ML20062M095
| ML20062M095 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/23/1982 |
| From: | Owen T DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML16162A369 | List: |
| References | |
| PROC-820723-01, NUDOCS 8208190422 | |
| Download: ML20062M095 (92) | |
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O, TABLE OF CONTENTS Emergency Telephone Numbers - (03/01/82, Rev. 6)
AP/0/A/1000/01 Event Index - (03/09/82)
AP/0/A/1000/02 Unusual Event - (03/09/82) l AP/0/A/1000/03 Alert - (03/09/82)
AP/0/A/1000/04 Site Area Emergency - (03/09/82)
AP/0/A/1000/05 General Emergency - (03/09/82)
AP/0/A/1000/06 Procedure for Initiating Protective Action Guides for the General Public in the Emer-gercy Planning Zone - (03/09/82)
AP/0/A/1000/07 Procedure for Offsite Dose Calculations by Control Room Personnel or Emergency Coordinator during a Loss of Coolant Accident - (02/26/82)
AP/0/A/1000/08 Procedure for Response Actions for Accidents /
Emergencies - (10/15/81)
C AP/0/A/1000/10 Procedure for Emergency Evacuation of Station Personnel - (02/02/82)
Station Directive 2.9.1 Station Assembly and Evacuation Procedure -
(04/14/82).
Station Directive'2.9.2 Emergency Response Organization - (06/23/82)
Station Directive 5.1.3 Personal Injury Procedure - (10/19/81)
PT/0/B/2000/04 Procedure for Establishment and Inspection
.of the Technical Support Center -.(04/25/82)~
CP/1/A/2002/04A Post Accident Liquid Sampling of the Reactor =
Coolant System (12/01/81) -
CP/2/A/2002/04A- Post Accident Liquid Sampling of.the Reactor Coolant System (12/01/81)
CP/3/A/2002/04A Post Accident Liquid Sampling of the Reactor Coolant System (12/01/81)-
CP/1/A/2002/04B . Post' Accident Liquid' Sampling of the Low-L m . Pressure Injection System (12/01/81)
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\ J EPM 001/A Reviston, July- 23, 1982 I
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8208190422 820810 "
1f,F~PDR ADOCK 05000269 PDR j
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] Table of Contents (Implementing Procedures - Continued)
CP/2/A/2002/04B Post Accident Liquid Sampling of the Low Pressure Injection System (12/01/81)
CP/3/A/2002/04B Post Accident Liquid Sampling of the Low Pressure Injection System (12/01/81)
CP/0/A/2004/2C Post Accident Determination of Chloride by Specific Ion Electrode Using Beckman 4500 Meter (04/26/82, Original Issue)
CP/0/A/2004/2E Post Accident Determination of Boron Concentration Using Carminic Acid - (07/09/82)
CP/0/A/2004/3C Post Accident Determination of Chloride by Specific Ion Electrode Using Beckman 4500 Meter - (07/09/82)
CP/0/A/2005/2D Post Accident Determination of Gamma Isotopic Activity - (07/09/82)
CP/0/B/4003/01 Procedure for Environmental Surveillance Following a Large Unplanned Release of Gaseous Radioactivity - (01/13/82)
CP/0/B/4003/02 The Determination of Plume Direction and Sector (s) v to be Monitored Following a Large Unplanned Release of Gaseous Activity - (08/20/81)
HP/0/B/1009/09 Procedure for Determining the Inplant Airborne Radioiodine Concentration During Accident Conditions - (07/09/81)
HP/0/B/1009/10 Procedure for Quantifying Gaseous Releases Through Steam Relief Valves Under Post-Accident Conditions - (05/06/82)
HP/0/B/1009/11 Projection of Offsite Dose from the Uncon-trolled Release of Radioactive Materials Through a Unit Vent - (07/08/81)
' HP/0/B/1009/12 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release - (03/02/82) l HP/0/B/1009/13 Procedure for Implementation and Verification for the Availability of a Back-Up Source of l Meteorological Data (04/23/82) l HP/0/B/1009/14 Project Offsite Dose from Releases other than Through a Vent -(01/29/82) l rr ) HP/0/B/1009/15 Procedure for Sampling and Quantifying High l (ss! Level Gaseous Radioiodine and Particulate.
( Radioactivity - (04/29/82) l EPM 001/A Revision, July 23, 1982
- A 9, Oconee Nuclear Station Directive 2.9.2 (LP) (TS)
Approved e, ,
Original Date $ 10 l Revised Date (r 6 2,'$
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DUKE POWER COMPANY OCONEE NUCLEAR STATION EMERGENCY RESPONSE ORGANIZATION M
A. KEY PERSONNEL 1 Emergency Coordinator . . . . . . . . . . . . . . ..... .4 Operations . . . . . . . . . . . . . . . . . . . . ..... 5
. Maintenance . . . . . . . . .. . . . . . . . . . ..... 6 Technical Services . . . . . . . . . . . . . . . . . . . . 11 Licensing and Projects . . . . . . . . . . . . . . . . . . 13 Performance . . . . . . . . . . . . . . . . . . . ..... 17.
, Health Physics . . . . . . . . . . . . . . . . . . . . . 21 1
Chemistry . . . . . . . . . . . . . . . . . . . . ..... 25 Administration . . . . . . . . . . . . . . . . . . . . . . 26 B. FUNCTIONAL AREAS OF EMERGENCY RESPONSE 29 i
.C. IMPLEMENTATION 32 D. EMERGENCY FACILITIES 35 i E. EMERGENCY RESPONSE TRAINING 39 0
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} DUKE POWER COMPANY J OCONEE NUCLEAR STATION EMERGENCY RESPONSE ORGANIZATION 1.0 PURPOSE The purpose of this directive is to identify the organization to be used in dealing with an emergency at the Oconee Nuclear Station. Major organi-zational divisions are identified and the responsibilities accountable to this area are listed. The Emergency Response Organization is flexible and will be modified to meet the varying emergency situations. Changes to this organization will be at the discretion of the Station Manager or his designee.
To provide training and specific guidance to members of the Emergency Response Organization.
To provide training to offsite agencies identified in the Oconee Nuclear Station Emergency Plan.
2.0 SCOPE To identify essential personnel by job function for emergency response.
l To train identified essential emergency response personnel to understand their responsibilities under accident conditions.
To train identified offsite agencies to fully understand their responsi-bilities should they respond to an emergency at the Oconee Nuclear Station or become a part of the overall response to a radiological emergency. that would affect the 10-mile emergency planning zone.
3.0 EMERGENCY RESPONSE ORGANIZATION A. EMERGENCY RESPONSE ORGANIZATION - KEY PERSONNEL-(Enclosure A) l Duties and Responsibilities
- 1. Emergency Coordinator- [-
Station Manager i
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- 2. Operations (Enclosure A-2) l
- 1. Superintendent of Operations and Support Staff i
- 2. Shift Supervisor and On Shift Staff i 3. Shift Technical Advisor
- 3. Maintenance (Enclosure A-3) l Superintendent of Maintenance
- ' I&E Engineer and Support Staff Mechanical Maintenance Engineer and Support Staff Planning & Materials Engineer and Support Staff
- 4. Technical Services (A-4 thru A-8) !
- Superintendent of Technical Services
!- Licensing and Projects Engineer and Support Staff 6 Performance Engineer and Support Staff Station Health Physicist and Support Staff
( Station Chemist and Support Staff
- 5. Administration (Enclosure A-9) l Superintendent of Administration Administrative Coordinator Training-and Safety Coordinator Contract Services Coordinator 1
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' 'b OCONEE suc4 EAR STATION Enclosure A-1 TECHNICAL SUPPORT CENTER 4
ORGANIZATION CHART (Key Personnell 4
OPERATIONAL SUPPORT CENTER OSC Coordinator '
a) Chem. Techs. SHIFT SUPERVISOR bl* Safettj = : EMERGENCY COORDINATOR
- V c) Mech. Maint. ' Station Manager CONTROL ROOM d) .1 & E 4
, e) HP Teclats. '
i On Shif t Operations o
-f _ 4 4 - o SUPERINTENDENT SUPERINTENDENT SUPERINTENDENT SUPERINTENDENT u OF OF OF OF ADMINISTRATION MAINTENANCE OPERATIONS l -TECHNICAL SERVICES v
Station Health Contraet Services Instrwnent OPERATIONS
. Physicist' l Ele cal SGINEEU Safety & Training l Health Physics Center Mechanic'al Maintenance
, Administtative Services ChemistAy Clerical Support
'Lic. & Projects t
Performance i I
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l STATION MANAGER l
O['~'h EMERGENCY COORDINATOR Duties and Responsibilities
- 1. Activate Technical Support Center
- 2. Assume responsibility as Emergency Coordinator after arrival at the Technical Support Center
- 3. Coordinate technical assistance for remedial actions to mitigate circum-stances surrounding plant operations.
- 4. Designate individual to communicate with offsite agencies promptly if CMC has not been activated.
- 5. Bring key personnel to standby basis including Crisis Management Team.
- 6. Sole responsibility to initiate any emergency actions within the provisions of the emergency plan.
- 7. Escalate or descalate emergency status if the Crisis Management Center is not operational.
/ 8. Make Senior Technical and Management staff available onsite for consulta-( tion with NRC and State on periodic _ basis if CMC.has not been activated.
- 9. Coordinate all emergency actions concerning the technical aspects of the corrective actions taken.
- 10. Evacuate all unnecessary personnel on site if a radiological emergency -
exists. Order all other necessary emergency workers to-have breathing apparatus and protective clothing. Be aware of exposure guidelines of personnel. Determine. exposure guidelines of all emergency response people.
l 11. Responsible for making protective action guides for the safety and welfare of the public to the appropriate offsite agency if the Crisis Management Center / Recovery Manager is not in a position to do so. This authority:may not be delegated.
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. i ENCLOSURE A-2
, , OPERATIONS EMERGENCY RESPONSE ORGANIZATION tc ,
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/ T SUPERINTENDENT OF OPERATIONS
( ) TSC OPERATIONS WTY
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l ENGINEER j TSC_ _j
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SHIFT SUPPORT SHIFT OPERATIONS SUPERVISOR STAFF TECHNICAL ENGINEERS on CR ADVISOR UNEFFECTED OSC CR UNITS OSC 1
ON SHIFT STAFF CR ,
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\ Resconsibilities N_s)
Superintendent of Operations Major responsibilities of the Superintendent of Operations or his designee are to oversee Operations activities, monitor the emergency situation, and make rtcommendations for stabilization and recovery of the emergency situa-tion. Participate as a member of the Technical Support Center.
- Operations Duty Engineer
! Major responsibities are to cversee the Technical Support Center activities until relieved by the Statior. Manager or Superintendent of Operations. Control access to the Control Room ar.d function as a liaison between the Control Room and the Technical. Support Cer.t er .
l Shift Suoervisor lbjor responsibilities are to oversee the _ Control Room activities on the affected unit and respond to the emergency situation in accordance with Operations Emergency Procedures, the Oconee Nuclear Station Emergency Plan-and the Oconee Nuclear Station Emergency Plan Implementing Procedures.
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l Serve as the Emergency Coordinator until the Station ibnager or his designee arrives and activates the Technical Support Center. ,
Other Operations Personnel e-'s Assume positions as assigned by the Superintendent of Operations to respond
( /) to the emergency situation.
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ItAINTENANCE EMERGENCY RESPO!1SE ORGA!!IZATION
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SUPERINTENDENT OF 11AINTENANCE TSC l DUTY MECIIANICAL l r----- DUTY I 6 E 7
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!!AINTENANCE SUPERVISOR I
_ _._ __ __ ___y l SUPERVISOR '
I L- TSCJ L _ _ TSC j e
I & E ENGINEER MECllANICAL 11AINTENANCE
- PLANNING & !!ATEP.IALS SBM/OSC ENGINEER . , . ENGINEER Sall/oSC ~ OSC t
- Serves as Operational Support Center Coordinator O O O
MECllANICAL ?!AINTENAflCE EMERGENCY I;I'SPONSE ORGANIZATION
!!ECIIANICAL ttAINTENANCE ENGIt!EER
__q SBit/OSC l DUTY ?!ECllANICAL l
?!AINTENANCE l ~ ~ ~ ~ ~ ~ ' ~ - -
SUPERVISOR I
TSC L _ _ _ _ _ _.1 -
HECitANICAL HAINTEt!ANCE MECllANICAL MAINTENANCE SUPPORT ENGINEER C00RDI!!ATOR SBt!/OSC OSC m
MECllANICAL MAINTENANCE MECllANICNu MAINTENANCE ENGINEERS SUPERVISOR SBM OSC MEC11ANICAL !!AINTENANCE TECllNICIANS ,
OSC O O O
I & E EFIERGE14CY RESPONSE ORGANIZATI0ii I & E ENGINEER f ~ ~ ~ ~ ~ ~ ~l SBM/OSC g DUTY I & E l SUPERVISOR l l L __ _. _TSC__.,____f-------
co I & E SUPPORT I&E ENGINEERS SUPERVISOR SBM/OSC OSC I&E I&E
- ENGINEERS TEC11NICIANS SBfl OSC '
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PLANE 4ING & MATERIALS EMERGENCY RESP 0s4SE ORGANIZATION
- Serves as Operational Support Center Coordinator es G e #
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MAINTENANCE EMERGENCY ORGANIZATION RESPONSIBILITIES Superintendent of Maintenance Major responsibilities of the Superintendent of Maintenance or his designee will be to provide maintenance engineering and craf t support to the emergency situation and to participate as a member of the Technical Support Center.
I&E Engineer (Duty I&E Supervisor)
Major responsibilities are:
- 1) Provide I&E technical and craft support as required in responding to the emergency situation and recovery effort.
- 2) Assure required skill levels of engineers and craftsmen are available to support the emergency situation.
