4.1 If the Ginna Primary Meteorological Tower is unavailable, use EPIP 2-2 to obtain meteorological data.
5.0 PREREQUISITES 5.1 The following equipment and data sources are available for use in performing dose projections:
5.1.1 Control Room wind and temperature indications 5.1.2 Plant Process Computer System (PPCS) 5.1.3 Control Room Radiation Monitoring System (RMS) Panel readouts of effluent monitors.
6.0 ACTIONS NOTE: IF PPCS IS UNAVAILABLE OR THE HIGH RANGE EFFLUENT MONITORS ARE OUT OF SERVICE, USE THE CONTROL ROOM RMS PANEL AND ATTACHMENT 4 TO PERFORM ASSESSMENT.
6.1 Obtain a printout of EVENT2.
6.1.1 At a PPCS terminal, select "Emergency Plan Menu" from the top menu.
6.1.2 Select "Group Event 2", then select "Report".
NOTE: IF THE GINNA PRIMARY METEOROLOGICAL TOWER IS UNAVAILABLE, USE EPIP 2-2 TO OBTAIN METEOROLOGICAL DATA.
6.2 Obtain the following parameters.
250 foot - 33 foot Delta Temperature F F F (250 ft temp) (33 ft temp)
EPIP 2-18:3 6.3 Using the 250-33 foot delta temp., determine Stability Class.
-1.74F -0.65F Unstable I Neutral I Stable
-3F -2F1 -1F JOF +1F 6.3.1 Stability Class = Unstable Neutral Stable (Circle one) 6.4 Based on the Stability Class, calculate the Site Boundary Whole Body Dose Rate by completing the appropriate Attachments:
Unstable - Attachment 1 Neutral - Attachment 2 Stable - Attachment 3 6.5 To perform the EPIP 2-18 calculations from the PPCS, select "Emergency Plan Menu" from the top menu.
6.5.1 Select "EPIP 2-18".
6.5.2 The EPIP 2-18 calculation form is displayed. Review the data for each input.
Your review should ensure that shine from radiation sources or instrument malfunctions are not affecting the quality of the data. When the data has been verified as being valid, select "verify" for each effluent release point.
6.5.3 When the calculation has been verified, select the printer icon and print the report.
Sign the report as the person completing the form. Then, have the Shift Supervisor review your calculation.
7.0 ATTACHMENTS
- 1. Unstable - Stability Class
- 2. Neutral - Stability Class
- 3. Stable - Stability Class
- 4. RMS Conversion Factors
I Stability Class = UNSTABLE I EEPIP 2-18:4 A'Attachment "age 1 of I 1
NOTE: The numbers in parenthesis refer to the line numbers on the Event 2 reports.
NOTE: If PPCS or SPING(s) are out of service, calculate pci/cc for 4A, 4B or 4C respectively using Attachment 4.
250 ft. temp. 33 ft. temp. Delta T
- 1. Verify Stability Class =
- 2. Determine the 33 ft. Level Wind Speed MPH
- 3. Determine which of the following monitors are on "ALARM" and providing a "RELEASE" path.
ALARM (Yes/No) 3A) R-1 2 Containment Vent Gas (during CV purge "ONLY") Yes No if yes go to 4A 3B) R-14 Plant Vent Yes No if yes go to 4B 3C) R-1 5 Air Ejector Vent Yes No if yes go to 4C 3D) R-31/32 "A/B" Steam Line Radiation Monitor Yes No if yes go to 4D and 4E
- 4. Dose Assessment Calculation at the Site Boundary 4A) R-12 ALARM Assessment. Use R12A7 unless >10uCi/cc, then use R12A9.
uCi/cc X 1.72E+2
. m R/hr I ~MPHI 4B) R-1 4 ALARM Assessment. Use RI 4A7 (30) unless >10OuCi/cc, then use R14A9.
X 8.61 E+2 =
. m R/hr I u cMPHI 4C) R-1 5 ALARM Assessment. Use R15A7 (33) unless s>1OuCi/cc, then use R15A9.
I u Hi/cc X 6.73E+0 =
--- --------- m R/hr S.... .. .... .. .. .. . .. .. .. .. . .. ...P H . .
4D) R-31/32 ALARM Assessment. Use R-31/32 whichever is HIGHER Number of ARV's OPEN (max. 1 per associated faulted steam generator) mR/hr X X4.1OE+0=
-..................................................................... m R /h r I MPH1 4E) R-31/32 ALARM Assessment. Use R-31/32 whichever is HIGHER Number of Safeties OPEN (max. 4 per associated faulted steam generator) mR/hrI x X 8.16E+0=
mR/hr I ~MPH1 4F) TOTAL SITE BOUNDARY DOSE RATE (Total of 4A thru 4E) mR/hr (Refer to EPIP 1-0, Initiating Condition:Effluent Releases for EAL Criteria) 4G) TOTAL PROJECTED EXPOSURETotal from 4F X Duration (if unknown use 4 hrs) mR/hr X hrs = mR (Refer to EPIP 2-1 for PARS) 4H) Person Completing Form Shift Supervisor Date/Time
S Stability Class = NEUTRAL 1
I Page 1 of 1 Attachment 2 NOTE: The numbers in parenthesis refer to the line numbers on the Event 2 reports.
NOTE: If PPCS or SPING(s) are out of service, calculate fci/cc for 4A, 4B or 4C respectively using Attachment 4.
