ML20044C155
| ML20044C155 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, Millstone File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/15/1993 |
| From: | Rodgers R NORTHEAST UTILITIES |
| To: | |
| References | |
| EP-93-154, PROC-930315, NUDOCS 9303180197 | |
| Download: ML20044C155 (72) | |
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N Date: 3/15/93 CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS PROCEDURE MANUAL FROM:
R. C. RODGERS, DIRECTOR, EMERGENCY PREPAREDNESS DEPARTMENT
SUBJECT:
NEW/ REVISED PROCEDURES Attached please find new or revised procedures for the Corporate Organization for Nuclear incidents Procedure Manual assigned to you. Also find a new Table of Contents and a memo describing the changes to each procedure.
Please sign and return entire form to:
R. C. Rodgers, Emergency Preparedness NORTHEAST UTILITIES SERVICE COMPANY POST OFFICE BOX 270 (Room W-122)
HARTFORD, CONNECTICUT 06141-0270 This acknowledges receipt of the Corporate Organization for Nuclear incidents Procedures information contained in Transmittal No. 75, dated March 15,1993.
N Signature of Manual Holder
- Date Copy No.
- lf signing for the Manual Holder, please indicate Manual Holder's name.
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23 730318o197930315 Date: December 30,1992 e"
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March 15,1993 EP-93-154 l
TO:
CONI Procedure Manual Copyholders FROM:
R. C. Rodgers (Ext. 5655)
SUBJECT:
CONITRANSMITTAL NO. 75, DATED MARCH 15,1993 The position of Radiological Work Center Coordinator (RWCC) has been added to the Radiological Assessment staff. This addition requires that several CONI Section 4 procedures be updated. They are:
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CONI 4.01, Rev.14 CONI 4.02, Rev. 20 CONI 4.08. Rev.10 CONI 4.10, Rev. 20 CONI 4.08 was also revised to replace the PUFF Dose Assessment Model with ADAM, the Accident Dose Assessment Model.
Also, two CONI Section 10 procedures were revised to reflect the Emergency Preparedness Department restructuring. They are:
CONI 10.04, Rev.1 CONI 10.05, Rev.1 RCR/JGM/sba TN
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANUAL TABLE OF CONTENTS Section No.
Section Title Section 1 Common Administrative And Operational Procedures Section 2 None Section 3 Director of Corporate Emergency Response Organization Section 4 Manager of Radiological Consequence Assessment t
Section 5 Manager of Technical 5upport Section 6 Manager of Resources Section 7 Manager of External Communications Section 8 Manager of PublicInformation Section 9 NUSCO, Nuclear Operations Duty Officer Section 10 Em'ergency Plan Surveillance, Maintenance and Coordination i
Section 11 None i
Section 12 Recovery Operations Section 13 Information Resources Group Team J
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'LJ CONIT of C Rev.
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANUAL SECTION 1. COMMON ADMINISTRATIVE AND OPERATIONAL PROCEDURES TABLE OF CONTENTS Procedure Revision issue Number Procedure Title Number Date CONI 1.01 Preparation, issuance and Control 23 12/30/92 of Procedures CONI 1.02 Corporate Emergency Response 44 02/12/93 Organization (CERO)
CONI 1.03 Alerting and Notification Using 26 10/30/92 the Radiopager System CONI 1.04 CERO 5taff Training 7
12/30/92 CONI 1.05 Corporate EOC Operations 16 10/30/92 CONI 1.06 Corporate Organization for 10 07/24/92 Recovery Operations CONI 1.07 OF15 Operations 2
07/24/92 CONI 1.08 ERDS Implementation 0
02/12/93 f
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f CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANUAL O
SECTION 3. DIRECTOR OF CORPORATE EMERGENCY RESPONSE ORGANIZATION TABLE OF CONTENTS I
Procedure Revision issue Number Procedure Title Number Date CONI 3.01 On-Call CERO Director 20 02/12/93 l
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANUAL O
SECTION 4. MANAGER OF RADIOLOGICAL CONSEQUENCE ASSESSMENT TABLE OF CONTENTS Procedure Revision issue Number Procedure Title Number Date CONI 4.01 On-Call Radiological Assessment 14 03/15/93 Staff Logistics l
CONI 4.02 On-Ca0 Radiological Assessment 20 03/15/93 l
Staff Responsibilities and General Guidelines CONI 4.03 Estimating Post-Accident Release 9
12/17/90 Rates CONI 4.04 Deleted CONI 4.05 Field Team Deployment and 11 10/22/90 Radio Operation CONI 4.06 Direction of POSL Field Team 8
04/15/92 Sampling CONI 4.07 inhalation and ingestion Dose 8
04/15/92 Calculations CONI 4.08 Accident Dose Assessment Model 10 03/15/93 CONI 4.09 On-Call MeteorologicalTeam 8
02/07/92 Responsibilities and Support Functions CONI 4.10 On-Call Radiological Assessment 20 03/15/93 Staff Telephone List CONI 4.11 Radionuclide Deposition and 1
06/15/91 Dose Calculation CON 14.12 Protective Action 5'!
03/30/92 Recommendations CONI 4.13 Relocation Surveys 0
04/15/92 O
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANU AL
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O SECTION 5. MANAGER OF TECHNICAL SUPPORT i
TABLE OF CONTENTS Procedure Revision issue Number Procedure Title Number Date i
CONI 5.01 On-Call Technical SupportTeam 22 10/30/92
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SECTION 6. MANAGER OF RESOURCES TABLE OF CONTENTS i
Procedure Revision issue Number Procedure Title Number Date CONI 6.01 On-Call Corporate Manager of 3
12/30/92 Resources l
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANUAL 1
SECTION 7. MANAGER OF EXTERNALCOMMUNICATIONS TABLE OF CONTENTS Procedure Revision issue Number Procedure Title Number Date t
CONI 7.01 On-Call Manager of External 6
12/30/92 l
Communications O
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANUAL O
SECTION 8. MANAGER OF PUBLICINFORMATION TABLE OF CONTENTS Procedure Number Procedure Title Nu r
D e CONI 8.01 Publicinformation 16 02/12/93 j
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANUAL O
SECTION 9. NUSCO, NUCLEAR OPERATIONS DUTY OFFICER
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TABLE OF CONTENTS Procedure Revision issue Number Procedure Title Number Date CONI 9.01 Incident Notification and 15 11/01/91 Communication CONI 9.02 Emergency Notification 2
10/10/91 Response System (ENRS)
Operations
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANUAL Ol SECTION 10. EMERGENCY PLAN SURVEILLANCE, MAINTENANCE AND COORDINATION TABLE OF CONTENTS Procedure Revision issue Number Procedure Title Number Date CONI 10.01 Corporate EOC Equipment 25 07/24/92 Surveillance CONI 10.02 Emergency Plans Changes 1
10/30/92 CONI 10.03 Emergency Preparedness Cyclical 1
-12/30/92 Schedule CONI 10.04 Exercise Preparation 1
03/15/93 CONI 10.05 Management of Drill and 1
03/15/93 Exercise Critique items O
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SECTION 12. RECOVERY OPERATIONS TABLE OF CONTENTS Procedure Revision issue Number Procedure Title Number Date CONI 12.01 Implem,entation of Recovery 2
06/15/91 Operations O
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE MANUAL e
SECTION 13. INFORMATION RESOURCES GROUPTEAM TABLE OF CONTENTS Procedure Revision issue Number Procedure Title Number Date CONI 13.01 Information Resources Group 8
02/12/93 Team O
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE f
t CONI 4.01 ON-CALL RADIOLOGICAL ASSESSMENT STAFF LOGISTICS t
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THIS PROCEDURE CHANGE 15 APPROVED, AND APPROPRIATE 10CFR50.54(q)
ACTIONS HAVE BEEN TAKEN.
l Lead Manager, Radiological Consequence Assessment l
REVISION 14 EFFECTIVE DATE March 15,1993 CONCURRENCE Corporate Nuclest Emergency Plan Coordinator i
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE g
A.J CONI 4.01 ON-CALL RADIOLOGICAL ASSESSMENT STAFF LOGISTICS 1.0 PURPOSE This procedure defines the responsibilities and duties of the NUSCO Radiological Assessment staff as they relate to the coordination and acquisition of personnel and other support services needed during emergency operations at a nuclear power generation facility.