3). Relieve the Shift Supervisor of any interim responsibilities designated to the I&E section until the Superintendent of Maintenance is available.
Mechanical Maintenance Engineer (Duty Mechanical Maintenance Supervisor) l Major responsibilities are:
s 1) Provide Mechanical Maintenance technical and craft support as required in
- responding to the emergency situation and recovery effort.
- 2) Assure required skill levels of engineers and craf tsmen are available to support the emergency situation.
3). Relieve the Shif t Supervisor of any interim responsibilities designated to the Mechanical Maintenance section until the Superintendent of Maintenance is available.
Planning and Materials Engineer Major responsibilities are:
- 1) Provide procurement, parts, and supplies as required to respond to the emergency situation and recovery effort.
- 2) Provide planning support as required to support work actions planned.
- 3) Assure required skill levels of personnel are available to support the emergency situation.
- 4) Serve as. Operational Support Center Coordinator.
Other Maintenance Personnel
,,_ 35 ihe situation warrants, personnel not required to support an emergency situa- ,
/ -tion will be evacuated. I V} 3g
ENCLOSURE A-4 OCONEE NUCLEAR STATION TECllNICAL SERVICES EMERGENCY RESPONSE ORGANIZATION
) SUPERINTENDENT OF TECIINICAL SERVICES TSC N
t-Lv:ensing S Projects Petfotmance llcattlt Pittjsics Cinemis tat] Environmental TSC, OSC, IIPC TSC-OSC TSC*
TSC TSC Note *: TInc Envltonmental scetion teotks tcLtit tite IIcattit Plujsics Section in .tlic field monito. ting atca until tlne C.tists Ifanagement Center (CtfC) is establisited. h'Iten tlic CitC is establislted, .tlic Ticld Ifonitoring petsonnel teill repost to .tInc Of f-SLte Radiological Coordination Group teltltin tite CtfC orgainization.
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's SUPERINTENDENT OF TECHNICAL SERVICES Major Tasks and Functions - Technical Support Center Alert Status
- 1. Report to the Technical Support Center and alert all other Technical Services section heads to a standby basis.
- 2. Oversee all Technical Services operations needed to cope with the emergency situation.
- 3. Provide personnel to interface with NRC and the NRC resident inspector.
- 4. Monitor activities of Technical Service Personnel as to radiation exposure.
- 5. Make recommendations for stabilization and recovery of the emrgency situation to the Emergency Coordinator.
- 6. Develop personnel rotation schedules if emergency extends beyond eight hours.
Site Area Emergency N
j 1. Oversee all Technical Services operations needed to cope with the
/ emergency situation. Monitor radiation reports.
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- 2. Provide expertise for Performance, Licensing and Projects, and Chemistry related activities.
- 3. Provide personnel to interface with NRC.
- 4. Monitor activities of all plant personnel as to possible exposure to radiation.
General Emergency l
i 1. Oversee and coordinate all. Technical Services operations needed to cope with the emergency situation. Monitor radiation reports. Be ,
l aware of radiation exposure to personnel on. site.
! 2. Provide expertise for Performance related activites, Licensing and Projects, and Chemistry requirements.
j 3. w Provide personnel to interface 'ith NRC.
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- 4. Make recommendations for stabilization and recovery of the emergency i
situation to the Emergency Coordiator.
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ENCLOSURE A-5 OCONEE NUCLEAR STATION m LICENSING AND PROJECTS EMERGENCY CONTINGENCY PLAN I. Ecernency Resconse Oreani:stion Licensing and Station Projects Engineer Manager or Designee TSC TSC/AM Licensing and Projects Duty ,_____ _
Person (s)
TSC Emergency Preparedness Coordinator or
' Designee Licensing TSC Engineer or Designee TSC Projects Engineer or Designee AM
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) NOTF: TSC - Position is located in the Technical Support Center AM - Position is located in the Licensing and Projects Office in the Administration Building II. Essential and non-essential eersonnel A. All non-exempt personnel are considered non-essential and will be evacuated and/or requested to leave (not come to) the station as ~
dictated by the Emergency Situation. These personnel may be recalled as necessary. All exempt personnel are considered essential with the below noted exception.
B. Certain exempt personnel may be designated by the Licensing and Projects Engineer or Designee as non-essential. These personnel would be evacu-ated and/or requested to leave or not come to the station as dictated by the Emergency Situation. These personnel may be recalled and/or set up on a rotating shift as necessary.
C. A minimum of 3 personnel to fill the positions noted in the Emergency Response Organi:ation (Item I) will be considered essential for any E=ergency Situation requiring activation of the Technical Support Center (TSC).
NOTE: The E=crgency Preparedness Coordinator will be considered essential and will assist the Station Manager in the TSC as requested.
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f- s III. Designation of Alternates
( A. The positions indicated in the Emergency Response Organization (Item I) will normally be assumed by personnel permanently assigned to those positions.
B. In the absence of the Licensing and Projects Engineer, the Licensing Engineer is the designated alternate.
C. In the absence of the Licensing and Projects Engineer and the Licens-ing Engineer, the Projects Engineer is the designated alternate.
D. In the absence of the Licensing Engineer and/or Projects Engineer, alternate (s) will be designated by the Licensing and Projects Engineer or designee.
E. In the absence of the Emergency Preparedness Coordinator, an alternate will be designated by the Licensing and Projects Engineer or designee as desired by the Station Manager.
IV. Emergency Response Organization Responsibilities A. Licensing and Projects Engineer (or designee)
Major responsibilities of the Projects an Licensing Engineer are to oversee the activities of the Licensing and Projects section and to ps s interface with the Technical Support Center.
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B. Licensing Engineer (or designee)
Major responsibilities are:
- 1. Notify Resident NRC Inspector of emergency status if emergency occurs during regular working hours.
- 2. Provide station interface with the NRC Resident Inspector on questions involving the emergency.
- 3. Provide station interface relative to providing access for additional NRC personnel.
- 4. Interface between the Technical Support Center and the NRC to provide prompt and adequate information to the NRC while minimi-zing their impact on other station personnel involved in the-emergency.
- 6. Interface with General Office Licensing personnel relative to the review and application of licensing related information.
,g 7. Work with the Licensing Group in the Crisis Management Center in f i performing the finctions listed above.
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- s 8. Report to the Technical Support Center and relieve Operations of responsibility of manning the NRC Red Phone until the CMC has been established.
IV. Emergency Response Organization Responsibilities (Cont'd.)
C. Projects Engineer (or designee)
Major responsibilities are:
- 1. Provide engineering services for Nuclear Station Modifications needed as the result of the emergency.
- 2. Provide Accountable Engineer services for Nuclear Station Modifications (designed by Design Engineering Department) needed as the result of the emergency.
- 3. Provide engineering support to the TSC relative to stabilization of the emergency and management of recovery operations.
- 4. Work with the Construction and Design Engineering Group in the Crisis Management Center in developing NSM's required as a result of the Emergency.
4 D. Emergency Preparedness Coordinator (or designee)
') Major responsibilities of the Emergency Preparedness Coordinator are to assist the Station Manager in the Technical Support Center in assuring that an emergency response organization is established and other activities as requested by the Station Manager.
V. Emergency Reponse During Normal Work Hours
- A. If a condition or event obtains an emergency classification of Alert, Site Emergency, or General Emergency (requiring activation of the TSC),
the Licensing and Projects Engineer or designated alternate will. est-ablish the-above noted Emergency Response Organization.
B. The Licensing Engineer or designee will immediately notify the NRC Resident Inspector of the emergency status.
C. The Emergency Response Organization will report to the appropriate locations as specified in Section I. All other Licensing and Projects personnel will report to the Licensing and Projects office for assignment. -
D. The Emergency Response Organization will carry out the responsibilities-contained in Section IV until the Technical Support Center is deactivated.
! VI. Emergency Response During Backshift,' Holidays, and Weekends A. The Licensing and Projects duty person (s) will be initially contacted of any condition or event requiring activation of the Technical
.(/') Support Center.
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p VI. Emergency Response During Backshift, Holidays, and Weekends k
U B. The Licensing and Projects duty person (s) will perform the following activities in order:
- 1. Immediateiy notify the NRC Resident Inspector. If the Inspector cannot be reached by phone, the beeper should be utilized and the Inspector should be requested to report to the station.
- 2. Attempt to notify the Licensing and Projects Engineer or the appropriate designated alternate.
- 3. Report to the Technical Support Center and provide immediate .
licensing and/or projects support to the Superintendent of Technical Services or his/her designee.
C. If the Licensing and Projects Engineer or designated alternate has been contacted, the Emergency Response Organization will be established as above indicated.
D. If the Licensing and Projects Engineer or designated alternate cannot be contacted, the Licensing and Projects duty person (s) should obtain the support from the Licensing and Projects section required to cope with the situation (i.e., call additional engineering and/or technical support personnel required to support Technical Support Center identified requirements). Attempts to notify the Licensing and p Projects Engineer or appropriate designated alternate should continue.
E. The Licensing and Projects Duty Perscn(s) will serve in the above noted capacity until relieved by the Licensing and Projects Engineer or designee.
NOTE: If the Licensing and Projects section is utilizing two duty personnel (one for Licensing and one of Projects), both personnel should respond as above indicated. Individual responsibilities may be divided between the duty individuals as agreed upon until the Emergency Organization is established.
VII. Providing Twenty-Four Hours A Day Support If the emergency situation dictates, a shift rotation schedule will be established by the Licensing and Projects Engineer or designee. This schedule will provide for the Emergency Response Organization specified in Section I on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day basis. This schedule will continue until otherwise indicated by the Licensing and Projects Engineer or- designee or
[ until_ deactivation of the Technical Support Center.
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SCIIEI)UI.E A-6 OCONEE filiCI. EAR STATION E!!ERGENCY CONTINGENCY PLAN - PERFORt!AtlCE FUtiCT10t/AL ORGANIZATIO!!
PERFOR!!ANCE EflGINEER Performance
............._...... Engineering Staff On Call As Required i
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I Performance Duty Engineer C Until Assigned to Test or Test Engineer Reactor Engineer As Reactor Engineer Appropriate Computer Operator
- Note 1 - Reactor Engineering Staff As Required
- Note 1 -- rest Engineering Staff As Required
- Note 1 -- rest Supervisory Unit As Required
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- Note 1: Performance Engineer will determine how many personnel are required in these functions, a
- Note 2: As situation warrants, personnel not required to support the emergency situation will be evacuated.
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O OCONEE NUCLEAR STATION y
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PERFORMANCE SECTION EMERGENCY CONTINGENGY PLAN Lj' EMERGENCY RESPONSE ORGANIZATION
- 1. Minimum Essential Personnel l Performance Engineer or Designated Alternate Reactor Engineer or Designated Alternate 9
l Test Engineer or Designated Alternate Computer Operator (Qualified Assistant Nuclear Performance Technician, h Nuclear Performance Technician, or Nuclear Performance Specialist) h.
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- 2. Designated Alternates [
h Designated alternates have been determined for the following job functions: . ed.
a) Performance Engineer Primary
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Alternates (2) b) Reactor Engineer Primary i.
Alternates (2) 4 O [=
(~ c) Test Engineer Primary .
Alternates (2)
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- 3. Performance Engineer - Responsibilitie's .U E
Major responsibilities of the Performance Engineer or his designee are to y
coordinate Performance related activities and to interface with the L.
Technical Support Center. This will include, if' required, establishing a 3 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day shift coverage of at least the minimum defined organization.
- 4. Performance Duty Engineer - Responsibilities _ fh Major responsibilities are: -
-1. Notify Performance Engineer or designee.
- 2. Report to'the Technical Support Center and provide immediate support ,
to the Shif t Supervisor and/or Shif t Technical Advisor within approxi- ;'
mately 30 minutes of notification. Relieve Shift Supervisor of , f duties that are th'e responsibility of the Performance section. .;
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- 3. Obtain'the support from the Performance Section required'to cope with .k' the situation until the required organization is~ established on. site t.
by the Performance Engineer (i.e., call' additional engineering and/or-s technical support required to support Technical Support Center -
T ' identified requirements). -
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Performance management personnel (i.e. , Assistant, Associate Engineer)
(s will rotate through this position to provide twenty-four hours a day support with the ability to respond within approximately 30 minutes.
- 5. Reactor Engineer - Responsibilities Major responsibilities are to provide support in the following areas:
- 1. Reactor core physics.
- 2. Thermal and hydraulic assessment.
- 3. Recommendations as to core cooling.
- 4. Provide Engineering support in performing shutdown margin calculations.
- 6. Provide Safety Review function.
- 7. Approve plant data to be released via OAC/VA computer.
- 6. Test Engineer - Responsibilities Major responsibilities are to provide support in the following areas:
A 1. Performance assessment of ventilation systems.
O- 2. Coordination of filter testing and filter replacement.
- 3. Performance assessment of required ES and post-accident equipment.
- 7. Data Transmission Coordinator - Responsibilities
- 1. Report to TSC and establish communication via time share computer with the Crisis Management Center and General _ Office. Relieve Operations of responsibility of providing plant status data i
offsite.
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- 2. Transmit and receive data information as required.
- 3. Distribute plant data to TSC~.
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- 8. Performance Duty Engineer - Training
- All Performance Duty Engineers will be trained as to appropriate actions to take in the event of a situation which may require performance support
'(i.e., Unusual Event, Alert, Site Area Emergency, or General Emergency).
Included in this training will be specific instructions for immediate .
(within approx. 30 min.) support of Operations' personnel'_in thermal and hydraulic assessment of the reactor core and the associated cooling system. A minimum of six technicians and/or specialists will be trained i /N in the use of computer programs required to support an emergency situation.
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s 9. Performance Duty Engineer - Instructions
- 1. Notify Performance Engineer or designated alternate of the extent of the emergency.
- 2. Proceed directly to the site and report to the Shif t Supervisor.
- 3. Begin thermal and hydraulic assessment.