250 ft. temp. 33 ft. temp. Delta T
- 1. Verify Stability Class - =
- 2. Determine the 33 ft. Level Wind Speed MPH
- 3. Determine which of the following monitors are on "ALARM" and providing a "RELEASE" path.
ALARM (Yes/No) 3A) R-1 2 Containment Vent Gas (during CV purge "ONLY") Yes No if yes go to 4A
- 38) R-1 4 Plant Vent Yes No if yes go to 4B 3C) R-1 5 Air Ejector Vent Yes No if yes go to 4C 3D) R-31/32 "A/B" Steam Line Radiation Monitor Yes No if yes go to 4D and 4E
- 4. Dose Assessment Calculation at the Site Boundary 4A) R-12 ALARM Assessment. Use R12A7 unless >1OuCi/cc, then use R12A9.
L IX 9.65E+2 =
m R/hr I MPHI 4B) R-14 ALARM Assessment. Use R14A7 unless >1OuCi/cc, then use R14A9.
uc/cc] X 4.84E+3 =
______________---- m R/hr I ~ MPHI 4C) R-15 ALARM Assessment. Use R15A7 unless >10uCi/cc, then use R15A9.
Iuci/cc X 3.78E-+1
-..................................................................... = m R/h r I MPH 4D) R-31/32 ALARM Assessment. Use R-31/32 whichever is HIGHER Number of ARV's OPEN (max. 1 per associated faulted steam generator)
MR/hr I- X X 2.30E+1=
mR /hr I MPHI 4E) R-31/32 ALARM Assessment. Use R-31/32 whichever is HIGHER Number of Safeties OPEN (max. 4 per associated faulted steam generator) mR/hr XI X74.59E+1=
.-- mR/hr I MPH I 4F) TOTAL SITE BOUNDARY DOSE RATE (Total of 4A thru 4E) mR/hr (Refer to EPIP 1-0, Initiating Condition: Effluent Releases for EAL Criteria) 4G) TOTAL PROJECTED EXPOSURETotal from 4F X Duration (if unknown use 4 hrs) mR/hr X hrs = mR (Refer to EPIP 2-1 for PARS) 4H) Person Completing Form_ Shift Supervisor Date/Time
EPIP 2-18 I Stability Class = STABLE I Attachment 3 Page 1 of 1 NOTE: The numbers in parenthesis refer to the line numbers on the Event 2 reports.
NOTE: If PPCS or SPING(s) are out of service, calculate mci/cc for 4A, 4B or 4C respectively using Attachment 4.
250 ft. temp. 33 ft. temp. Delta T
- 1. Verify Stability Class =
- 2. Determine the 33 ft. Level Wind Speed MPH
- 3. Determine which of the following monitors are on "ALARM" and providing a "RELEASE" path.
ALARM (Yes/No) 3A) R-1 2 Containment Vent Gas (during CV purge "ONLY") Yes No if yes go to 4A 3B) R-14 Plant Vent Yes No if yes go to 4B 3C) R-1 5 Air Ejector Vent Yes No if yes go to 4C Yes No if yes go to 4D and 4E 3D) R-31/32 "A/B" Steam Line Radiation Monitor
- 4. Dose Assessment Calculation at the Site Boundary 4A) R-12 ALARM Assessment. Use R12A7 unless >lOuCi/cc, then use R12A9.
uCi/cc X 1.78E+3 =
mR/hr MPH I 4B) R-14 ALARM Assessment. Use R14A7 unless >1OuCVcc, then use R14A9.
I uCi/ccI X 8.94E+3 =
mR/hr L ~ MPHI 4C) R-15 ALARM Assessment. Use R15A7 unless >1OuCi/cc, then use R15A9.
I uCi/ccI X 6.99E+1 =
mR/hr I ~ MPHI 4D) R-31/32 ALARM Assessment. Use R-31/32 whichever is HIGHER (max. 1 per associated faulted steam generator)
Number of ARV's OPEN
...R/hr x F ]
-- -- m R /hr I ~ MPHI 4E) R-31/32 ALARM Assessment. Use R-31/32 whichever is HIGHER Number of Safeties OPEN (max. 4 per associated faulted steam generator)
-mR/hr x Lii] X8.48E+1=
. mR/hr I ~ MPHI 4F) TOTAL SITE BOUNDARY DOSE RATE (Total of 4A thru 4E) mR/hr (Refer to EPIP 1-0, Initiating Condition:Effluent Releases for EAL Criteria) 4G) TOTAL PROJECTED EXPOSURETotal from 4F X Duration (if unknown use 4 hrs) mR/hr X hrs = mR (Refer to EPIP 2-1 for PARS) 4H) Person Completing Form _ Shift Supervisor _ Date/Time
J EPIP 2-18:6 Attachment 4, Rev. 13 I
II RMS Conversion Factors Page 1 of 1
- 1. R-12 Conversion (during CV purge "ONLY") Reading in 0Ci/cc R-12 Reading in CPM Conversion Factor 5.6E-8 ZCi/cc CPM
- 3. R-15 Conversion Reading in pCi/cc R-15 Reading in CPM Conversion Factor
[111-1] 5.OE-8 !Ci/cc =
CPM NOTE: Use the converted value for R-12A, R-14A and R-15A values on the applicable Attachment (Unstable, Neutral or Stable).
NOTE: The maximum reading that can be used for R-12, R-14 or R-15 is 1E7 cpm.