2.0 APPLICABILITY This procedure applies to the on-call Radiological Assessment staff (Manager of Radiological Consequence Assessment, Radiological Work Center Coordinator, l
Radiological Assessment Engineer, and Field Team Data Coordinator) and the supporting staff, the Meteorological Team and Environmental Sampling Team.
3.0 REFERENCES
3.1 CONI 1.03. Alerting and Notification Using the Radiopager System.
3.2 CONI 4.10. On-Call Radiological Assessment Staff Telephone List.
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4.0 DEFINITIONS 4.1 On-call Radiological Assessment staff-the Corporate Manager of Radiological Consequence Assessment (CMRCA), Radiological Work Center Coordinator (RWCC), Radiological Assessment Engineer (RAE), and the Field Team Data Coordinator (FTDC).
4.2 On-call Lead Manager - is the Director of the Emergency Preparedness Department.
4.3 Reporting Location - the reporting location for the on-call Radiological Assessment staff and the Meteorological Team is the Corporate Emergency Operations Center, Berlin. The reporting location for the Environmental Sampling Team is Middletown Station.
5.0 RESPONSIBILITIES The on-call Radiological Assessment staff, after receiving notification of an emergency, shall respond in accordance with Reference 3.1.
6.0 INSTRUCTIONS 6.1 On-Call Personnel A listing of the on-call Radiological Assessment staff, on-call Meteorologica!
Team, and on-call Environmental 5ampling Team appears in Reference 3.2.
CONI 4.01 Rev.
14 Date: March 15,1993 Page: 1 of 2
6.2 On-Call Schedule 6.2.1 Annually, the Lead Manager shall provide the Nuclear Operations Duty Officer with a schedule for the on-call Radiological Assessment staff.
6.2.2 Annually, the Meteorological and the Environmental Sampling Team Leaders shall provide the Nuclear Operations Duty officer with a schedule of theirteam membership.
6.3 Fan Out Notification 6.3.1 ALERT - Charlie-One, SITE AREA EMERGENCY - Charlie-Two, GENERAL EMERGENCY - Bravo or Alpha 6.3.1.1 Upon notification by radiopager or by telephone, the on-call CMRCA, RWCC, RAE and FTDC will respond to the radiopager l
message y calling in and also by immediately attempting to notify at east one other person trained as CMRCAs, RWCCs, l
RAEs, and FTDCs, respectively,,as listed in Reference 3.2.
The on-call CMRCA, RWCC, RAE, and FTDC will then report to the Berlin EOC as prescribed in Reference 3.1.
6.3.1.2 When notified, the on-call Meteorological and Environmental Sampling team members will respond to the radiopafer h
message as prescribed in Reference 3.1. They will also cal at least one more member of their respective teams to come in to provide assistance.
6.3.2 UNUSUAL EVENT-Delta-Two When notified, the on-call CMRCA will call the station Duty Officer or chemist for more details and offer assistance. Other support staff will be notified as necessary.
6.3.3 The Lead Manager will have prepared telephone number listings of his on-call staff. These will be distributed to all on-call staff. Also, this listing appears in Reference 3.2.
7.0 FIGURES None 8.0 ATTACHMENTS None j
O CONI 4.01 Rev.
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O CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE CONI 4.02 i
ON-CALL RADIOLOGICAL ASSESSMENT STAFFn RESPONSIBILITIES AND GENERAL GUIDELINES a
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O THIS PROCEDURE CHANGE IS APPROVED, AND APPROPRI ATE 10 CFR 50.54(q)
ACTIONS HAVE BEEN TAKEN.
Pt Lead Manager, Radiological Consequence Assessment REVISION
'20 EFFECTIVE DATE March 15,1993 CONCURRENCE N
Lt Corporate Nuclear E[phergency Plan Coordinator
CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE CONI 4.02 i
ON-CALL RADIOLOGICAL ASSESSMENT STAFF i
RESPONSIBILITIES AND GENERAL GUIDELINES i
1.0 PURPOSE To provide a listing of the major responsibilities of the on-call Corporate radiological assessment staff positions; the Corporate Manager of Radiological Consequence Assessment (CMRCA), the Radiological Work Center Coordinator (RWCC) the Radiological Assessment Engineer (RAE), and the Field Team Data Coordinator (FTDC), and the support position of meteorologist. This procedure provides guidelines and a general strategy for the CMRCA.
2.0 APPLICABILITY This procedure is to be used by the on-call Corporate radiological assessment staff.
3.0 REFERENCES
3.1 Millstone Station Emergency Plan implementing Procedures.
3.2 Haddam Neck Station Emergency Plan implementing Procedures.
3.3 CONI Procedures - Section 4.
3.4 CONI Procedures 1.05,1.07, and 3.01.
3.5 EMIT Manual.
3.6 Emergency Reference Manual.
3.7 State of Connecticut Emergency Response Plan.
3.8 State of Connecticutingestion Pathway Plan.
4.0 DEFINITIONS Ncne.
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1 5.0 RESPONSIBILITIES g
5.1 General Each member of the on-call radiological assessment staff is responsible for understanding the rec luirements of their position as outlined in this procedure. During an mcident, the CMRCA has overall responsibility for assuring that the requirements of this procedure are fulfilled. The corporate radiological assessment staff report to the CERO Director through the CMRCA.
This staff supports the station EOC staff and State DEP staff, through the l
CMRCA, in determining radiological consequences and recommending protective actions.
5.2 Corporate Manaaer of Radioloaical Consequence Assessment l
l The CMRCA should ensure that the functions in this procedure, as outlined below in section 6.1, are fulfilled. During an incident, the CMRCA will direct t
l the activities of the radiological on-call staff in meeting the requirements of 1
this procedure. Further, the CMRCA will use his expertise to interpret results of calculations. The CMRCA will directly interface with the DCERO and State l
DEP in providing Protective Action Recommendations (PARS) per CONI 4.12.
5.3 Radioloaical Work Center Coordinator The RWCC will coordinate and review the work of the RAE, FTDC, and Meteorologist to ensure the direction provided by the CMRCA is carried out and a comprehensive evaluation (not only data)is provided to the CMRCA.
5.4 Radioloaical Assessment Enaineer The Radiological Assessment Engineer (RAE) performs calculations (i.e.,
manual and/or computer) to determine radioactive releases, doses, and core damage estimates. During an incident, the RAE will perform analytical tasks assigned by the CMRCA through the RWCC in compliance with this procedure.
5.5 Field Team Data Coordinator The Field Team Data Coordinator (FTDC) provides the strategy and logistics of field team deployment and data collation and reponing. During an incident, the FTDC will perform tasks assigned by the CMRCA through the RWCC in compliance with this procedure.
5.6 Meteoroloaist The Meteorologist obtains and interprets actual and forecasted meteorological conditions. During an incident, the meteorologist will perform tasks assigned by the CMRCA or through the RWCC in compliance with this procedure.
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6.0 INSTRUCTIONS l
6.1 Primary Functions of the CMRCA The following lists the primary functions of the CMRCA and some general guidelines on how to carry these out:
6.1.1 Assist the CERO Director in recommending changes to the emergency l
classification.