- 4. Continue performance-related support until the Performance Contingency Plan Organization can be established or until relieved by the Perfor-mance Engineer.
- 10. Thermal and Hydraulic Assessment Guidelines for Duty Engineers
- 1. Determine the core cooling status (i.e., normal-subcooled, saturated, or superheated-inadequate cooling) using core outlet thermocouple and reactor coolant system (RCS) pressure indications.
- 2. Determine the thermal hydraulic status of the reactor coolant system .
using RCS loop temperature, pressure and flow indications, as well as pressurizer and make-up conditions (HPI, LPI, CF).
- 3. Evaluate the core cooling mode (normal, natural circulation, or LOCA) underway and/or planned to assure that a complete thermal " pathway" is maintained.
O 4. Evaluate indirect indications of abnormal thermal hydraulic conditions and/or core damage.
- 5. Maintain data records.
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E!4CI.0S11RE A-7 IIEALTil PilYSICS
.Et!ERCENCY RESP.OriSE ORCAt!I,7.ATIOt1 Station Realth Physicist TSC t
IIPC Assistant Duty Realth Physicist
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TSC Data Report Coordinator S & C Coordinator Field 11onitorint TSC (HPC)
TSC (HPC)
Coordinator g Support Wnct ion s Coordinator (TSC - IIPC) TSC (HPC) a m
Realth Physics Field Dose Assessors Supervisor lionitoring .TSC/ilPC
~
OSC Supervisor.
(Field) - -
U IO~ Respiratory Desimetry Ffeld gtte bis Shif t & Inst. And Records Control (Fleld)
OSC (Field)
- tio te: a'h e Field !!onitor ing Coordinator will move to the Crisis !!anancment Center once
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that organization is activated and is on site. -
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g HEALTH PHYSICS EMERGENCY ORGANIZATION & RESPONSIBILITIES Station Health Physicist Major responsibilities of the Station Health Physicist or his designee are to oversee Health Physics activities and to interface with the Technical Support Center. Approve Health Physics information released to offsite agencies.
l Duty Health Physicist Major responsibilities are:
- 1. Report to the Technical Support Center and relieve Shift Supervisor of H.P. management duties. d
- 2. Notify Health Physics management personnel necessary for implementing the emergency organization.
l 3. Coordinate H.P. support and provide the Emergency Coordinator with data and evaluation of radiological surveys, monitoring and analysis reports until the Station H.P. arrives. .
S & C Coordinator -
Major responsibilities are:
- 1. Recall / notify Health Physics personnel necessary for in-plant surveillance.
i
- 2. Organize support vendor manpower and coordinate in-plant surveillance.
- 3. Keep Technical Support _ Center aware of station radiological control status.
- 4. Monitoring and decontamination of personnel.and vehicles during site evacu--
ation routes on site and at offsite personnel assembly location.
Supervisors of the S & C subsection can' fill this position i the absence of the S & C Coordinator.
l Support Functions Coordinator Major responsibilities are:
A. :Shif t, Respiratory and Instrument -
- 1. Establish an area for issuance of respiratory. equipment.
- 2. Recall / notify. personnel necessary-for supporting ~these responsibili- ,
i ties
, N 3. Maintain an adequate . supply of respiratory- equipment.
22.
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e s 4. Maintain an adequate supply of monitoring equipment.
- 5. Keep Technical Support Center aware of the status of this area.
Shif t, Respiratory and Instrument Health Physics Supervisor is responsible for the above.
Lead technicians in the Shift, Respiratory and Instruments subsection can fill this position in the supervisor's absence.
B. Radioactive Materials Control / Dosimetry and Records Control:
- 1. Establish an area for issuance of TLO's and dosimeters.
- 2. Maintain records for accountability of personnel exposure.
- 3. Recall / notify personnel necessary for supporting this activity.
- 4. Maintain records for accountability of radioactivity release to the environment.
- 5. Keep Technical Support Center aware of situation in this area.
Radioactivs Materials Control Health Physics Supervisor and Administra-tive Supervisor are responsible for the above.
/'~'\ Lead technicians in the Support Functions subsection can fill this position
( ,)
in the supervisor's absence.
C. Count Room
, 1. Implement and oversee operation of Count Room or the Emergency Count Room Equipment.
- 2. Recall / notify personnel necessary to support Count Room activities.
- 3. Keep Technical Support Ce'nter aware of situation in this area.
l l Count Room Health Physics Supervisor is responsible for the above.
1 Lead technicians in the Count Room subsection can fill this position in the supervisor's absence.
Field-Monitoring Coordinator Major responsibilities are:
- 1. Recall / notify personnel necessary for environmental surveillance.
- 2. Oversee environmental surveillance and the preparation and distribution of offsite radiological status reports.
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~'s 3 Interface with the Technical Support Cente r concerning radiological and
( ) meteorological conditions in the environment.
! 4. Identifying plume pathway. ;
Station Biologist is responsible for the above.
HPC Assistant (Health Physics Center Assistant)
- 1. Document flow of information to and from the Station Health Physicist.
- 2. Receive radiological information from the Data Report Coordinator for
- offsite notification.
i
- 3. Update radiological status board.
- 4. Maintain cpen communication with the Health Physics Center.
Data Report Coordinator Major responsibilities are:
- 1. Report to the Control Room and relieve the Shift Supervisor of the responsibility of offsite dose assessment and protective action recommendations.
("N 2. Evaluate offsite dose calculations until relieved of this responsibility
( ) by the Crisis Management Center.
v
- 3. Prepare radiological status reports and provide information to the TSC Communicator for notification offsite,
- 4. Keep Field Monitoring Coordinator aware of' radiological situation.
Personnel in the Projects and Training subsection can fill _this position.
Others
- Other Health Physics personnel will assemble in the Operational Support Center for further support assignments as necessary.- As the situation warrants, personnel not required to support the emergency situation will be evacuated.
Specific instructions for emergency response requirements, (e.g., shift schedule, job assignments, 'etc.), will be provided from the TSC prior to evacuation.
1 O
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- - ,- =
ENCLOSURE A-8
(
OCONEE NUCLEAR STATION TECHNICAL SERVICES CHEMISTRY EMERGENCY RESPONSE ORGANIZATION STATION CREMIST TSC 1
_ _1 _ _ _ _ ,
,_ _ _ DUTY CHEMIST l i CHEMISTRY SUPERVISORS i i OSC u__________a CHEMISTRY TECHNICIANS OSC Responsibilities Station Chemist Major responsib'ilities of the Station Chemist or his designee are to oversee Station Chemistry activities and to interface with the Technical Support Center
,s on Chemistry related matters.
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( ,, / Duty Chemist ,
Major responsibilities of the Duty Chemist are:
- 1. To report to the Technical Support Center and provide immediate suppoct to the Shif t Supervisor by relieving him of any Chemistry peripheral dutics until the Station Chemist arrives and assumes the management of the Chemistry activities.
- 2. Notify Station Chemist for implementation of the emergency organization.
1 Chemistry Supervisors Major responsibilities are to:
- 1. Provide the Chemistry support required from their areas of responsibility, i
- 2. Assure proper skill level personnel are available to support Chemistry requirements in the Operational Support Center.
Other Chemistry Personnel i As the situation warrants, personnel not required to support the emergency I situation will be evacuated.
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' ADMINISTRATION EMCitGENCY RESPONSC ORGANIEATION l
I l' $UPERINTimDI.NT OF Aret!NISTRATION i
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f- s EMERGENCY ORGANIZATION RESPONSIBILITIES s_s ADMINISTRATION GROUP i Superintendent of Administration Major responsibilities of the Superintendent of Administration or his designee will be to oversee the Administration activities and to interface with the Technical Support Center.
(Duty) Administrative Services Report to the Technical Support Center and relieve the Shift Supervisor 1.
of any Administration activities he may have assumed as Emergency Coordinator. Interface with the Technical Support Center until the arrival of the Superintendent of Administration or his designee.
- 2. Obtain support from the individuals required to support the activities of the Administration Group.
Administrative Coordinator The major responsibilities of the Administrative Coordinator are:
- 1. Provide 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day coverage of the switchboard.
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- 2. Establish liaison with Southern Bell for additional or special phone service.
- 3. Coordinate the location of trailers for office space or special facilities.
- 4. Coordinate additional vending requirements.
- 5. Provide additional administrative support such as telecopy, document control, typing, expense payment, clerical support, etc.
- 6. Provide support for vendor screening.
Contract Services Coordinator The major responsibil'ities of the Contract Services Coordinator are:
- 1. Assure securing of the Controlled Area and other. areas as deemed necessary. I
- 2. Screen individual request for access.
3 Provide additional badging capability.
- 4. Provide necessary janitorial services.
- 5. . Provide necesstay access controls.
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_ - _ _ . . _ _ _ _ _ _ _ _ . . _ _ - - _ _ _ _ _ _ . . - - _ _ _ - . . _ - _ _ _ _ _ -~. .- -
j Training & Safety Coordinator The major responsibilities of the Training & Safety Coordinator are:
l l
- 1. Establish, as required, orientation training such as Security, Emergency '
Plan, and Health Physics.
- 2. Establish a safety audit team to assure that the safety of personnel is not jeopardized.
- 3. Provide medical support to the Operational Support Center.
Clerical Support
- l. 1. Answer telephones.
I
- 2. Provide copy and telecopier service.
- 3. Maintain a log of various reports received and sent out of the Technical Support Center.
- 4. Distribute copies of reports to appropriate individuals in the Technical Support Center and Operational Support Center.
! 5. Provide general clerical support as needed (posting, meals, site assembly information, etc.)
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B. EMERGENCY RESPONSE ORGANIZATION - EUNCTIONAL AREAS OF EMERGENCY
RESPONSE
- 1. Emergency Reponse Coordination Shift Supervisors Station Manager Assistant. Station Manager Group Superintendents
- 2. Plant Systems Operations Superintendent of Operations Shif t Supervisor Operations Engineers On Shift Staff (Operations)
- 3. Accident Assessment Emergency Coordinator Group Superintendents Operations Engineers Shift Technical Advisor Performance Core Engineers Shif t Supervisor i
4 Radiological Environmental Survey and Monitoring j Chemistry
- Environmental Health Physics
- 5. First Aid / Rescue, Firefighting i +
Station Nurse
, Personnel who have recieved Multi-media First. Aid Safety Fire Brigade
- 6. Personnel Monitoring Health Physics - g' Private Vendor - '-
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- 7. Decontami'ation n
Health Physics Private Vendor
- 8. Security of Plant and Access Control i
Southern Security i
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- 9. Repair / Corrective Actions ,
, Maintenance 10, Personnel Accountability i
Emergency Coordinator Group Superintendents Section Heads Supervisors I
- 11. Radiological Accident Assessment Health Physics i Performance Operations Chemistry 4
- 12. Communications Emergency Coordinator Operations
! Licensing and Projects Administration Health Physics
, Performance Environmental >
- 13. -Radiation Protection Health Physics l J
- 14. Plant Chemistry Chemistry i
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( 16. Technical Support l General Office and Crisis Management Center i
i 17. Manpower Planning and Logistical Support ;
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Administration
. Crisis Management Center and General Office !
- 18. Public Information i Crisis News Center - Corporate Communications
} 19. Licensee Representative to State EOC 1
) Crisis Managem-nt Center .f>
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C. EMERGENCY RESPONSE ORGANIZATION - IMPLEMENIATION
- 1. The Shift Supervisor shall augment on-shif t resources to support the requirements of an Unusual Event class emergency. For '
Alert or higher emergency classifications, the Technical Support Center and Operational Support Center will be activated. Emer-gency response personnel have been assigned specific assembly locations. Abbreviations used to identify assembly locations include:
I TSC - Technical Support Center OSC - Operational Support Center HPC - Health Physics Center AM - Administration Building 1
SBM - Service Building Mezzanine CR - Control Room TB - Turbine Building SB - Service Building TSB - Technical Services Building ,
- 2. Normal Working Hours (Enclosure C-1)
Implementation of the Emergency Response Organization will be initiated by the Shift Supervisor. The Shift Supervisor activates the Emergency Response Organization by calling the Station Manager
, or, if he is unavailable, the Assistant Station Manager or one of the designated Group Superintendents. The Station Manager or his
[ alternate will then alert the other Group Superintendents who will
\ then put their emergency response sections into operation.
- 3. After Hours, Weekends, and Holidays (Enclosure C-2)
After hours, weekends and holidays, the Shift Supervisor initiates the Emergency Response Organization by calling the. Station Manager or, if he is unavailable, the Assistant. Station Manager, or one of the designated Group Superintendents. A call will also be made to Security at the Switchboard for them to contact all duty per-i sonnel. The duty personnel will activate the emergency response for their section. . Specific procedures for each section have been defined. Alternates have been designated for each position and each section will respond as designated to an emergency.
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OCOf;EE !.ULLEAR STATI0tl Et1ERCEllCY ORCA!IlZATIOil RECALI, ENCI.0SUR! C-1
!!ORilAI. W0ltKit!G IloliitS
!! NIT OPERATING SilIFT SifrERVISOR f HRC (RED PilotlE) h SilPERINI'EFIDENT OF OPERATIONS OFFSI1E AGENCIES
, V ASST. STATION STATION HAf1ACER CRISIS tlAf3AGEllEllt flANAGER f ORCAt11ZATI0tl m
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- IfrERINTEND'EllT OF~ 1UPERINTE!! DENT OF TECil. SERVICES -
IIAltlTEtIAtiCE ADrittll STRATIOli llcalth Physics -
- nvironmental
- I&E
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> Services
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~g Mechan ical V. Itaintenance k Sa f ety anti-
_g Licensing and 13RC Resident -
y .y.ralnlu 7 Protects inspector Planning anil
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OCClEE l;UCI. EAR SiAT10N E!!EP.SEhCY ORCAtlIZATION RECAI.L ENCI.OStil'E C-2 -
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(BAC/.SdIFTo WEEKEllDS o ll0LIDAYS)
OPERATInflS DUTY ~ -
E!!GINEER S!!IFT SUPERVISOR NRC (RED Pil0NE) v SUPERINTEllDENT OF
-f STATI0tl,11At1AGER CRISIS tfAllAGEllENT ORGANIZATION OFFSITE AGEllCIES ASST. STATION tlA!!AGER bbh}bfb"kkkhlbkS s
, SUPERI!1TE!! DENT OF 3 V . itAI!!TENANCE P Planning 6 ffaterial SWITCllBOARD
'iUPERINTE!! DENT OF ADil1NISTRAT10ft i
- Security at the Switchboard will recall Dnty Per onnel assigned to varlons sections.
TECl!NICAL _
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SERVICES HAINTENAtlCE .
ADill!!ISIRATIOf!
-k Ilealth Physics -f ",f, f " ' "
4 is t I L belt I&E
, Admin. Services l'e r f o rmanc e _ Illolog i st ,.
ticeluin ica l 11a Irit ena nce
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F Projects Inspector V Wilcox
_ Emergency Prep. l conratnntnr 1 Ch ry
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D. EMERGENCY RESPONSE ORGANIZATION - EMERGENCY FACILITIES
The Technical Support Center is a designated area to be utilized by station management, technical and engineering support person-nel for onsite emergency control. The Technical Support Center is activated for all Alert, Site Area Emergency, and General Emergency class emergencies. Enclosure D-1 shows the location of the Technical Support Center.
Provisions have been made to quickly connect the telephones of the Station Manager, Group Superintendents, and various section heads into the Technical Support Center Operational Support Center, and Health Physics Center. Switches in the Telephone Equipment i Room enables each primary member of the TSC, OSC and HPC to have the extension number he/she normally uses.
- 2. Health Physics Center (HFC)
The Health Physics Center is a part of the Technical Support Center and is tbe work location for coordinating environmental-surveillance, in-plant surveillance, offsite dose projection,-
and preparation of required radiological reports. Radio Commi-unications are available between the Health Physics Center, local Civil Defense Agencies, the State Forward Emergency Operations Center, and the nearsite Crisis Management Center.
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's .The Health Physics Network communication system is also available in this Center.
- 3. Operational Support Center (OSC) 4 The Operational Support Center is an area designated for support-personnel (i.e. , auxiliary operators, Chemistry and Health Physics technicians, I&E and Mechanical Maintenance support:
personnel, and Safety Assistants) other than those required or-allowed in the Control Room, to report for further assignments in'an emergency situation.
~ Location ~s: (Enclosure D-2)
- I&E Shop of Unit #3 - Primary location for Chemistry an'd Health' l Physics technicians,'I&E and Mechanical Maintenance support personnel, and Safety Assistants).
' Unit ~ 1&2, 3 Kitchen - Primary location'for. Operations equipment operators depending on which unit is affected by the emergency.
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- 4. Other Designated Areas In addition to the emergency response personnel located in the !
Technical Support Center and the Operational Support Center, i other station support manpower shall be assembled in their normal working space as radiological conditions permit. l t
Should the site be evacuated, personnel that was not needed to cope with the emergency conditions, would be evacuated. Specific i instructions for emergency response requirements (i.e. shif t l
schedule, job assignments, etc.) would be provided from the Technical Support Center before evacuation proceedings are instigated.
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DUKE PCWER CCMPAi4Y l EMERGENCY RESPONSE FACILITIES OCONEE NUCLEAR STATION EstcLosu,te O-1 N #
TECHNICAL SUPPORT CENTER w] UNIT 1 & 2 C0'; TROL ROOM i
Commustica. tics 1 System lutcludes: l Cu.tside Liste (Scuthetst Bell Stjstem)
ONS Su:i.tcItboa.td Alictaccave Radio ~
Telecopic.t ENS (Red Plioste)
HPN (Health Phijsies - NRC)
Ristgdctest Phaste to Of fsite Agesteies (State FECC, Occatec ECC, Picketts ECC)
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EMERGENCY RESPONSE FACILITIES OCONEE NUCLEAR STATION ENCLOSURE D-2 OPERATIONAL SUPPORT CENTER
- Location: Unit #3 I & E Shop C0!NUNICATION: '
Nuclear GNS Switchboard Equipment Microwave operators 16' x 9' (Kitchen Unit 1&2, 3 e, Control Room ) c' r'
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- The areas designated as the Operational Support Center has the same ventilation and f shielding as the Control Room. Provisions for protective clothing and breathing
( 2pparatus have been established.
(_
L/ 38 4
d E. EMERGENCY RESPONSE TRAINING
) 1. Onsite Emergency Response Training Emergency Response Training is required on an annual basis.
Records will be maintained by the Station Training Section, using TSR-10, Training Summary, as documentation. Training records of individual identified emergency response personnel
! will be audited on an annual basis (plus or minus three months) to determine that all required emergency response training is current.
Listed below are the various forms of Emergency Response Training that will be required at the Oconee Nuclear Station:
(a) Emergency Response Training Figures E-1 and E-2 designates the people to be trained according to job function.
(b) HPC Operations Training Figure E-3 designates the people to be trained according to job function.
(c) Information Transmission to Offsite Groups Training
['~' Figure E-4 designates the people,to be trained according
\ f to job function.
(d) Data Transmissions Training Figure E-5 designates the people to be trained according to job function.
(e) Field Moaitoring Team Training Figure E-6 designates the people to be. trained according to job function.
- l. Responsibility for auditing, providing and/or coordinating train-ing for Emergency Res~onse p is designated to the Emergency Pre-paredness Coordinator.
- 2. Offsite Emergency Response Training The Oconee Nuclear Station will provide for the training of certain offsite response agencies. Site specific Emergency Response Training will be:provided on an annual basis for Fire Support, Medical / Rescue, andl Governmental Support. The Local Law Enforcement Agency training program will be provided on-a bi-annual' basis. Topics and agencies to be trained are as follows:
I /
N' J' -Major Revision 39-l 9
._ . - _ . . -_. . - . ~ . . _ . _ . ._ _
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a) Emergency Response Training - Medical / Rescue Support
' _/ Oconee Memorial Hospital Emergency Room Personnel Oconee Memorial Emergency Medical Service Medical / Rescue Support training will be coordinated through the Emergency Preparedness Coordinator at the Oconee Nuclear Station, Oconee County Emergency Preparedness Coordinator, Pickens County Civil Defense Director, the Safety and Training Section at the Oconee Nuclear Station, and the Associate Administrator at the_0conee Memorial Hospital.
Training will be provided annually.
b) Emergency Response Training - Fire Support Oconee County Rural Fire Association 7 The Fire Support training will be coordinate'd through the Emergency Preparedness Coordinator at the Oconee Nuclear. ,
Station, Safety and Training Section at the Oconee Nuclear i Station, Pickens County Civil Defense Director, the Oconee County Emergency Preparedness Director, and the Oconee County Fire Marshall. Training will be provided annually to parti-cipating personnel from the county volunteer fire departments.
c) Emergency Response Training - Local Law Enforcement Agencies Oconee" County Sheriff's Department j Pickens County Sheriff's Department S. C. Wildlife State Law Enforcement Division S. C. Highway Patrol Training for participating personnel from the law enforce-ment agencies will be provided .once every two years by the Contract Services Section at the'Oconee Nuclear Station.
The training given will constitute the required' emergency.
response training to offsite law enforcement agencies.
d) Emergency: Response Training -' Governmental Support Oconee County Emergency. Preparedness Agency Pickens County Civil-Defense. Agency'-
( South Carolina Emergency Preparedness Division Bureau of Radiological Health' Designated personnel.from these agencies'will be provided training .by the Duke Power General. Office Emergency
. Response Coordinator and the.Oconee Nuclear-Station i Emergency Preparedness-Coordinator on.~an annual basis.
. Records of those attending the offsite! agency emregency
' response training sessions will be located'in tuelfiles of the Emergency Preparedness Coordinator at the.0conee'
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- Maj or ' Revision - 40 i
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DUKE POWER COMPANY 4
, OCONEE NUCLEAR STATION l
- EMERGENCY COORDINATORS !
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- FIGURE E-1 l
l Station Manager ,
4 i
i Assistant Station Manager i i
4
- Superintendent of Technical Services ,
! l t Superintendent of Maintenance i
j Superintendent of Operations l; Shift Supervisor ("A" Shift) !
4 Shift Supervisor ("B" Shift) i l- Shif t Supervisor ("C',' Shift)
. Shif t Supervisor ("D" Shif t)
Shift Supervisor ("E" Shift)
(
i Relief Shift Supervisor
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l DUKE POWER COMPANY i TECHNICAL SUPPORT CENTER PERSONNEL l GROUP #2 TIGURE E-2 EMERGENCY COORDINATOR Station Manager, Primary Assistant Station Manager,
- Alternate TECHNICAL SERVICES Superintendent of Technical Services Primary Alternates Station Chemist Primary .
Alternates Licensing and Projects Engineer Primary 4
Alternates Licensing Engineer Primary Alternates Emergency Preparedness Coordinator Primary Alternates i
Station Health Physicist- Primary Alternates S & C Coordinator Primary
. Alternate i Data Report Coordinator Primary.
Alternate-Field Monitorf; g Coordinator . Primary
, Alternate f
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[ Performance Engineer Primary L
Alternates MAINTENANCE
. Superintendent of Maintenance Primary Alternates.
I&E Engineer . Primary Alternates 42 O
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l Page 2 j FIGURE E-2 (Continued) 1 .
- GROUP #2 TECHNICAL SUPPORT CENTER PERSCNNEL (Continued)
MAINTENANCE (Continued)
Mechanical Maintenance Engineer Primary Alternates i Operational Support Center Coordinator Primary
- Alternates OPERATIONS l
Superintendent of Operations Primary Alternate l Operating Engineers (all) Primary 4
I Shift Supervisors (all) . Primary ADMINISTRATION i
Superintendent.of Administration Primary i Alternates Clerical Support Primary Alternates I
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l DUKE POWER COMP 0ANY OCONEE NUCLEAR STATION HEALTH PHYSICS CENTER GROUF #3 FIGURE E-3 STATION HEALTH PHYSICIST Primary Alternates i
DATA REPORT COORDINATOR Primary Alternates DOSE ASSESSORS Primary Alternates i
SUPPORT FUNCTIONS COORDINATOR Prim:.4y Alternates S & C COORDINATOR Primary
, Alternates HEALTH PHYSICS SUPERVISOR (OSC) Primary Alternates I
1
. COUNT ROOM Primary
' Alternates RAD MATERIALS CONTROL Primary Alternates RESP / SHIFT AND INSTRUMENT Primary
, Alterna tes .-
i l DOSIMETRY AND RECORDS (OSC) Primary-
[ Alternates SURVEILLANCE.AND CONTROL Primary Alternates.
HPC ASSISTANT Primary.
- Alternates e
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FIGURE E-4 l
HEALTH PHYSICS CENTER Data Report Coordinator
+
Dose Assessors (6) i TECHNICAL SUPPORT CENTER Emergency Preparedness Coordinator
] Licensing Engineer
- Designated Clerical Support (2) 4 CONTROL ROOM *0perations On Shift Staff l'
FIELD MONITORING Environmental (4) i
- Note:
Operations Personnel:
Shift Supervisor Unit Supervisors l Unit (or Duty) Operating Engineer
! Control Room Operators l.-
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.y Form SPD-1002-1 CONTROL COPY DUKE POWER COMPANY (1) ID No:CP/0/A/2004/02E PROCEDURE PREPARATION Change (s) na to PROCESS RECORD 1 Incorporated OCOEE WCM SMION (2) STATION:
(3) PROCEDURE TITLE: Post Accident Determination of Boron Concentration Using Carminic Acid (4) PREPARED BY: _v r0 h tA DATE: "1k6 %~Z (5) REVIEWED BY: DATE: [ d Cross-Disciplinary Review By: N/R:
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
g By: m _ Date:
(7) APPROVED BY: ( 3 M Date: 3 O
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i (8) MISCELLANEOUS:
hviewedppprovedBy: Date: 7f/v
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Reviewed / Approved By: f Date:
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- CP/0/A/2004/02E Page 1 of 11 DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT DETERMINATION OF BORON CONCENTRATION USING CARMINIC ACID I
1.0 Discussion 1.1 Scope This procedure describes the colormetric method for the post accident determination of boron concentration ([B]) in the RCS when fuel damage is estimated to be greater than 1%. -
1.2 Principle In concentrated sulfuric acid, boron forms a red colored chelation complex with carminic acid by splitting off water. Due to its hygroscopic nature, sulfuric acid aids in splitting off the water and prevents the reaction from reversing. Hydrochloric acid is added to inhibit the interference of nitrates. The intensity of the red color is proportional to the concentration of boron ([B]) in the sample, that is, it obeys Beer's law.
'Q 1.3 Limits 1.3.1 This method is applicable in the range of 0.1 to 2.0 ppm B.
1.3.2 Refer to CP/0/B/2001/03 for the laboratory' quality control of the spectrophotometer.
1.4 Interferences 1.4.1 Substances normally present in reactor' coolant do not interfere with this test.
1.4.2 Colors at 590 nm interfere, however, none are expected.
1.5 Precautions 1.5.1 DO NOT ATTEMPT ANY PHASE OF ANALYIS WITHOUT HEALTH PHYSICS COVERAGE!
1.5.2 Radiation exposure to. an individual during all phases of analysis should be limited so as not to exceed a quarterly accumulative exposure of 3 rems whole body; 7.5 rems skin
.of wholebody; or 18 3/4 rems extremities respectively.