6.1.2 Identify the accident sequence through discussions with the Manager of Technical Support. Use OFl5 or, if unavailable, communicate with the station to obtain radiation monitor readings to maintain awareness of radiological conditions on-site. Specify to the RWCC and RAE the assumptions for parametric calculations using Attachment
- 8. E.
6.1.3 Develop public PARS for the DCERO who will in turn provide them to l
the State through the NU Corporate Representative in the State EOC.
If possible, the CMRCA should discuss these recommendations in advance with the State DEP in the State'EOC.
Initiate PAR preparations immediately in anticipation of a GENERAL EMERGENCY. They should be provided to the State preferably at the time of declaration of a GENERAL EMERGENCY. Use CONI 4.12 and Attachments 8.J,8.K, and 8.L as appropriate. In fast-moving events, verbal concurrence by the CERO Director is appropriate.
6.1.4 Notify the CERO Director the first time any off-site dose rates exceed 5 mR/hr, 50 mR/hr,1,000 mR/hr, or 5,000 mR/hr for the whole body and/or thyroid dose rates exceed 25 mrem /hr, 250 mrem /hr, 5,000 mrem /hr, or 25,000 mrem /hr.
6.1.5 Provide technical support to the Site Manager of Radiological Consequence Assessment, the Site Manager of Radiological Dose Assessment, and the State DEP at the State EOC.
l Determine the Site Manager's priorities for technical and resource support. For example, the Site MRCA may need assistance in determining core damage estimates or in reducing radiation exposure.
6.1.6 Manage and direct support staff activities. Staff the Work Center with additional call-out personnel as soon as possible. If necessary, set up the expanded two shift organization, using the guidelines in.D.
Establish control on appropriate Work Center activities such as calculations and release of radiological and meteorological data. Establish the strategy to be used in off-site dose assessment (Attachment 8.C). Anticipate conditions / actions as much as possible. Keep Work Center key staff informed of plant status.
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i 6.1.7 Inform the Manager of Technical Support of radiological conditions which may affect the completion of their recommendations for plant recovery. Obtain data on core uncovery times, operation of radioactivity mitigating systems, containment pressure reduction, etc.,
which affect off-site projected / actual dose calculations. Perform j
radiological based core damage assessments and compare with l
thermo-hydraulics estimates from ManagerTechnical Support.
6.1.8 Provide updated Meteorological and Field Team Data, as necessary, to l
l the station MRCA and MRDA as well as the State DEP in the State EOC.
l Review and initial all data prior to transmittal.
l 6.1.9 Periodically update the Environmental Sampling Team (POSL) with l
plant status and meteorology. Wind direction data is needed for them to assess their potential habitability problems. If release rates significantly change, this may also be important to discuss with them.
6.1.10 Provide, as necessary, updated meteorological data to the Emergency l
Planning Zone towns using the FAXWorks System.
Have the i
meteorologist complete Attachment 8.M and have it transmitted as follows:
e Dial 1-800-833-4329 on the FAX machine telephone to access FAXWorks.
When asked, enter the password followed by the star key; enter e
7561708*.
To send a FAX, press 1.
e Four transmittal options will be offered. Select the first, which is to e
send the FAX immediately. Press 1.
The destination FAX number or list number will be requested.
Enter the list number followed by the star key. Enter 1* for Millstone EPZ towns or Enter 2* for Connecticut Yankee EPZ towns.
. io transmit to both lists, enter 1*2*.
Press the pound (#) key on the telephone to end list number entry.
e At the tone, press the FAX machine start button, then hang up the e
telephone.
6.1.11 Provide emergency dosimetry services.
Obtain or assist the Station Manager of Radiological Consequence Assessment in obtaining additional dosimetry or monitoring instrumentation as necessary.
e NUSCO TLD Lab e The alternate nuclear site Other nuclear facilities in the area. Phone numbers are given in CONI 4.10.
CONI 4.02 Rev.
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6.1.12 Maintain a log of data /information on all key events brought to your m
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attention and communications made.
6.2 Primary Functions of the RWCC The RWCC's primary functions and some general guidelines on how to accomplish them are as follows:
6.2.1 Ensure effective communications among the radiological staff. For example, ensure plant status information obtained from the main EOC is communicated to the Work center staff, ensure key calculation i
l results or field team measurements are communicated to the CMRCA.
implement the radiological assessment strategy established by the CMRCA.
6.2.2 Provide guidance and technical oversight to the RAEs and FTDCs.
Discuss strategy with these individuals and ensure actions are effective. Summarize data and provide results for the CMRCAs (e.g.,
location and extent of the plume footprint, correlation of calculated and measured dose rates, key data thresholds per 6.1.4).
6.2.3 Review the radiological, meteorological, and environmental data provided to the CMRCA and the State.
6.2.4 Communicate information to the State DEP and station personnel as requested by the CMRCA.
[V3 6.2.5 initiate and maintain the Work Center Log and Checklist. Perform other duties as assigned by the CMRCA.
6.3 Primary Functions of the RAE The following) lists the primary functions of the Radiological Assessment Engineer (RAE and some general guidelines on how to carry out these responsibilities.
6.3.1 Provide Technical Support to the CMRCA Upon receiving ouidance from the CMRCA or RWCC on the prioritization of work requests, the RAE will be responsible for performing technical assessments and calculations, including calculation of release rates and resultant offsite doses and correlation of calculated and measured doses. In addition, the RAE may be assigned to perform other tasks such as core damage estimates, shielding calculations, etc. Use Attachment 8.E to identify the assumptions for parametric calculations.
l 6.3.2 Make Frequent Reports to the RWCC and FTDC r
l The RAE should provide u adates of dose calculations to the RWCC and obtain approval to use tais information prior to issuing it to other station or corporate staff. Notify the CMRCA if predictions on l
,o calculated dose rates will exceed the values in 6.1.4.
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6.3.3 Document Calculations The RAE should document all calculations and important communications and insure that date and time are noted.
6.4 Primary Functions of the FTDC The Field Team Data Coordinators' primary functions and some guidelines on how to accomplish them are as follows:
6.4.1 Be the Source of Technical and Looistic Control for Off-Site Field Teams The FTDC will assume control of field team deployment as soon as possible, and preferably when the team is ready to leave the site EOF.
The FTDC will operate under the direction of the RWCC and will furnish instructions to the offsite Field Teams. The FTDC will interact with the RWCC and RAE in order to determine proper deployment so as to locate and track the radioactive plume in an expeditious manner.
6.4.2 Document the Radioloaical Monitorino Reports of Field Teams The FTDC will keep reports on the radio transmissions of the Field Teams in accordance with CONI 4.05.
6.4.3 Track Radioloaical Doses of Field Teams in Liaison with the Station The FTDC will track and log exposures of the field teams and will track allowable exposures with the assistance of the Station MRDA.
6.4.4 Inform the RWCC or the CMRCA when measured dose rates exceed the levels in 6.1.4.
6.5 Execution of Duties it is the responsibility of the CMRCA in conjunction with the CERO Director to determine the needs and priorities of all radiological tasks to be performed.
The CMRCA should perform and/or direct the radiological assessment staff to perform jobs as appropriate. Attachments 8.A and 8.B provide checklists of some tasks and responsibilities of the on-call CMRCA. These checklists are a i
guide for the CMRCA and should be reviewed periodically during an incident.
I 7.0 FIGURES None l
I CONI 4.02 Rev.
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l 8.0 ATTACHMENTS Attachment No.
Attachment Title l
8.A CMRCA Task Checklist i
i 8.8 Work Center Checklist 8.C Dose Assessment Guidelines 8.D Call-out Expanded Organization Guidelines I
I 8.E Dose Calculations -Input Information 8.F Connecticut Yankee Plant 8.G Millstone Unit 1 i
8.H Millstone Unit 2 8.1 Millstone Unit 3 8.J Imminent Core Damage -Whole Body Dose Estimate 8.K Plume Profile Off Centerline - Elevated Release 8.L Plume Profile Off Centerline-Ground Release 8.M Weather (Meteorological) Status j
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ATTACHMENT 8.A
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CMRCA TASK CHECKLIST Time Completed Notes A.