' All personnel uill need prior authorization 'from TSC to
/'~'h knowingly exceed any. exposure limit. 'The exposure re-( ,/ ceived may' require an occupational. exposure penalty and/
. CP/0/A/2004/02E Page 2 of 11 or a medical decision as to whether an individual can
N continue in radiation work.
1.5.2.1 If r.acessary to remedy a situation immediately hazardous to lite and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities.
1.5.2.2 If necessary to save lives or prevent loss of life and/or extensive damage to property (voluntary basis only), the Planned Emergency Exposure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems skin of wholebody; or 375 rems extremities.
1.5.2.3 For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin of wholebody; 75 rems extremities; or 15 rems other single organ.
1.5.3 Radiation levels of the lab area shall be measured con-tinuously during all phases of analysis.
1.5.3.1 Air activity should be determined by use of installed air monitors or through the use of portable air sampling equipment.
1.5.3.2 Area dose rates should be established by the use of installed radiation monitors or by portable radiation survey instrument.
1.5.3.3 Portable shielding, remote handling equipment, video equipment, etc. , 'should be used where.
practical during. sample preparation and sample analysis.
I 1.5.4 Water droplets or smudge marks on the cuvettes will cause an error in absorbance. Ensure light path surfaces of cuvettes are clean and' dry.
j 1.5.5 Matched cuvettes shall be used in order to correct for i absorption due to the glass surfaces of. the cuvette.
1.5.6 Clean cuvettes with dilute nitric' acid (1 + 99), air dry, and rinse with several small portions of standard or sample before filling and reading the absorbance.
1.5.7 Samples containing more than 2 ppm B should be diluted to less than 2 ppm usign demineralized water.
l 1.5.8 The carminic acid solution is hygroscopic (absorbs water).
l Keep. tightly capped except when-using..
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. CP/0/A/2004/02E
. . Page 3 of 11 I
1.5.9 This procedure shall be donc either in a fume hood and/or i I other precautions shall be taken to avoid the release
/ of gaseous activity.
1.5.10 Maximum color development requires approximately one hour ;
with the color intensity decreasing slightly thereafter, but is of little consequence if standards are run simul-taneously with the samples.
2.0 Apparatus 2.1 Spectrophotometer suitable for measurement at 590 nanometers (nm) - (Bausch and Lomb Spectronic 70 or equivalent).
2.2 50 mm cuvettes, matched, nitric acid washed, and air dried 2.3 5 ml glass pipettes - nitric acid washed 2.4 Dispensers, preset for 5 ml and 30 ml 2.5 Dropper bottle
.2.6 Disposable beakers 2.7 100 ml glass volumetric flasks - nitric acid washed 2.8 Eppendorf pipettes with appropriate tips: 10, 25, 50, 100 p1 d 2.9 Parafilm for covering beakers l
2.10 Analytical balance 2.11 Shielded Sample Container i 2.12 Sample Tongs __
2.13 Poly bottles - 60ml (2 oz.) size 2.14 Carboy -
- 1 gal.
3.0 Reagents -
3.1 Carminic Acid Solution - Dissolve 0.50 g (10.01 g) of carminic acid in 100 mis of concentrated sulfuric acid. Mix thoroughly until l
solution is complete. Store in a plastic bottle. This solution is relatively stable for several days, but exercise care to prevent water absorption. Discard after seven (7) days.
3.2 Boron Standard (* 1000 ppm B) - Standardize either the purchased or prepared standard before use per CP/0/A/2004/02A or CP/0/A/2004/02B.
3.2.1 . Purchased Standard - Use Fisher S0-B-155 or equivalent.
- Check the expiration date before use and discard if expired.
r ,, Page 4 of 11 3.2.2 Prepared Standard - Dissolve about 5.72 g (t 0.01 g) of boric acid in dcmin. water and dilute to 1 liter with demin. water in a volumetric flask and mix.
O Stable for two (2) weeks.
3.3 Concentrated Hydrochloric Acid - Use from dropper bottle. Sp. Gr.
1.19.
3.4 Concentrated Sulfuric Acid - Sp. Gr. 1.84.
3.5 Nitric Acid (1 + 99) - Mix 1 volume of concentrated nitric acid (Sp.
Gr. 1.42) to 99 volumes of water.
4.0 Procedure 4.1 Initial Conditions .
4.1.1 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure to personnel, in the lab for the analysis.
4.1.2 Request HP to perform a constant radiation survey during the analysis. .
4.1.3 Determine and use the required respiratory equipment and protective clothing to prevent or minimize internal exposure in any Planned Emergency situation. Use high range and/or
's extremity dosimetry if required by HP.
s' 4.1.4 Prepare one (1) carboy (* 1 gal.). Label as " Post Accident Lab Waste". This container must be shielded and used as interim liquid waste disposal container for all liquid analytical waste.
4.1.5 Prepare a shielded work area in a fume hood. This area must be used for handling the sample when it is removed from the shielded sample container. '
4.1.6 Prepara a waste disposal container for all solid analytical' waste. Label as " Post Accident Lab Waste".
4.1.7 Check the serial numbers of the cuvettes to ensure that they are matched. Visually check the cells for scratches,
, cracks, chips and discoloration. Replace or clean as i
necessary.
4.1.8 Clean cuvettes with dilute (1 + 99) nitric acid and air dry.
4.1.9 Prepare a 1:2000 ' sample dilution using the post-accident sample panel or by the manual method described in Enclosure 6.5. Ensure 5 ml of diluted sample for the analysis.
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, , Page 5 of 11 4.2 Concentration Measurements 4.2.1 Prepare a series of boron standards in 100 ml volumetric O\s_- flasks by diluting measured volumes of 1000 ppm boron standard with demin. water to produce 100 m1 solution of the concentrations as follows:
pl of 1000 ppm stock diluted to 100 ml = ppm B 10 pl 0.10 25 pl 0.25 50 pl 0.50 100 p1 1.00 200 pl 2.00 4.2.2 Pipet 5 ml of demin. water (reagent blank) and each standard to separate beakers and cover.
4.2.3 Pipet 5 ml of the 1:2000 sample dilution (s) to separate beaker (s) and cover.
4.2.4 To each beaker, add 5 drops of conc. hcl and 30 ml of -
conc. H2 SO 4 , swirl to mix and cover. Allow approximately 15 minutes for cooling (less time will be needed for cooling if an ice bath is used to cool the samples).
CAUTION: Hydrogen chloride fumes and large amounts of heat may be generated during this phase.
Add the conc. H2 SO 4 slowly and exercise care.
4.2.5 Add 5 ml of carminic acid solution to each beaker and swirl to mix. Cover and allow to stand approximately 45 minutes for full color development.
4.2.6 Rinse a clean and dry 50 mm cuvette with several small portions of the reagent blank before filling the cuvette completely.
4.2.7 Set the Spec-70 wavelength to 590 nm and set the absorbance to zero with the reagent blank.
4.2.8 Record the absorbance of each reacted standard in order of increasing concentration - rinse the matched 50 mm cuvette with several small portions of-each standard before filling the cuvette. completely and reading the absorbance of that standard.
4.2.9 Record the absorbance of each reacted sample - rinse a clean and dry 50 mm cuvette with several small portions of each sample before filling the cuvette completely and reading the absorbance.
4.2.10 - Plot the data obtained in 4.2.8 on linear graph paper g'~' as shown in Enclosure 6.4.
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, CP/0/A/2004/02E Page 6 of 11 4.2.11 Compare the abs. reading (s) from 4.2.9 to the calibration curve.
4.2.11.1 If the sample concentration is > 2.00 ppm repeat 4.2.1 thru 4.2.11 using a more dilute sample.
4.2.11.2 If the sample concentration is < 2.00 ppm but
> 0.10 ppm apply the necessary dilution factor and record on the calibration curve.
4.2.11.3 If the sample concentration is < 0.10 ppm consider repeating 4.2.1 thru 4.2.11 using a less dilute sample or apply the necessary dilution factor to < 0.10 and record the "less than" value on the calibration curve.
4.3 Waste Disposal 4.3.1 Dispose of all liquid analytical waste in the " Post Accident Liquid Lab Waste" carboy. This container must be shielded and used as an interim liquid waste disposal container for all liquid analytical waste.
4.3.2 Dispose of all solid analytical waste in the " Post Accident Solid Lab Waste" container.
4.3.3 Request HP to designate an area where both post accident
\s_ / lab waste containers may be stored until final disposal.
4.3.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protective covering to prevent the spread of airborne activity.
4.4 Dose Exposure Evaluati .
l 4.4.1 Evaluate the exposure to all personnel involved and complete i all records, internal-body burden analysis, etc., as
- required. The exposure received may require an occupational l exposure penalty. Higher doses will require a medical
- decision as to whether an individual can continue in l radiation work.
l l 4.5 Data Disposition 4.5.1 Deliver Enclosure 6.4 to the Station Chemist in the Technical Support Center (TSC). Deliver a copy of Enclosure 6.4 to the Power Chemistry Supervisor. in the Operational Support Center (OSC). .
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CP/0/A/2004/02E
," Page 7 of 11 5.0 References 5.1 ASTM, Part 31, D 3082-79 Method A (1980) 5.2 B&W Water Chemistry Manual, BAW-1385 (1973) 5.3 NUREG-0737 5.4 DPC System Health Physics Manual 5.5 Radiological Health Handbook, U.S. Dept. of HEW (1970) 5.6 Radiation Safety Technician Training Course, H.J. Moe, ANL-7291 Rev.
1 (1972) 6.0 Enclosures 6.1 Shield Thickness 6.2 5, A, and R valves for 1% Failed Fuel and DBA 6.3 Conversion Factors 6.4 Typical Calibration Curve 6.5 Manual Sample Dilution 4
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CP/0/A/2004/02E Page 8 of 11 ENCLOSURE 6.1 V SHIELD THICKNESS The following equations can be used as an aid in determining shielding requirements for a saanple of RCS after an accident.
given: I=Ie* g E
where: p = p,p Y0 I/I, = e m
- In(I/I )g = -p,px in(Ig/I)
(eq. 6.1.1) p,p where: x = thickness of absorber (cm) p = linear attenuation coefficient (cIn1 )
2 p* = mass attenuation coefficient (cm /g) @ the energy level (Mev) of the source p = density of the absorber material (g/cm 3) p Ig = source intensity w/zero thickness of the absorber 1
(mR/hr or R/hr)
I = source intensity w/an x thickness of the absorber (mR/hr or R/hr) given: (HVL) I/I, = 1/2 = EYmE*
In(1/2) = -p,px (eq. 6.1.2) , ,0.693 p,p A half value layer (HVL) is that thickness- (x) of an absorber that will
~
reduce the intensity of the Source to 1/2 of its initial value. As a general rule we add one HVL to our absorber thickness calculations for conservatism:
(eq. 6.1.3) In(I o/I) + 0.693 x total ,
-p p x
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_ __ . . .-- - .. . . . . - . - . - . = _ - . _ . - - . . _ - . - - _ .
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CP/0/A/2004/02E
- Page 9 of 11 i
I ENCLOSURE 6.2 5, A and R Values for 1% Failed Fuel and DBA i i- 1% Failed Fuel:
5
- 0.34 MeV/ dis. A
- 0.293 mci /ml R = 0.18 mR/hr-mci @ la for 5
- 0.34 MeV 100% Failed Fuel or Design Basis Accident (DBA)-
i 5N 1.14 MeV/ dis. A
- 1.324 x 105 pCi/ml R = 0.58 R/hr-Ci @ la for 5 % 1.14 MeV d
A direct proportion should exist between 5 and R for any failed fuel value greater than 1% and less than 100%.
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Page 10 of 11 I
ENCLOSURE 6.3 i CONVERSION FACTORS Source Activity - (A) 1 Curie (C1) = 3.7 x 10 10 dis./sec. - 2.22 x 1 10 dpm 2 1 mci = 3.7 x 10 dps 7 = 2.22 x 10 dpm 8 I pCi = 3.7 x 10 dps4 8
= 2.22 x 10 dpm R _ mR hr-Ci hr-mci Density - (p)
(p) for elements and common materials can be found on pg 65 i
and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm3 Mass Attenuation Coefficient - (p,)
(p (MNe)) for the source can be found on pg.137 thru 139 of thefor element
" Radiological Health Handbook."
./
Distance - (d) given: I g/I = d 2/d 2 where: I g= Source intensity (mR/hf or R/hr) @ distance (dg )
I = Source intensity (mR/hr or R/hr) @ distance (d) 1 m. = 3.281 ft. = 39.37 in.
I ft.= 0.305 m 3 ft. = 0.914 m e
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- I CP/0/A/2004/02E Page 11 of 11 ENCLOSURE 6.5 MANUAL SAMPLE DILUTION 6.5.1 Place a, magnetic stirrer in the shielded work area.
6.5.2 Partially fill a glass volumetric flask with demin water and place on the magnetic stirrer in the shielded work area.
6.5.3 Using tongs remove the sample from the shielded sample container and place in the shielded work area.
6.5.4 Using a pipette transfer enough sample to the volumetric flask to produce the desired dilution.
6.5.5 Fill the volumetric flask to the mark with demin water, insert a stirring bar and cap.
6.5.6 Using tongs place the sample back into the shielded sample container. ~
6.5.7 Stir the diluted sample for ~ 5 min and allow to remain in the
. shiel'ded work area until ready for analysis or disposal.
6.5.8 Repeat 6.5.1 thru 6.5.7 for additional samplet.
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Form SPD-1002-1 CONEOL COPY DUKE PO'JER COMPANY (1) ID No:CP/0/A/2004/03C PROCEDURE PREPARATION Change (s)na to PROCESS RECORD 1 Incorporated (2) STATION:
(3) PROCEDURE TITLE: Post Accident Determination of Chloride by Specific Ion Electrode Using Beckman 4500 Meter (4) PREPARED BY: h_. , e _n i DATE: 9 k 6 k %~Z (5) REVIEWED BY: DATE: 7 Cross-Disciplinary Review By: N/R:
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Da e:
[) By: Date:'
(7) APPROVED BY: Date: 9 b N. .
(8) MISCELLANEOUS:
Reviewed / Approved By: . Date: 7 [ [V Reviewed / Approved By: Date:
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DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT DETERMINATION OF CHLORIDE BY SPECIFIC ION ELECTRODE USING BECKMAN 4500 METER 1.0 Discussion 1.1 Scope .
This procedure describes the specific ion electrode method for,the post accident determination of chloride ion concentration'([C1 ]) in the RCS when fuel damage is estimated to be greater than 1%.
1.2 Principle The chloride ion-sensitive electrode is a solid-state ion sensor.
The electrode uses a hgs /Hg2C1 2 sensing crystal at the tip of the electrode. A potential is developed by chloride iona across this
, crystal in much the same manner as a glass electrode responds to
g ,
hydrogen ions. The potential varies with the chloride ion concen-
, tration. At 25 C it exhibits a 59 mV decrease in potential for each ten-fold increase in chloride ion concentration. A plot of mV vs.
chloride concentration is prepared from standseds of known chloride concentration. The chloride concentration of unknown samples can then be determined from this curve. A typical calibration curve is shown in Enclosure 6.4. -
' 1. 3 Limits -
n 1.3.1 This method is applicable in the range of 0.05 ppm to 1.00 ppm C1 .
1.4 Interferences 1.4.1 Exposing the chloride electrode to a pH > 7 will produce an oxide film on the sensing crystal reducing the elec-trode sensitivity. Accurate measurements can be made from pH 1 to 7. Treating all sampics, standards and soak solutions with ISA will reduce the pH to
- 2 and prevent the oxide film formation.
1.4.2 Variations in total ionic strength will affect the chloride electrode response. Maintaining a constant total ionic strength over a wide concentration range by treating all samples and standards with ISA will enhance the electrode l /Si sensitivity and accuracy.
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CP/0/A/2004/03C 1.4.3 Ions which form very insoluble salts with mercury (such as S 2 I , Br , CNS ) or chromates will poison the sensing crystal reducing the electrode sensitivity. However none are expected to be present at the concentrations necessary for the poisoning to occur.
4 1.5 Precautions 1.5.1 DO NOT ATTEMPT ANY PHASE OF ANALYIS WITHOUT HEALTH PHYSICS COVERAGEt 1.5.2 Radiation exposure to an individual during all phases of analysis should be limited so as not to exceed a quarterly accumulative exposure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively.
All personnel will need prior authorization from TSC to knowingly exceed any exposure limit. The exposure received may require an occupational exposure penalty and/or a medical decision as to whether an individual can continue in radiation work. ,
l 1.5.2.1 If necessary to remedy a situation immediately hazardous to life and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of
! wholebody; or 75 rems extremities.
( ,,/ 1.5.2.2 If necessary to save lives or prevent loss of life and/or extensive' damage to property (vol-untary basis only), the Planned Emergency Ex-posure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems skin of wholebody; or 375 rems extremities.
1.5.2.3 For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin of wholebody; 75 rems i
extremities; or 15 rems other single organ.
l 1.5.3 Radiation levels of the lab area shall be measured con-tinuously during all phases of analysis.
1.5.3.1 Air activity should be determined by use of installed air monitors or through the use of portable air sampling equipment.
1.5.3.2 Area dose rates should be established by the use of installed radiation monitors or by portable radiation survey instrument.
i l 1.5.3.3 Portable shielding, remote handling equipment, video equipment, etc. , should be used where l
t f-~si practical during sample preparation and sample
\s_,/ analysis.
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d 1.5.4 SamP l es and standards shall be stirred during measurement using a magnetic stirrer to reduce electrode response tEme.
1.5.5 SEnce electrode potentials are affected by changes in temperature, samples and standards should not differ more d:an 1 5 C.
NCTE: Temperature and slope controls are inoperative in the mV and mV abs mode.
1.5.6 Samples containing more than 1 ppm chloride should be diluted to less than 1 ppm using demin water.
1.5.7 Mercuric salts are poisonous! Gloves shall be worn when handling the chloride electrode. .
1.5.8 Never store both electrodes together in the same solution.
1.5.9 The electrodes need not be immersed more than one (1) inch fer accurate readings. However, they maybe immersed further to obtain more rapid temperature equilibrium.
, 1.5.10 Always keep the reference electrode filling solution levels higher than the level of solution being measured.
1.5.11 Never operate the reference electrode with the filling s hole obstructed.
)
1.5.12 This procedure shall be done in a fume hood and/or other precautions shall be taken to avoid the release of gaseous activity.
2.0 Apparatus 2.1 Beckman 4500 Digital pH/mV Meter 2.2 Chloride Electrode (Graphic Controls PHI 91100 or equivalent) 2.3 Double Junction Reference Electrode (Graphic Controls PHE54473 or equivalent) 2.4 Beckman 583540 Multiple Electrode Selector 2.5 Electrode Holder 2.6 Magnetic Stirrer and Teflon-Coated Stirring Bars 2.7 Stopwatch, Clock or Timers 2.8 150 ml Glass Beakers 2.9 Eppendorf Pipettes with appropriate tips: 50, 100, 250, 500, 1000 pl U
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CP/0/A/2004/03C 2.10 Graduated Cylinder, 100 ml 2.11 Thermometer 2.12 Polishing Kit (Graphic controls PHA76518 or equivalent) 2.13 1 liter volumetric flask (as needed) 2.14 Erlenmeyer flask or as equivalent 2.15 Parafilm for covering beakers 2.16 Analytical balance 2.17 Shielded Sample Container 2.18 Sample Tongs 2.19 Carboy -
- 1 gal.
3.0 Reagents 3.1 Ionic Strength Adjustment Solution (ISA Solution) - slowly add about 63 mis (t I al) of concentrated nitric acid to about 437 mis (1 1 ml) of demin water. Mix thoroughly. Stable for six (6) months.
3.2 uhloride stock standard solution (100 ppm _C1") - use purchased (Orion 94-17-07 or equivalent) 100 ppm Cl standard or prepare as follows: dry sodium chloride (NaC1) to constant weight at s 105 C.
Dissolve 0.1649 g (t 0.0001) of the dry Nacl in demin water and dilute to 1 liter in a volumetric flask and mix. Purchased standard
, is stable indefinitely. Prepared standard is stable for six (6) months.
3.3 Double Junction Reference _ Electrode Filling Solutions 3.3.1 Upper fill'ing solution - use the upper filling solution supplied (Graphic Controls PHB1322 or equivalent) with the double junction reference electrode. Stable indefinitely.
3.3.2 Lower filling s.olution - use the lower filling solution supplied (Graphic Controls PHB1326 or equivalent) with the double junction reference electrode. Stable indefinitely.
4.0 Procedure 4.1 Initial Condition 4.1.1 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc.,- to minimize the exposure to personnel, in the lab for the aralysis.
I
. s ,
l 4.1.2 Request HP to perform a constant radiation survey during ;
the analysis.
4.1.3 Determine and use the required respiratory equipment and protective clothing to prevent or minimize internal ex- ,
posure in any Planned Emergency situation. Ure high range and/or extremity dosimetry if required by HP.
4.1.4 Prepare one (1) carboy (* 1 gal.). Label as " Post Accident Lab Waste". This container must be shielded and used as interim liquid waste disposal container for all liquid analytical vaste.
4.1.5 Prepare a shielded work area in a fume hood. This area must be used for handling the sample when it is removed from the shielded sample container. .
4.1.6 Prepare a waste disposal container for all solid analytical waste. Label as " Post Accident Lab Waste".
4.1.7 Ensure noth chambers of the reference electrode are filled.
4.1.8 Insure that the chloride electrode and the reference electrode is connected to back of multiple eletrode selector (MES). Place C1 channel of the NES inservice.
i 4.1.9 Place the mV meter in STANDBY and in the mV mode of operation.
f~m f 4.1.10 Prepare a sample dilution using the post-accident sample
\ panel or by the manual method described in Enclosure 6.5.
Ensure 100 ml of diluted sample for the analysis.
4.2 Concentration Measurements.
'4.2.1 Place the mV meter in STANDBY.
4.2.2 If necessary, polish the chloride electrode as follows:
4.2.2.1 Wet the cloth-covered acrylic polishing block with demin water and shake off excess water.
4.2.2.2 Place a .small amount of. alumina powder on the polishing block to form a polishing paste.
4.2.2.3 Using light pressure and circular motion polish
! the surface of the sensing crystal for s 30 l seconds.
4.2.2.4 Rinse the electrode thoroughly with demin water.
- 4.2. 2.5 Soak the electrode in 100 ml of demin water-containing 1 ml of ISA solution for about 20 l
. minutes to pre-condition the' sensing crystal.
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. CP/0/A/2004/03C 4.2.3 R:inse the eletrodes with demin water.
4.2.4 Iummerse electrodes and thermometer into 99 ml of demin water containing 1 ml of ISA solution and a stirring bar.
4.2.5 Judjust stirring rate so that there is no vortex and release tine mV meter from STANDBY.
4.2.6 Ihecord the temperature of the calibration solution.
~
4.2.7 Add 50 p1 of 100 ppm Cl standard (0.05 ppm). Wait 2 cainutes, then adjust the MES controls so that the display reads + 500 mV.
~
4.2.8 Add an additional 100 p1 of 100 ppm Cl standard (0.15 prun) . Wait 2 minutes and record the mV reading. .
~
4.2.9 Add an additional 100 pl of 100 ppe Cl standard (0.25 pra). Wait 2 minutes and record the mV reading.
~
4.2.10 Add an additional 250 pt of 100 ppm C1 standard (0.50 ppm). Wait 2 minutes and record the mV reading.
4.2.11 Add an additional 500 p1 of 100 ppm Cl standard (0.99 ppm). Wait 2 minutes'and record the mV reading.
4.2.12 Place the mV meter in STANDBY.
t 4.2.13 Plot the data obtained in 4.2.7 thru 4.2.11 on semi-log graph paper as shown in Enclosure 6.1. Record the tem-perature of the calibration solution, measured in section 4.2.6, on this graph.
NOTE: There should be,* 14 mV between-the 0.05 ppa and the 0.15 ppm CL standards.
4.2.14 Place the mV meter in STANDBY.
4.2.15 Rinse the electrodes with demin water.
4.2.16 Add I ml of ISA solution to 100 ml of the sample. dilution.
4.2.17 Immerse electrodes, thermometer,' and a stirring bar into sample /ISA solution. . Adjust stirring rate so that there is no vortex.
4.2.18 Check the temperature of- the sample and compare to that listed on the calibration curve'. The temperature should be within 15'C of that listed on the calibration curve.
4.2.19 Release the mV meter from STANDBY. Wait 2 minutes and
/ compare the mV- reading to the calibration curve.
. CP/0/A/2004/03C 4.2.19.1 If the sample concentration is > 1.00 ppm repeat 4.2.14 thru 4.2.19 using a more dilute sample.
4.2.19.2 If the sample concentration is < 1.00 ppm but
> 0.05 ppm apply the necessary dilution factor and record on the calibration curve.
4.2.19.3 If the sample concentration is < 0.05 ppm consider repeating 4.2.14 thru 4.2.19 using a less dilute sample or apply the necessary dilution factor to
< 0.05 and record the "less than" value on the calibration curve.
4.2.20 Place the mV meter in STANDBY and either repeat sections 4.2.15 to 4.2.19 for additional Cl measurements or pro-ceed to 4.2.21.
4.2.21 Rinse the electrodes with demin water and store the elec-trodes as follows:
~
4.2.21.1 Store the Cl electrode in 100 ml of demin water containing 1 ml of ISA solution.
4.2.21.2 Store the reference electrode in a separate portion of demin water.
4.2 Waste Disposal 4.3.1 Dispose of all liquid analytical waste in the " Post Accident Liquid Lab Waste" carboy. This container must be shielded and used as an interim liquid waste disposal container for all liquid analytical waste.
4.3.2 Dispose of all solid analytical waste in the " Post Accident Solid Lab Waste" container.
4.3.3 ' Request HP to designate an area where both post accident
- lab waste containers may be stored until final disposal.
t 4.3.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protectvie i covering to prevent the spread of airborne activity, i
4.4 Dose Exposure Evaluation 4.4.1 Evaluate the exposure to all personnel involved and com-plete all records, internal-body burden analysis, etc., as i required. The exposure received may require an occupational exposure penalty. Higher doses will require a medical decision as to whether an individual can continue in
! radiation' work.
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4.5 Data Disposition
( 4.5.1 Deliver Enclosure 6.4 to the Station Chemist in the Technical Support Center (TSC). Deliver a copy of Enclo-sure 6.4 to the Power Chemistry Supervisor in the Opera-tional Support Center (OSC).