Staffing 1.
Confirm that all On-Call Staff have reported.
2.
Contact additional Call-Out personnel for sup aort as necessary. Establish expanc ed organization per.D.
3.
Consider the possibility of staffing for extended time periods.
4.
Consider staffing CT or RI State EOCs.
B.
Hardware - EOC 1.
Initiate log of activities in the EOC.
2.
Ensure information Resources Group (IRG) representative prioritizes IBM Mainframe. If not, callIRG,Wethersfield (8-702-4051) for prioritization of computer resources:
a.
For an emergency, indicate Affected Site and " Code 1 Nuclear Emergency."
b.
For an exercise, indicate Affected Site and " Code 2 Nuclear Exercise."
c.
For a drill, indicate Affected Site and " Code 3 Nuclear Drill."
3.
Hot line to station RCA Manager.
4.
Hot line to station RDA ManagerN/ork Center.
5.
Internal Ext.3805 with Work Center Ext. 5199 or 5298.
6.
Outside line 666-3397.
7.
Meteorological Team Ext. 5294.
g CONI 4.02 Rev.
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ATTACHMENT 8.A nU CMRCA TASK CHECKLIST Time Completed Notes B.
Hardware - EOC 8.
Hot line to State DEP in State EOC (or alternate phone).
9.
Access the Offsite Facilities information System (OF15).
(See CONI 1.07 for instructions.) Log on using BE091 AZ.
- 10. Have Work Center complete their checklist.
C.
Inform CERO Director when Staffing and Equipment are Operational.
- 11. On-Going MajorTasks This list should be reviewed periodically for applicability. The items here are to done in
,o accordance with the priorities set by the CMRCA. Ensure that these tasks are
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documented in the logbook.
A.
Key Tasks 1.
Assist the CERO Director in incident classification recommendations to the SERO Director.
2.
Identify to the RWCC, the calculations to be done by the RAE. Identify or l
predict the release pathway through the plant systems. Use Attachment 8.E to specify inputs for dose calculations.
3.
Initiate as soon as possible the PAR development using CONI Procedure 4.12.
l Commence filling out the appropriate data on the forms in anticipation of approaching GENERAL EMERGENCY. Use, as appropriate, the quick method of whole body dose calculation Attachment 8.J and the Plume Profile data in Attachments 8.K and 8.L 4.
Keep DCERO informed - plant status, in-plant operations - to mitigate l
radiation releases or core uncovery and field team data.
5.
Determine the needs of the Station Managers of RCA and RDA. A!so, keep them informed on dose and core damage assessment results, field team data, and meteorologicalinformation.
6.
Keep State DEP informed on meteorology, effluent parameters, dose (3
assessments, and field team data. Also, discuss protective action strategies
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and formulate recommendations.
CONI 4.02 Rev.
20 Date: March 15,1993 Page: 8.A-2 of 4
i i
ATTACHMENT 8.A h'
CMRCA TASK CHECKLIST B.
Calculations and Recommendations 1.
Have source terms calculated. Some methods are grab samples (CONI 4.03),
radiation monitor readings (CONI 4.03, EPIPs - Ctmt High Range Monitors),
process system inventories (EMIT Manual), piping source terms, PASS systems.
i Take note of sampling time and location. Is this a representative sample?
2.
Have release rates calculated. Methods include CONI 4.02 Attachments 8.E and 8.J, CONI 4.03, and station EPIPs.
3.
Have off-site doses (actual and projected) calculated. Methods include station EPIPs, CONI 4.02 Attachment 8.J, and CONI 4.08 (ADAM). From a radiological standpoint, verify classification as soon as possible.
4.
Have data correlated. Compare calculated dose rate data with actual data collected from the Field Teams. When appropriate, adjust calculations. See CONI 4.05.
5.
Based on the results of calculations, verify proper classification and ensure that station and State DEP are updated with the latest information.
6.
Provide technical resource support. The station or Corporate EOC may require l
technical resource support in a variety of areas (e.g., shielding calculations, l
on-site dose rate estimate, etc.).
7.
Provide emeroency dosimetry services to station. Services can be obtained l
from NUSCO TLD lab, alternate nuclear site, or other nuclear facilities in the area. List appears in CONI 4.10.
8.
Provide additional health physics personnel. Work with Manager of Resources. Personnel may be available from the lists in CONI 4.10 or CONI 1.05.
9.
Provide guidance on potassiurn iodide tablets to NU offices and power plants.
i (For locations, see CONI Procedure 3.01.)
- 10. Direct the collection of TLDs and environmental samples. Method given in CONI 4.06.
- 11. Direct the analysis of environmental samples. Method given in CONI 4.06,
- 12. Calculate the incestion Pathway doses per CONI 4.07,if appropriate.
- 13. Perform core damage assessment.
O'
)
CONI 4.02 Rev.
20 Date: March 15,1993 Page: 8.A-3 of 4
i ATTACHMENT 8.A
(~
CMRCA TASK CHECKLIST l
C.
Information Flow l
1.
Obtain on-site Field Team data from site Manager RCA.
2.
Keep Work Center informed of current conditions.
3.
Review all essential Work Center calculations. Sign off data leaving the Work Center (e.g., that is going to site managers RCA or RDA, State EOC, or other Managers in Corporate EOC).
4.
Distribute met data (forecast about once/ hour and actual about every 15 minutes) from on-call Meteorologist to Work Center, Site EOF, Manager Radiological Dose Assessment, and State DEP.
5.
Distribute Field Team Data and Dose Calculation Results to site EOF, Manager Radiological Dose Assessment, and State DEP.
6.
Provide State DEP with assumptions on plant parameters for an off-site dose l
calculation. Initialize models and assumption as soon as possible. Then periodically update data. Send copy to Site EOF Manager Radiological Dose Assessment.
O 7.
Verify that FTDC is providing guidance to Field Teams on sampling locations d
and plant status.
8.
Discuss plant status with Manager of Technical Support, especially core uncovery and radioactivity mitigating systems. Follow OF15 data to maintain awareness of plant radiological conditions.
9.
Brief site MRDA on off-site Field Team data, results of calculations, weather forecasts, etc.
- 10. Keep NRC representative in EOC informed as necessary.
- 11. Ensure status boards are updated with correct radiologicalinformation.
- 12. Keep POSLinformed of plant conditions and meteorology.
(m
, (
l CONI 4.02 Rev.
20 Date: March 15,1993 t
Page: 8.A-4 of 4
l l
i ATTACHMENT 8.B gi WORK CENTER CHECKLIST The RWCC or an assigned staff member should accomplish this checklist.
Time Completed Notes /Name 1.
Initiate log of work center activities.
2.
Check Hot line to POSL.
l l
3.
Check outside phones.
l l
4.
Radio connection with Site EOC and Field Team.
5.
Check NU Berlin computer for operability.
Log on using BE09182, BE091CE, or BEO91DE-6.
Check operability of portable computers.
7.
Obtain meteorological data from time of notification to present.
O i
O CONI 4.02 Rev.
20 Date: March 15,1993 Page: 8.B-1 of 1
i ATTACHMENT 8.C DOSE ASSESSMENTGUIDELINES This document provides a general discussion of dose assessment strategy for the Corporate Manager of Radiological Consequence Assessment (CMRCA); Radiological Work Center Coordinator (RWCC); Radiological Assessment Engineers (RAE); and the Field Team Data Coordinators (FTDC) as guidance on the proper utilization of various resources available at the Corporate EOC. It is understood that every situation is different and that what follows might not always apply. In all cases, the CMRCA will make the final determination of actions and priorities.