5.0 References i
5.1 Beckman Model 4500 Dig %tal pH Meter Instruction Manual (1976) 5.2 Graphic Controls PHI 9100 Chloride Electrode Instruction Manual 5.3 I. Sekerka, J. F. Lechner, and L. Harrison, Analysis for Chloride
! Ion in High Purity Water and Heavy Water of Pressurized Reactors and Cooling Systems by Ion Selective Electrode (1977) .
r 5.4 BAW Water Chemistry Manual, BAW-1385 (1975) 5.5 NUREG-0737 5.6 DPC System Health Physics Manual 5.7 Radiological Health Handbook, U.S. Dept. of HEW (1970) 5.8 Radiation Safety Technician Training Course, H.J. Moe, ANL-7291 Rev. 1
{ (1972)
.h 6.0 Enclosures 6.1 Shield Thickness 6.2 5, A, and R valves for 1% Failed Fuel and DBA 6.3 Conversion Factors 6.4 Typical Calibration Curve l
! 6.5 Manual Sample Dilution e
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ENCLOSURE 6.1 SHIELD THICKNESS
\
The following equations can be used as an aid in determining shielding requirements for a sample of RCS after an accident, given: I=Ie* g E
where: p = p,p I/I = g EY P*
m In(I/Ig) = -p,px
( In(I g/I)
(eq. 6.1.1) p,p where: x = thickness of absc.;ber (cm)
I p = linear attenuation coefficient (cIni) p" = mass attenuation coefficient (cm 2/g) @ the energy level (Mev) of the source p h density of the absorber material (g/cm3)
Ig = source intensity w/zero thickness of the absorber (mR/hr or R/hr)
I = source intensity w/an x thickness of the
, s absorber (mR/hr or R/hr)
I (HVL) I/I = 1/2 = e EP given: g m*
In(1/2) = -p,px (eg. 6.1.2) , ,0.693 EP m
l A half value layer (HVL) is that thickness (x) of an absorber that will reduce the intensity of the Source to 1/2 of its initial value. As a general rule we add one HVL to our absorber thickness calculations l for conservatism:
(eq. 6.1.3) In(I /I) + 0.693 x
total = p,p l G l
NW"M* N '4"P?l'U.'W77 CTS eK*.y ""'?,0$**g. g . r* J yf7t*. 7,q'j*a m y,3
. . gy. -j_, - -
, __ ._ _ _ ____._ _ .. _ __ ~ _ _ _ . _ _ - . _ _ _ _ . _ . . _ .
i
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! . . . . CP/0/A/2004/03C i
l 1 ENCLOSURE 6.2
- 5. E
! 5, A and R Values for 1% Failed Fuel and DBA ;
i l
l 1% Failed Fuel:
l E
- 0.34 MeV/ dis. A
- 0.293 mci /ml R = 0.18 mR/hr-mci @ Im for E
- 0.34 MeV ;
100% Failed Fuel or Design Basis Accident (DBA) ,
4 5% 1.14 MeV/ dis. A
- 1.324 x 105 pCi/ml R = 0.58 R/hr-Ci @ Im for 5
- 1.14 MeV i A direct proportion should exist between 5 and R for any failed fuel t value greater than 1% and less than 100%.
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. . CP/0/A/2004/03C ENCLOSURE 6.3 CONVERSION FACTORS Source Activity - (A) 1 Curie (C!) = 3.7 x 1010 dis./sec. = 2.22 x 1012 dpm l 1 mci 7
= 3.7 x 10 dps = 2.22 x 109 dpm 1 pCi = 3.7 x 10 4dps = 2.22 x 108 dpm E R _
d hr-Ci hr-mci l
q Density - (p)
(p) for elements and common materials can be found on pg 65 and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm3 Mass Attenuation Coefficient - (p,)
(p ) for elements and common materials at varying energy levels (be ) for the source can be found on pg.137 thru 139 of the
" Radiological Health Handbook."
Distance - (d) given: 2 2 Ig /I = d /d g where: I g= Source intensity (mR/hr or R/hr) @ distance (dg)
I = Source intensity (mR/hr or R/hr) @ distance (d) 1 m. = 3.281 ft. = 39.37 in.
- 1 ft.= 0.305 m 3 ft. = 0.914 m E
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- Sample Date/Thee Sanole ID Curve Cone. st DLlution Factor = Original Conc. -~
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- CP/0/A/2004/03C 4
+
ENCLOSURE 6.5 MANUAL SAMPLE DILUTION 6.5.1 Place a magnetic stirrer in the shielded work area.
6.5.2 Partially fill a glass volumetric flask with demin water and place on the magnetic stirrer in the shielded work area.
6.5.3 Using tongs remove the sample from the shielded sample container and place in the shielded work area.
6.5.4 Using a pipette transfer enough sample to the volumetric flask to produce the desired dilution.
i 6.5.5 Fill the volumetric flask to the mark with demin water, insert a stirring bar and cap.
6.5.6 Using tongs place the sample back into the shielded sample container.
6.5.7 Stir the diluted sample for ~ 5. min and allow to remain in the ,
shielded work area until ready for analysis or disposal.
6.5.8 Repeat 6.5.1 thru 6.5.7 for additional samples.
\
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/ DUKE POWER COMPANY (1) ID No:CP/0/A/2005/02D PROCEDURE PREPARATION Change (s) na to PROCESS RECORD 1 Incorporated OCONEE NUCLEAR STATION (2) STATION:
(3) PROCEDURE TITLE: Post Accident Determination of Gar:=a Isotopic Activity (4) PREPARED BY: -ubu DATE: 1 %' %"L, (5) . REVIEWED BY: -
DATE:
7,/((2-Cross-Disciplinary Review By: N/R:
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
By: m Date:
(7) APPROVED BY: l , W Date: $ 1 s . -
3 ) (8) MISCELLANEOUS:
/ Approved By: /,
9 Date: _7 f f2 -
Reviewed / Approved _By: Date:
/ / .
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CP/0/A/2005/02D DUKE POWER COMPANY OCONEE NUCLEAR STATION POST ACCIDENT DETERMINATION OF GAMMA ISOTOPIC ACTIVITY 1.0 Discussion 1.1 Scope - This procedure describes the post accident determination of gamma isotopic activity as measured by gamma ray spectrometry in the RCS when fuel damage is estimated to be greater than 1%.
1.2 Principle - Gamma interact with lithium drifted germanium diodes or Ge(Li) detectors, having an applied electric field, to produce electric charge pulses. These pulses are proportional to the energy lost by the incident gamma. Amplifiers amplify these e.lectric pulse to produce voltage pulses. The multichannel analyzer (11CA) determines the amplitude of each voltage pulse and accumulates in a memory the number of pulses (or counts) in each amplitude band (or channel) in a given period of time. The number of counts accumulated in each channel forms a continuous curve of photopeaks called a " gamma spectrum".
The location of a photopeak in the gamma spectrum is proportional to
[s the gamma energy of the incident gamma and is the basis for identi-N fying a particular isotope in a sample. The area or total counts under a photopeak then represents the gamma activity of that partic-ular isotope in the sample. Isotopes and their gamma activity are identified and calculated by computer program using the sample data stored in the MCA memory and reference data stored in a library file on magnetic disc. The results of the " pulse-height analysis" is presented on'a paper printout. See Enclosures 6.1 and 6.2.
Certain conditions may require manual identification of photopeaks and calculation of gamma activity for isotopes not listed in the nuclide library as identified by computer program. The process of identifying photo peaks and calculating gamma activity is presented in this procedure.
1.3 Limits 1.3.1 The sample size and geometry must be selected such that i
less than 15% deadtime is encountered at the Analog to Digital Converter (ADC). _
1.3.2 The lower. limit of detectability is dependent on the background of the detector system in use, elapsed count time, sample size, sample geometry, detector efficiency and isotopes present.
l V
l l ~ . _ .
- - . ~ _. . _ _ . -- .- - .- - --. . -
- k CP/0/A/2005/02D 1.4 Interferences 1.4.1 Variations in sample geometry can cause both qualitative and quantitative variations in the gamma ray spectrum.
Calibration sources duplicating standard sample geometries can account for geometry effects.
I 1.4.2 Electronic characteristics such as deadtime, resolution and pulse pile-up degrade with increasing sample activity.
Maintaining the deadtime below 15% by reducing the sample activity via decay or volume reduction and interpreting the gamma spectrum via computer program can provide easier and more reliable sample analysis.
- 1.5 Precautions 1.5.1 DO NOT ATTDfPT ANY PHASE OF ANALYSIS WITHOUT HEALTH PHYSICS COVERAGE!
1.5.2 Radiation exposure to an individual during all phases of analysis should be limited so as not to exceed a quarterly i
accumulative exposure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively.
All personnel will need prior authorization from TSC to knowingly exceed any exposure limit. The exposure re-ceived may require an occupational exposure penalty and/
or a medical decision as to whether an individual can l ~') continue in radiation work.
! N/
1.5.2.1 If necessary to remedy a situation immediately hazardous to life and property, the Planned Emergency Exposure for Duke Power Personnel will not exceed 5 rems wholebody; 30 rems skin of wholebody; or 75 rems extremities.
I j
1.5.2.2 .If necessary to save lives or prevent loss of life and/or extensive damage to property (voluntary basis only), the Planned Emergency Exposure for Duke Power Personnel will not exceed 25 rems.wholebody; 150 rems skin of
.wholebody; or 375 rems extremities.
1.5.2.3 For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin of wholebody; 75 rems
[
extremities; or 15 rems other single organ.
l l 1.5.3 Radiation levels of the lab area shall be measured' con-tinuously during all phases of analysis.
l 1.5.3.1 Air activity should be determined by use of installed air monitors or through the'use of s portable' air sampling equipment.
x
,. . , . . , - - . . . . - ~ . _
. CP/0/A/2005/02D 1.5.3.2 Area dose rates should be established by the use O of installed radiation monitors er by portable radiation survey instrument.
1.5.3.3 Portable shielding, remote handling equipment, video equipment, etc., should be used where practical during sample preparation and sample analysis.
1.5.4 Ecsure sample container has not leaked prior to sealing in poly bag.
1.5.5 This procedure shall be done in a fume hood and/or other
- precautions shall be taken to avoid the release of gaseous activity.
2.0 Apparatus 2.1 15 cc glass gas vials with rubber septum 2.2 Hypodermic syringe - assorted sizes l
2.3 Plastic Petri Dishes (2")
2.4 Poly bottles: 50 ml, 500 m1, 1000 ml and 3500 ml.
'N 2.5 Ge(Li) . detector and multichannel analyzer (ND6600 or equivalent) 2.6 Shielded Sample Container 2.7 Sample Tongs l
2.8 Carboy - ~ l gal.
3.0 Reagents - None. . _ ,
4.0 Procedure i
4.1 Initial Conditions 4.1.1 Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the exposure ,
to personnel, in the lab for the analysis.
4.1.2 Request HP to perform a constant radiation survey during l the analysis.
4.1.3 Determine and use the required respiratory equipment and protective clothing to prevent or minimize interal exposure -
in any Planned Emergency situation. Use high range and/or extremity dosimetry if required by HP.
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,, CP/0/A/2005/02D 4.1.4 Prepare one (1) carboy (~ 1 gal.). Label as " Post Accident Lab Waste". This container must be shielded and used as
{ interim liquid waste disposal container for all liquid analytical waste.
i 4.1.5 Prepare a shielded work area in a fume hood. This area i must be used for handling the sample when it is removed l from the shielded sample container.
4.1.6 Prepare a waste disposal container for all solid analytical waste. Label as " Post Accident Lab Vaste".
4.1.7 Prepare a sample dilution using the post-accident sample panel or by the manual method described in Enclosure 6.6.
4.2 Preparation of Gas Samples for Counting ,
4.2.1 Remove about 10 cc of air from a sealed and labeled gas viar using a syringe to extract the air.
4.2.2 Insert the syringe needle through the rubber septum of the sample gas bomb. Adjust the volume of sample in the syringe to the desired volume (based on activity).
- 4. 2. 3' Quickly remove the syringe from the sample gas bomb and insert the syringe needle through the rubber septum of the gas vial, inject the sample and remove the syringe from the gas vial.
4.2.4 Seal the vial in a poly bag and' store in a plastic bag.
Allow the vial to remain in the shielded work area until ready for analysis. or disposal.
l 4.3 Preparation of Liquid Samples for Counting l 4.3.1 Transfer the desired volume of the sample dilution (based' l on activity) to a labeled poly bottle. The Ge(Li) system l is calibrated for 50 m1, 500 m1,,1000 ml and 3500 ml geo-metrie .
4.3.2 Seal the poly bottle in a poly"b'ag and s' tore in a plastic
' bag. Allow the poly bottle to remain in the shielded work area until ready for analysis or disposal.
4.4 Waste Disposal 4.4.1 Dispose of all liquid analytical waste in the " Post Accident Liquid Lab Waste" carboy. This container must be shielded and used as an interim liquid waste disposal container for all liquid analytical waite.
l 4.4.2 , Dispose of all solid analytical waste in the " Post Accident
- Solid Lab Waste" container.
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'. CP/0/A/2005/02D 4.4.3 Request HP to designate an area where both post accident
... lab waste containers may be stored until fical disposal.
4.4.4 In the event an area is grossly contaminated and cannot be decontaminated, evaluate the need for shielding or protective covering to prevent the spread of airborne activity.
4.5 Dose Exposure Evaluation 4.5.1 Evaluate the exposure to all personnel involved and complete all records, internal-body burden analysis, etc., as required.
The exposure received may require an occupational exposure penalty. Higher doses will require a medical decision as to whether an individual can continue in radiation work.
4.6 Data Disposition -
4.6.1 Deliver the gamma isotopic print-out to the Station Chemist in the Technical Support Center (TSC). Deliver a copy of the print-out to the Power Chemistry Supervisor in the Operational Support Center (OSC).
5.0 References 5.1 BAW Water Chemistry Manual, BAW-1385 (1973) 5.2 BAW Radiochemistry Manual, BAW-1410 (1975) 5.3 ASTM, Part 31, D3649-78 5.4 AST!!, Part 31, ANSI / ASTM D2459-72 5.5 NUREG-0737 5.6 DPC System Health Physics Manual 5.7 Radiological Health Handbook, U.S. Dept. of HEW (1970) 5.8 Radiation Safety Technician Training Course, H.J. Moe,.ANL-7291 Rev. 1 (1972) -- --- --- -- -
6.0 Enclosures .
6.1 Title Page of ND6600 Print-out 6.2 Summary Page of ND6600 Print-out 6.3 Shield Thickness - --
6.4 E, A, and R valves for 1% Failed Fuel and DBA 6.5 Conversion Factors 6.6 Manual Sample Dilution 1
~-. -............. ...... _.