Purpose of Dose Assessment The results of a dose (or dose rate) assessment will be used for the following purposes (in order of priority):
Give important information for the proper determination of event classification.
e As a basis for periodic reports to the DCERO to be used in the development of e
recommendations for public protective actions to the State.
Validate the CMRCA's grasp of the situation. By comparing what is understood to e
be happening to measurements of what is actually happening, the CMRCA can estimate the validity of his understanding of the events.
O Requirements of Dose Assessment LJ The best assessment of dose requires that the CMRCA and staff:
Be familiar with the available release rate and dose rate calculation models, e
including their limitations and manpwer requirements.
Understand the physical situation (e. g., release point).
e Know what the dose assessment will be used for, particularly if it is used for off-e site protective actions.
Comparino Dose Assessment ModelTo Field Team Data Validate and compare dose model results with those results obtained from field e
team data.
ADAM may be used to back calculate release rates based upon monitoring team e
location. Care should be used because this method is not exact.
ADAM is useful for integrating doses at certain locations. Comparing ADAM e
results to field team data validates estimates.
Reportino of Dose Assessments to CMRCA and DCERO l
Give highest field team and calculated data on hourly basis for site boundary,2,5, and 10 i /3 miles. The Radiological Work Center staff should immediately notify CMRCA as soon as l
V calculated or measured site boundary,2-mile,5-mile, and 10-mile dose rates exceed 5 mR/hr,1,000 mR/hr, or 5,000 mR/hr for the whole-body and/or thyroid dose rates exceed 25 mrem /hr,250 mrem /hr,5,000 mrem /hr, or 25,000 mrem /hr.
l l
CON! 4.02 Rev.
20 Date: March 15,1993 Page-8.C-1 of 1
ATTACHMENT 8.D CALL-OUT EXPANDED ORGANIZATION GUIDELINES g
Guidelines are provided as to the optimum organization for the expanded on-shift Radiological Consequence Assessment Team. The initial on-call group of one each CMRCA, FTDC, RAE, RWCC, and Meteorologist should be expanded through call-out by cach of the on-call persons to up to two more CMRCA trained, one more RWCC trained, two more RAE trained, two more FTDC trained, one more meteorologisc trained individuals, and one secretary. This would enable a two shift (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> each) approach to dealing with the emergency.
The expanded organization would function as follows:
A.
Main EOC Desk The on-call or the Designated CMRCA and one other CMRCA trained person and, as necessary, one RWCC trained person will occupy the desk in the main EOC. They will be the front line interface with the rest of the Corporate EOC,the site EOF, the State DEP, and NRC, answering all phones, etc.
B.
Annex Room The Annex Room staff should consist of up to two RWCCs, three FTDCs, two RAEs, two meteorologists, and one secretary.
The three FTDCs should develop the strategy and conduct the logistics for Field Team deployment. They should periodically report results to the lead CMRCA through the RWCC. The two RAEs should do the dose calculation and other assignments as called for by the CMRCA and/or identified in procedures. Results will be reported to the lead CMRCA through the RWCC. The two Meteoroloaists will follow their procedures and also assist the RWCC and FTDCs in providing advance meteorologicalinformation to develop field team strategy. The Secretary will operate the telecopier machines to transmit and receive all radiological, meteorological and other data as directed by the CMRCA.
l l
1 9
CONI 4.02 Rev.
20 Date: March 15,1993 Page: 8.D-1 of 1
ATTACHMENT 8.E DOSE CALCULATIONS - INPUT INFORMATION Name:
Date/ Time:
Calculation Type: What if/ Actual (Circle One)
Unit / Release Point:
Met. Data Elevation:
Rx Shutdown Time:
Release From:
to l
(Hr/ Min)
(Hr/ Min) j
(
Noble Gas Release Rate (Check One) i 1 Ci/sec j
l Gap (3% Core inventory)/1 hour
{
Melt (100% Core inventory)/1 hour
{
Calculation Based On Current Radiation Readings Other:
i l
lodine Release Rate Not Controlling - Assume 10-6 times NG release rate Calculation Based on CONI Procedure 4.03 l
i Mitigating Systems To Consider For lodine Releases MP1 MP2 MP3 O'
Containment Air Recirc X
Reactor Containment /Drywell 5 prays X
X X
X t
PAB/ Aux Building Filtration System X
X X
]
Enclosure Building Filtration X
Rx Building Standby Gas Treatment System X
Supplemental Leak Collection System (SLRCS)
X Torus Scrubbing X
X X
SGTR - Normal Partitioning X
X X
SGTR - Solid Secondary Side X
X X
Containment /Drywell Hold Up X
X X
X Rx Building Hold Up X
PAB/ Aux Building Hold Up and Plate Out X
X X
ESF Building Hold Up and Plate Out X
O Other (Specify)
X X
X X
CONI 4.02 Rev.
20 Date: March 15,1993 Page: 8.E-1 of 1
ATTACHMENT 8.F CY PLANT 5N.d N M M M
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20 Date: March 1993 4
4 Page: 8.F-1
ATTACHME
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20 Date: March 15,1993 Page: 8.G-1 of 1
ATTACHMENT 8.H MILLSTONE UNIT 2 N
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20 Date: March 15,1993 g
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AHACHMENT 8.J IMMINENT CORE DAMAGE-WHOLE BODY DOSE ASSESSMENT
- 1. Noble Gas Source Term Decay Reduction Factor
'CY 6.2 E8 Ci X
MP1 6.8 E8 Ci X
l MP2 9.1 E8 Ci g
l Fraction of Core inventory MP3 1.2 E9 Ci E
C (2) ost %uMown Reducdon Rilease to Env ronment l
(hrs.)
Factor l
0 1.0 l
Assumotions for Release From
.5
.6 l
Core 2
.5 100 %
CLAD
.03 4
.4
=
100 %
OVERHEAT
=
.50 12
}3 100 %
= 1.0 2
48 l 2. Projected Centerline Dose 72
.1 l
Ground Level W8 Dose Factors rem u /Ci Distance A
B C
D E
F 5/B (500m)4.4 E-6 4.7 E-6 1.0 E-5 2.6 E-5 3.9 E-5 7.8 E-5 2 mi 1.5 E-7 4.2 E-7 1.1 E-6 3.1 E-6 5.6 E-6 1.2 E-5 5 mi 5.8 E-9 6.1 E-8 1.7 E-7 8.1 E-7 1.6 E-6 3.3 E-6 g
10 mi 2.3 E-8 3.6 E-8 5.6 E-8 2.7 E-7 6.4 E-7 1.7 E-6
+
$ 33 Dose Distance Ci rem u /Ci Dose Equi alent m sec DCF Correction i
X 5/B (500m)
X
+
=
X 2 mi X
+
=
S mi X
X
+
=
10 mi X
+
X
=
4 (1) Projections are made for ground level releases Post Shutdown DCF (2) Release rate calculation for State of Connecticut (hrs.)
Correction O
1.0
.5
.88 1
.79 4
=
2
.70 4
.53 12
.20 Noble Gas Release Period NG Ci/sec 24
.10 Ci Seconds y
y CONI 4.02 Rev.
20 Date: March 15,1993 Page-8.J-1 of 1
ATTACHMENT 8.K PLUME PROFILE OFF CENTERLINE - ELEVATED RELEASE 57TE BOUNDAPY P11'MF PPDFIIT 2 M11I Pit'MF PROTI1F Deseles Release Elevated kettese
, Freeuen of Centertine Dose Freedon of Centertine Dose
.. t.
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.,7
. s (.
.g
.4 D
A A.
F c
s s.
as eo si no as es as s
se as ao es se Degrees From Plume Centerline Degrees From Plume Centerline Location DR centerline 0 0ff Centerline DR ce terl e center ne i
I SB (500m) 2 miles l
5 miles e
IV ID11e3 g
1 t
S Mfl.F PirWF PROTf1F 10 MRF PirWF PPOTTI.T rie.*ts c Fetease D--t'ee Pe!.eet Fraeuon of Centerline Do.e Freedon of Centerline Dose N)
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CONI 4.02 Rev.
20 Date: March 15,1993 Page: 8.K-1 of 1
ATTACHMENT 8.L PLUME PROFILE OFF CENTERLINE - GROUND RELEASE g
EfTT pol'NOAPY PirMF PROPitr 2 WTII Pit'WE PPOP!1F Grour.d Petre s*
Ground Petes**
Freetion of Centerline Dose Freetion of Centerline Dose
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so Degrees From Plume Centerline Degrees From Plume Centerline l
Location DR centerline o
Fraction of DR off Off Centerline DR centerline Centerline t
FB (500m)
O 2 miles 5 miles e
au faiJt m i
1 i
5 Mill P11'MT PPOPflE 10 MUT P11'MF PROTfil cre t c e p.g.a,.
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Fraction of Centerline Dose Fr.etion of Centerline Dose
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CONI 4.02 Rev.
20 Date: March 15,1993 Page: 8.L-1 of 1
i ATTACHMENT 8.M Q
WEATHER (METEOROLOGICAL) STATUS Connecticut Yankee Current Date:
Millstone Station Current Time:
1 l
Current site wind - wind speed mph: Data from foot level.
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The wind is expected to shift at:
hours.
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.cs 6 INSTRUCTIONS:
- 1. Draw a bold arrow completely through the CURRENT SITE WIND Compass Rose in the down wind direction.
/7
- 2. Draw a bold arrow completely through the FORECAST SITE WIND Compass Rose in the' V
forecasted down wind direction.
Release ugnature CONI 4.02 Rev.
20 Date: March 15,1993 Page: 8.M-1 of 1
O CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE CONI 4.08 i
ACCIDENT DOSE ASSESSMENT MODEL i
i o
THIS PROCEDURE CHANGE IS APPROVED, f
AND APPROPRIATE 10CFR50.54(q)
.r ACTIONS HAVE BEEN TAKEN.
p Lead Manager, Radiological Consequence Assessment REVISION 10 e,
I EFFECTIVE DATE March 15,1993 CONCURRENCE Corporate Nudear Emergency Plan Coordinator
CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE O
CONI 4.08 ACCIDENT DOSE ASSESSMENT MODEL 1.0 PURPOSE To estimate iodine concentrations and whole-body and thyroid doses in a ten mile radius around the Millstone and Haddam Neck Nuclear Power Stations for unplanned airborne releases. This procedure provides an acceptable method to calculate doses under emergency conditions. Since all possible emergency conditions cannot be anticipated by procedure, deviations from this procedure are allowed.
2.0 APPLICABILITY This procedure applies to airoorne releases of radionuclides from Millstone Nuclear Power Station or Haddam Neck Plant.
3.0 REFERENCES
3.1 CONI Procedure 4.03, " Estimating Post Accident Release Rates."
3.2 ADAM Model Documentation Package (Corporate EOC, Rad Consequence Work Center).
l 3.3 ADAM Program Operator Manual (Corporate EOC, Rad Consequence Work Center).
3.4 MPDOSE User's Manual (Corporate EOC, Rad Consequence Work Center) 3.5 CYDOSE User's Manual (Corporate EOC, Rad Consequence Work Center) l 3.6 Reference Binder with Copies of EPIP 1.5-7 and EPIP 4201 (Corporate EOC, Rad Consequence Work Center) 4.0 DEFINITIONS 4.1 PC - Personal Computer.
l 4.2 ADAf 4 - Accident Dose Assessment Model. The ADAM program is a gaussian l
puff modeMhat simulates the atmospheric transport and dispersion of plumes from multiple release points. Plumes are approximated by a series of discrete overlapping " puffs" that are transported according to the prevailing wind 5aeed, direction, and atmospheric stability. Concentration or dose at a point cepends on the number of puffs near that point and the total amount and distribution of radioactive materialin each puff.
O CONI 4.08 Rev.
10 Date: March 15,1993 Page: 1 of 4
Each release is governed by site and release specific parameters such as release height, exit velocity, etc. Plume rise and terrain effects are taken into account.
The source term can be either a specified mix of noble gases and iodmes or a calculated mix based upon time since reactor shutdown. Effects from noble
]
gas daughters, are included and decay in plume transit is considered.
i i
4.3 RMP - Radiation Monitoring Points. These are a set of predefined, site-specific monitoring locations. See Reference 3.2.
j 4.4 Definition of ADAM Polar Grid Points Figure 7.1 depicts the grid used by ADAM. The gridwork is set up as follows:
4.4.1 0 to 1 Mile Radius -the sectors are divided in half with one point at the midpoint at.5 and 1.0 mile radial distances. These points are 22.5 apart.
4.4.2 1 to 2.5 Mile Radius - the sectors are divided into three parts with points located 11.25a apart at 1.5, 2.0, and 2.5 mile radial distances.
The points on the output are listed counterclockwise. On ADAM l
output,looking out from the center of the grid, the rightmost point is listed first.
4.4.3 2.5 to 10.0 Mile Radius - the sectors are divided into four parts using three points located 7.5* apart in one-half mile radial increments out to 10 miles. These points are also output counterclockwise - with the rightmost point in the sector listed first, with the midpoint second, and the leftmost point last.
5.0 RESPONS!BILITIES 5.1 The Corporate Manager of Radiological Consequences Assessment (CMRCA) maintains training in this procedure.
5.2 The Radiological Assessment Engineer (RAE) and Radiological Work Center Coordinator (RWCC) maintains training in this procedure.
5.3 The CMRCA directs the completion of this procedure. The RAE (or another trained, qualified designee of the CMRCA) completes this procedure after initiation by the CMRCA. Both the CMRCA, RWCC, and the RAE are l
responsible for interpreting the results of this procedure.
5.4 The RAE collects the following information required to operate the ADAM model:
5.4.1 Time of reactor shutdown 5.4.2 Release point (s) 5.4.3 Release rate of noble gases and iodine 5.4.4 Individual radioisotopic percentages, when available 5.4.5 Meteorological conditions for the release period CONI 4.08 Rev.
10 Date: March 15,1993 Page: 2 of 4 1
NOTE: Attachment 8.E is provided as a reference to determine atmospheric O-stability class from a Differential Temperature (DT) measurement from the 196' level on the Connecticut Yankee tower and 142' and 374' level on the Millstone tower.
6.0 INSTRUCTIONS 6.1.A - 8.D (ADAM site-specific data sheet), should be completed by the CMRCA or his designee from information available from the plant and other involved groups. Special care should be taken to ensure that the units of the information requested are as indicated on these attachments. This information must be available to the staff member running the ADAM model.
6.2 Use Reference 3.3 to call up the program and execute the ADAM program in WINDOWS on a PC.
6.3 Care must be taken when entering in release rate data.
6.3.1 ADAM does not calculate an iodine release rate based on an input noble gas release rate. A method like the one in Reference 3.1 should be used to estimate the iodine release rate,if not specifically known.
6.3.2 Ensure corresponding release information is placed in correct release categories (e.g., noble gas and iodine release rates for the main stack are entered in the main stack position on the screen as denoted).
6.5 Output Options At the end of each time step, a number of options are available to view or print program output. ADAM stores all present and past output data. Each step is sequentially numbered. For hardcopy output, select the print option from the Results Viewer Window under File."
6.5.1 RMP File Selecting this option will let the user view the whole-body dose rate, integrated whole-body dose,1-131 DEQ concentration and thyroid dose at all Radiation Monitoring Points (RMP) and plume centerline points.