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4.o**g......e*oo. 13 NOV 1990 12: 41: 13 'AM oooooe.o.*......o (t:cTE 1)
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- oo oo * , ++ + oo * + o o + . *e.o o o* oo o o.o. o o.... .o oo SRWP 4 (NOTE 2) ENCLOSI[RE 6.I CHEM. 2 LPI CRUD 7MPLE DATE: 7NOV30 1820: 00 tMPLE IDENTIFICATION: CRUD FILTER
- TYPE OF SAMPLE: SOLIDS SAMPLE QUANTITY: 100.0000 UNITS: ML SAMPLE GEOMETRY: FILTER.AT 6CM EFFICIENCY FILE NAME: EFF.CFILT6 o*************************************************************
ACCUISITION DATE: 13NOV80 29: 37
- FWHM(1332) 1.356 PRESET TIME (LIVE): 600. SEC
- SENSITIVITY: 5.000 ELAPSED REAL TIME: 644. SEC
- SHAPE PARAMETER : 35.0 %
ELAPSED LIVE TIME: 600. SEC
- NBR ITERATIONS: 10.
DETECTOR: GELI-C
- LIBRARY: NUCL. MASTER DATE CALIBRATED: 12NOV80 29: 45
- ENERGY TOLERANCE: 1.750KV KEV /CHNL: 0.5004218
- HALF LIFE RATIO: 8.00 OFFSET: -0.1842307 KEV
- ABUNDANCE LIMIT: 80.00%
o*************************************************************
COLLECTED BY:
- COUNTED BY:
RWP/SRWP/ LWR /GWR:
- COMMENTS:
l i
l 12SPIRATORY EQUIP USED:
- f jCONTROL GROUP USE)
DEAD TIME: 7.33%
ACTION REQUIRED: NONE ENERGY WINDOW 32.343 TO 2046.541 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 1 0 67.07 1451. 17278. 1.71 134.39 130 9 2.41SE 00 13.1 2 0 80.27 17243. 25599. 1.66 160.77 154 14 2.874E 01 1. 5 3 0 109.63 294. 11084. 1.24 219.45 213 6 4.900E-01 51.0 4 0 140.56 7004. 23187. 1.73 281.25 276 12 1.167E 01 3. 3 5 0 145.32 790. 13928. 1.52 290.77 288 7 1.317E 00 21.4 l 6 :O 153.31 656. 16112. 2.09 306.73 304 7 1.093E 00 27.7 i 7 0 161 33 9200. 27129. 1. 61 325.75 320 12 1.533E 01 2. 7 8 0 176.99 2423. 20205. 1.91 354.05 350 9 4.03SE 00 8. 5 9 0 273.52 610. 9725. 1.56 546.94 543 9 1.016E 00 23.-2 10 0 294.35 20076. 15503. 1. 78 568.59 561 15 3.346E 01 1. 1 11 0 304.87 3257. 12620. 1. 88 609.59 603 13 5.42SE 00 5. 2 12 0 319.36 1954. 10192. 1.56 639.55 634 11 3.256E 00 7. 7 13 0 323. 34 13920.l 15892. 1.74 657.48 652 16 2.320E 01 1. 5 340.51 2337. 9485. 1.66 680.31 676 11 3.896E 00 6. 2 7s 14 15 0 0 364.51 205590. 15375. 1.79 728.78 721 19 3.426E O2 ' O. 2 (s 6074. 1.56 846.77 340 13 3.587E 00 5. 6 16 0 423.56 2152.
17 3 432.50 1577. 3230. 2.00 864.64 858 24 2.629E 00 5.7 1.56E 0 13 3 437.54 1091, 2735. 1.79 374.70 ess 24 1.819E 00 7. 5 19 0 407.05 22420. 7556.- 1. 37 973.54 965 18 3.737E 01 0. 9 20 0 496.95 179. 3142. 1. 08 993.42 990 8 2.975E-01 45.0
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CP/0/A/2005/02D
... Page 1 of 2 ENCLOSURE 6.1 LEGEND FOR ENCLOSURE 6.1 NOTE 1: Date print-out generated.
NOTE 2: Title of sample.
SAMPLE DATE: Date sample collected.
SAMPLE IDENTIFICATION: Description of sample container (vial, bottle or filter).
TYPE OF SAMPLE: Gas, liquid or solid.
SAMPLE QUANTITY: Number of units and unit type for sample distributed in sample container. ,
SAMPLE GEOMETRY: Sample container at the specified distance from the detector.
EFFICIENCY FILE NAME: Describes the efficiency curve referenced as a function of the geometry.
ACQUISITION DATE: Date data acquisition began.
PRESET TIME (LIVE): User specified count time in seconds.
ELAPSED REAL TIME: Elapsed clocktime in seconds.
ELAPSED LIVE TIME: Elapsed ADC time in seconds.
FWHM: During detector calibration, the ratio of the peak width at half its maximum height of the 1332 kev (Co-60) peak is calculated. The Peak Search program applies this value to each peak to determine if it is a single or multiplet peak.
SENSITIVITY: The Peak Search program will ignore a peak whose height is less than the selected number of standard deviations above the average background in the region of the peak.
SHAPE PARAMETER: A channel must be greater than the average background in the region of the peak by the specified percentage to be considered as part of the peak area, hBR ITERATIONS: To analyze multiplet peaks, the Peak Search program will successively refine the shape of the peaks (run a line thru the points) until successive " passes" over the peaks do not differ significantly or until the maximum number (NBR) of passess as specified are reached.
. _-. , - - .. - . - -. . - - . . - = -
i
, ,, CP/0/A/2005/02D Page 2 of 2 I
ENCLOSURE 6.1 !
\
h DETECTOR: The user-selected detector used.
DATE CALIBRATED: Detector /ADC calibration date.
KEV /CHANL: Slope of the energy calibration curve in kev / Channel.
OFFSET: Intercept of the energy calibration curve in kev.
LIBRARY: Library file used for identification of peaks.
ENERGY TOLERANCE: The ND program compares the kev of detected peaks with the kev of known nuclides from the selected library file. A detected peak will be accepted as a known nuclide if its kev is within (t) the selected energy tolerance of the known nuclides kev.
HALF LIFE RATIO: For a nuclide to be considered genuine, 8 half-lives must not be exceeded between the Sample Date and the Acquisition Date.
ABUNDANCE LIMIT: The ND program will accept the identification of a nuclide having multiple gammas if the total detectable abundance exceeds the selected percentage of the nuclides absolute abundance.
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.$UM, MARY OF NUCLILE ACTIVITY PAGE 4 .
- TOTAL LINES IN SPECTRUM 58 LINES NOT LISTED IN LIERARY 13 E2iCLOSCME 6.2 IDENTIFIED IN
SUMMARY
REPORT 42 72.41%
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FISSION GAS NUCLIDE HLIFE t.L3EC DECAY UC/UT ERROR % ERR XE-131M 1.19E 01D 1.028E 06 2.264E -3 2.297E -2 6.239E -4 2.74 XE-133 5.25E 00D 4.536E 05 3.338E -3 3.115E -3 4.726E -5 1.52 ACTIVATION PRODUCT NUCLILE HLIFE HLSEC DECAY UC/UT ERROR % ERR CR-51 2.77E 01D 2.393E 06 1.901E -3 1.645E -3 1.25SE -4 7.65 MN-54 3.12E 02D 2.700E 07 1.686E -3 8.840E -5 1.100E -5 12.44 CO-58 7.08E 01D 6.117E 06 1.755E -3 5.703E -3 3.462E -5 0.61 FE-59 4.46E 01D 3.853E 06 1.809E -3 1.457E -4 2.329E -5 15.99 CO-60 5.27E OGY 1.663E 08 1.670E -3 1.415E -4 1.247E -5 8. 81 AG-110M 2.51E O2D 2.167E 07 1.691E -3 4.230E -4 1. .",63E -5 2.99 i
HALOGEN FISSION PRODUCT NUCLIDE HLIFE .HLSEC DECAY UC/UT ERROR % ERR I-131 8.04E 00D 6.947E 05 2.623E -3 3.294E -2 7.806E -5 0.24 I-133 2.08E 01H 7.483E 04 1.119.E -1 3.218E -2 1.142E -3 3. 55 R) .
ISSION PRODUCT *
'NUCLIDE HLIFE HLSEC DECAY UC/UT ERROR % ERR ZR-95 6.40E 01D 5.52SE 06 1.764E -3 1.276E -4 1.616E -5 12.66 NB-95 3.52E 01D 3.037E 06 1.349E -3 2.312E -4 1.514E -5 6.55 RU-103 3.93E 01D 3.400E 06 1.828E -3 2.556E -5 1.151E -5 45.04 CS-134 2.06E 00Y 6.501E 07 1.675E -3 1.186E -3 2.063E -5 1.74 CS-136 1.31E 01D 1.132E 06 2.202E -3 7.144E -4 1.683E -5 2.36 CS-137 3.02E 01Y 9.521E 08 1.667E -3 1.259E -3 1.776E -5 1.41 BA-140 1.2SE 01D 1.105E 06 2.216E -3 8.845E -3 1.221E -4 1.38 i LA-140 4.02E 01H 1.44SE 05' 1.468E -2 4.826E -2 4.068E -4 0. 84 L
(~s)
- , CP/0/A/2005/02D Page 1 of 1 ENCLOSURE 6.2 LEGEND FOR ENCLOSURE 6.2 TOTAL LINES IN SPECTRUM: Total number of peaks found by Peak Search program.
LINES NOT LISTED IN LIBRARY: Number of peaks not identifiable by the ND program.
IDENTIFIED IN
SUMMARY
REPORT: Number of peaks identified and accepted.
NUCLIDE: The nuclides identified by the ND program.
HLIFE: The half life of the identified nuclides in scientific notation with the appropriate time.
t HLSEC: The half life of the identified nuclide converted to seconds in scientific notation.
DECAY: The ratio of the elapsed time between the Sample Date and the Acquisition Date to the KLSEC.
UC/UT: The . activity of the identified nuclides in pCi per unit of volume or weight.
t ERROR: The confideace level (standard deviation) at I sigma, of the activity of the identified nuclides in pCi/ unit volume or weight.
% ERR: The standard deviation (i I sigma) in percentage.
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. CP/0/A/2005/02D Page 1 of 1 ENCLOSURE 6.3 SHIELD THICKNESS The following equaticas can be used as an aid in determining shielding requirements for a sample of RCS af ter an accident.
given: I = I EY*
g where: p = p,p I/I,= e m EE*
In(I/I )g = -P,PX In(Ig/I)
(eq. 6.1.1) p,p i where: x = thickness of absorber (cm) p = linear attenuation coefficient (cIn )
i p" = mass attenuation coefficient (cm 2/g) @ the energy level (dev) of the source p = density of the absorber material (g/cm 3)
I = source intensity w/zero thickness of the absorber (mR/hr or R/hr)
I = source intensity w/an x thickness of the absorber (mR/hr or R/hr) given: (HVL) I/Io= 1/2 = EE mE*
In(1/2) = -p,px (eg. 6.1.2) x ,0.693 EEm ,
A half value layer (HVL) is that th'ickness (x) of an absorber that will reduce the intensity of the Source to 1/2 of its initial value. As 2 general rule we add one HVL to our absorber thickness calculations for conservatism:
(eq. 6.1.3) M /O+0.03 g
x _
Local ~ pp l
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,.., CP/0/A/2005/02D Page 1 of 1 l ENCLOSURE 6.4 5, A and R Values for 1% Failed Fuel and DBA 1
i 1% Failed Fuel:
i
! 5
- 0.34 MeV/ dis. A
- 0.293 mci /ml l
R = 0.18 mR/hr-mci @ Im for 5
- 0.34 MeV 100% Failed Fuel or Design Basis Accident (DBA) i 5
- 1.14 MeV/ dis. A% 1.324 x 105 pCi/mi R = 0.58 R/hr-Ci @ la for 5 % 1.14 MeV A direct proportion should exist between 5 and R for any failed fuel value greater than 1% and less than 1C0%.
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- CP/0/A/2005/02D Page 1 of 1 ENCLOSURE 6.5 CONVERSION FACTORS Source Activity - (A) 1 Curie (C1) = 3.7 x 1010 dis./sec. = 2.22 x 1012 dpm 1 mci = 3.7 x 10 7dps 9
= 2.22 x 10 dpm 1 pCi = 3.7 x 10 4dps = 2.22 x 10sdpm R _ mR hr-Ci br-mci Density - (p)
(p) for elements and common materials can be found on pg 65 and 66 of the " Radiological Health Handbook." p for lead (Pb) = 11.35g/cm3 Mass Attenuation Coefficient - (p,)
(p ) for elements and common materials at varying energy levels (MEV) for the source can be found on pg. 137 thru 139 of the
" Radiological Health Handbook."
Distance - (d) given: I g/I = d 2/d g2 unare: I g= Source intensity (mR/hr or R/hr) @ distance (dg )
I = Source intensity (mR/hr or R/hr) @ distance (d) 1 m. = 3.281 ft. = 39.37 in.
I ft.= 0.305 m 3 ft. = 0.914 m s
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CP/0/A/2005/02D l Page 1 of 1 ENCLOSURE 6.6 MANUAL SAMPLE DILUTION 6.5.1 Place a magnetic stirrer in the shielded work area.
6.5.2 Partially fill a glass volumetric flask with demin water and place on the magnetic stirrer in the shielded work area.
6.5.3 Using tongs, remove the sample from the shielded sample container and place in the shielded work area.
6.5.4 Using a pipette, transfer enough sample to the volumetric flask to produce the desired dilution.
6.5.5 Fill the volumetric flask to the mark with demin water, insert a stirring bar and cap.
6.5.6 Using tongs, place the sample back into the shielded sample container.
6.5.7 Stir the diluted sample for
- 5 min. and allow to remain in the shielded work area until ready for analysi.s as disposal.
6.'5.8 Repeat 6.5.1 thru 6.5.7 for additional samples, s
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