6.5.2 Grid File Selecting this option will let the user view the whole-body dose rate, integrated whole-body dose,1-131 DEQ concentration and thyroid dose at the polar grid receptor locations.
6.5.3 Graph File.
The high resolution color graphics include a complex geopolitical map showing town boundaries, rivers, lakes, and roads out to 10 miles overlaid with a detailed dose profile mosaic depicting dose ranges.
The graphic has zoom capability, special interest points like schools
/]
and hospitals, and the ability to obtain dose information anywhere (j
within the 10-mile EPZ. Requesting a print will give you a hardcopy color output. However, be aware that the print option can take as much as 5 minutes to print.
CON 14.08 Rev.
10 Date: March 15,1993 Page: 3 of 4
l 6.6 Determine the maximum site boundary,2,5, and 10-mile distant whole body dose rates and iodine concentrations and report any findings to the RWCC and CMRCA. To determine the appropriate site boundary distances corresponding to each sector for each site, see Attachment 8.F.
6.7 As an alternative to ADAM, the following dose assessment methods may be used.
6.7.1 The MPDOSE or CYDOSE program may be run using the TRS-80 computer. Use Reference 3.4 or 3.5 as appropriate.
6.7.2 Reference 3.6 may be used to manually perform the calculations done by computer in paragraph 6.7.1.
7.0 FIGURES Figure No.
Figure Title 7.1 ADAM Model Polar Grid 8.0 ATTACHMENTS Attachment No.
Attachment Title 8.A Connecticut Yankee ADAM Data Sheet 8.B Millstone Unit 1 ADAM Data Sheet 8.C Millstone Unit 2 AD AM Data Sheet 8.D Millstone Unit 3 ADAM Data Sheet 8.E Stability Class Determination 8.F Wind Directions and Distances To Nearest Land and Site Boundary O
CONI 4.08 Rev.
10 Date: March 15,1993 Page: 4 of 4
FIGURE 7.1 ADAM MODEL POLAR GRID I
ADAM lbdel Polar Grid i
N f
53 of 848 points 5.5 mile shown; =150 radiation sonitoring points and onsite points not shown because of non-unifomity l
q' 6
4 9,e l O 5.5 mile 5.5 mile 1
l ALAMs maintained l
within this grid 5.5 mile (purged if beyond) 4 l
CONI 4.08 Rev.
10 Date: March 15,1993 Page: 7.1 1 of 1
ATTACHMENT 8eA CONNECTICUTYANKEE ADAM DATA SHEET TIME STEP 1st Step ONLY Start:
(mm/dd)
(hh mm)
Reactor Shutdown:
End:
(hh mm)
(mm/dd)
(hh mm)
Release Point (s) / Rate (s)
(Ci/sec)
Isotopic (Y/N)
Isotopic %
1.
Stack NG I
2.
- 5. G. Safeties NG I
3.
Steam Dump NG 1
4.
Terry NG Turbine 1
5.
Containment /
NG Ground I
Ground Rooftop / Elevated MET DATA AT033 WD033 W5033 DT196 WD196 W5196
("C)
(From)
(m/sec)
('C)
(From)
(m/sec)
Conversion Formulae:
Mph = M/sec x 2.24 DT(oF) = DT(oC) x 1.8 CONI 4.08 Rev.
10 Completed by:
Date:
March 15,1993 Date:
Time:
Page 8.A-1 of 1 9
9 e
D ATTACH T 8.B
<O.
(V
'v' MILLSTONE UNIT 1 A M DATA SHEET TIME STEP 1st Step ONLY Start:
(mm/dd)
(hh mm)
Reactor Shutdown:
End:
(mm/dd)
(hh mm)
(hh mm)
Release Point (s)/ Rate (s)
(Ci/sec)
Isotopic (Y/N)
Isotopic %
1 Stack NG l
2.
Reactor Bldg /
NG Ground i
P Ground Rooftop Elevated MET DATA AT033 WD033 W5033 DT142 WD142 W5142 DT374 WD374 W5374
('C)
(From)
(m/sec)
(C)
(From)
(m/sec)
("C)
(From)
(m/sec)
Conversion Formulae:
Mph M/sec x 2.24
=
DT( F) = DT( C) x 1.8 CONI 4.08 Rev.
10 Completed by:
Date:
March 15,1993 Date:
Time:
Page 8.B-1 of 1
ATTACHMENT 8.C MILLSTONE UNIT 2 ADAM DATA SHEET TIME STEP 1st Step ONLY Start:
(mm/dd)
(hh mm)
Reactor Shutdown:
End:
(mm/dd)
(hh mm)
(hh mm)
R lease Point (s)/ Rate (s)
(Ci/sec)
Isotopic (Y/N)
Isotopic %
1.
Stack NG I
2.
- 5. G. Safeties NG I
3.
Steam Dump NG l
4.
MP2 Vent NG l
5.
Reactor Bldg /
NG Ground i
Ground Rooftop Elevated MET DATA AT033 WD033 W5033 DT142 WD142 W5142 DT374 WD374 W5374
('C)
(From)
(m/ set)
('C)
(From)
(m/ set)
('C)
(From)
(m/se()
Conversion Formulae:
Mph M/sec x 2.24
=
DT(oF) = DT(oC) x 1.8 CONI 4.08 Rev.
10 l
Completed by:
Date:
March 15,1993
O
^ Trac"eT8 o O
MILLSTONE UNIT 3 ADAM DATA SHEET TIME STEP 1st Step ONLY Start:
(mm/dd)
(hh mm)
Reactor Shutdown:
End:
(mm/dd)
(hh mm)
(hh mm)
Release Point (s)/ Rate (s)
(Ci/sec)
Isotopic (Y/N)
Isotopic %
1.
Stack NG I
2.
- 5. G. Safeties NG I
3.
Steam Dump NG I
4.
MP3 Vent NG I
5.
Aux. Feed NG Pump I
6.
Reactor Bldg /
NG Ground -
l Ground Rooftop Elevated MET DATA AT033 WD033 W5033 DT142 WD142 W5142 DT374 WD374 W5374
('C)
(From)
(m/sec)
('C)
(From)
(m/sec)
('C)
(From)
(m/sec)
Conversion Formulae:
Mph M/sec x 2.24
=
DT(oF) = DT( C) x 1.8 CONI 4.08 Rev.
10 Completed by:
Date:
March 15,1993 Date:
Time:
Page 8.D-1 of 1
i ATTACHMENT 8.E STABILITY CLASS DETERMINATION 1
Connecticut Yankee DT 196 Measurement Stability Class DT 5 -1.0 A
-1.0 < DT 5 -0.9 B
-0.9 < DT5
-0.8 C
-0.8 < DT5
-0.3 D
-0.3 < DT 5 0.7 E
0.7 < DT F
Millstone DT 142 DT 374 Measurement Stability Class Measurement Stability Class DT 5 -0.7 A
DT 5 -2.0 A
-0.7 < DT 5 -0.6 B
-2.0 < DT 5 -1.8 B
-0.6 < DT 5 -0.5 C
-1.8 < DT 5 -1.6 C
-0.5 < DT 5 -0.2 D
-1.6 < DT 5 -0.6 D
-0.2 < DT 5 0.5 E
-0.6 < DT 5 1.6 E
0.5 < DT F
1.6 < DT F
O CONI 4.08 Rev.
10 Date: March 15,1993 Page: 8.E-1 of 1
O O
i l
ATTACHMENT 8.F WIND DIRECTIONS AND DISTANCES TO NEAREST LAND AND SITE BOUNDARY l
CY Releases MP1, MP2 Ground & MP2 Mixed MP3 Grovrid & Mixed MP1 Stack W;nd Direction Downwind Downwind Nearest Site Nearest Site Nearest Site Nearest Site is From Direction Sector Nearest Land Boundary Nearest Land Boundary Nearest Land Boundary Nearestland Boundary 169' 191' 349* 11' A (N) 630 m 630 m 1,138 m 1,138 m 924 m 924 m 1,695 m 1,695 m 192'-213' 12'- 3 P 8 (NNE) 690 m 690 m 997 m 997 m 1,550 m 1,550 m 813 m 813 m 214'-236' 34'-56' C (NE) 710 m 710 m 620 m 620 m 841 m 841 m 4% m 4% m 237' 258' 57'-78' D (ENE) 1,240 m 1,240 m 1,070 m 620 m 602 m 602 m 1.101 m 4% m 259' 281' 79'-101' E (E) 1,970 m 1,510 m 1,600 m 620 m 1,300 m 602 m 1,410 m 4% m 282*-303' 102'-123' F (ESE)
- 1,970 m 1,370 m 1,900 m 620 m 1,690 m 602 m '
1,640 m 496 m -
304' 326' 124'-146' G (SE) 1,300 m 340 m.
31,700 m 620 m 33,000 m
' 602 m 31,700 m 496 m 32P34ti' 147'- 16F H (55E) 890 m 230 m
.12,390 m 620 m 22,200 m 631 m 12,390 m 496 m I
349' 11' 169'-191' J (5) 740 m 150 m 13,100 m 620 m 16,100 m 602 m 13,100 m 496 m 12'-33' 192' 213' K (55W) 700 m 120 m 14,500 m 620 m -
18,300 m 602 m 14,500 m 496 m 34'-56' 214' 23r L (SW) 580 m 120 m 3,430 m 620 m 3,380 m 602 m 3,660 m 496 m 57'- 7F 237' 25F M (WSW) 580 m 130 m 3,100 m 620 m 3,050 m 602 m 3,270 m 4% m 79*-101' 259'-281' N (W)
- 620 m 170 m 2,830 m 620 m 2,700 m 602 m 3,050 m 496 m 192' 123' 282'-303' P (WNW) 550 m 310 m 2,550 m 620 m 2,310 m 602 m 2,660 m 649 m -
124' 146' 304'- 32F Q (NW) 550 m 550 m 1,930 m 620 m 684 m 602 m 997 m 710 m 147' 16F 327'- 34r R. (NNW) 510 m 510 m 915 m 915 m 694 m 694 m 1,029 m 1,029 m NOTE:
For " Nearest Land
- sectors on riverside, the distante to the opposite side of the river is given.
NOTE:
Nearest Site Boundary is given as 620 m from the MP2 stack for water sectors (sectors D through Q).
NOTE:
Nearest Site Boundary is given as 602 m from the MP3 ventilation vent for water sectors (sectors D G and J-0).
NOTE:
Nearest Site Boundary is given as 496 m from the MP1 sta(k for water sectors (sectors D through N).
CONI 4 08 Rev.
10 Date: March 1,1993 -
Page: 8.F-1of1
. ~....
't e
O t
CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE i
CONI 4.10 ON-CALL RADIOLOGICAL ASSESSMENT STAFF TELEPHONE LIST t
A THIS PROCEDURE CHANGE IS APPROVED, 5/'
AND AP PR O P RI AT E 10 CF R 50.54(q) f ACTIONS HAVE BEEN TAKEN.
Lead Manager.Yadiological Consequence Assessment REVISION 20 EFFECTIVE DATE March 15,1993 CONCURRENCE Corporate Nucleai4mergency Plan Coordinator
CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE CONI 4.10 l
ON-CALL RADIOLOGICAL ASSESSMENT STAFF TELEPHONE LIST l
l l
1.0 PURPOSE i
This procedure provides convenient listings of personnel and telephone numbers.
It includes the Radiological Assessment staff, Meteorological Team and Environmental Team members, and other potentially useful numbers.
2.0 APPLICABILITY Radiological Assessmentstaff.
3.0 REFERENCES
None 4.0 DEFINITIONS None 5.0 RESPONSIBILITIES The Radiological Assessment staffis to be aware of this procedure.
6.0 INSTRUCTIONS The Manager of Radiological Consequence Assessment or designee will call out personnel using Attachments 8.A and 8.B.
7.0 FIGURES None 8.0 ATTACHMENTS Attachment No.
Attachment Title 8.A Radiological Assessment and Support Staff Phone Numbers 8.B Meteorological Team, Environmental Team, and Other Phone Numbers -
O CONI 4.10 Rev.
20 Date: March 15,1993 f~)no - Qr;{LD
f l
ATTACHMENT 8.A l
RADIOLOGICAL ASSESSMENT AND SUPPORT STAFF PHONE NUMBERS INDIVIDUAL
- WORK HOME R. C. Rodgers (CMRCA) 5655 666-1728 R. J. Schmidt (CMRCA) 3720 828-0803 l
l J. H. Argazzi 5983 828-5292 l
L. A. Bowen 3757 568-4948 l
R. A.Crandall (CMRCA) 5863 563-3359, W.J. Eakin (RWCC) 5246 267-0562 T. L. Drake (RAE) 5260 635-9869 D. M. Flick 5336 569-7432 C. A. Flory (RAE) 3592 344-1642 L. J. Landry (RWCC) 3593 633-5562 D. W. Marzilli (RWCC) 3005 346-5245 D.W. Miller (RAE) 5992 269-0596 E. J. Molloy (CMRCA) 3588 659-0300 D. G. Aloi (CMRCA) 3746 635-3940 M. E. Birch (FTDC) 3749 345-8298 C. Borea (FTDC) 3752 529-3858 VV. H. Buch 3502 CY 434-8763 T. J. Dembek 5494 MP 442-9676 G. J. Kelly (FTDC) 3747 646-3395/647-8636 W. T. McCance 5384 MP 464-6758 J. G. McHugh (RAE) 3058 447-9897 L. M. DeLuca (FTDC) 3753/609 CY 632-9264 T. J. Reyher (FTDC) 5785 349-0439 H.W. Siegrist (CMRCA) 3591 563-3468
- 1. L. Haas (RWCC) 3598 721-8164 A. 5. Klotz (FTDC) 3750 389-9811 T. E. Quattrochi (RAE) 3595 683-1450
- 5. M. Torf (R AE) 5814 285-0006 B. Kreiling 3756 429-7328 G. H. Baskette 6084/7050 646-1186 C. J. Scully (FTDC) 3640 746-9417 l
J. P. Carta 6082 347-7784 R. D. Hinkle (FTDC) 3697 529-9325 C. A. Diaz 6083 871-7107 J. J. Hawxhurst 5279 563-4712 K. D. Morgan 6080 347-9273 W. R. Koste (RWCC) 5838 659-2874
- CMRCA = Corporate Manager of RadiologicalConsequence Assessment RAE = Radiological Assessment Engineer FTDC = Field Team Data Coordinator RWCC = RadiologicalWork Center Coordinator CONI 4.10 Rev.
20 Date: March 15,1993 Page: _ 8.A-1 of 1
ATTACHMENT 8.B METEOROLOGICALTEAM, ENVIRONMENTALTEAM, AND OTHER PHONE NUMBERS O
WORK HOME Meteoroloaical/EDAN H. L. Chamberlain 4631 633-0344 H. L. Conway 4622 346-0244 J. W. Leavitt 4634 684-4925 R. T. Myers 4635 875-6573
- 5. L. Ragland 4643 443-4392 EDAN Room 4980,4976 Met Work Station 3972 667-4413 Weather Services Corporation:
617/275-8860 i
617/275-8861 f
617/275-8862 National Weather Service:
i Bradley Field 623-3888,2353 Bridgeport 378-2344 Production Operation Services Lab 1-638-3173 (Exempt)
G. Martel 8-304-3175 564-8239 R. Parker 8-304-3178 859-1541 D. Struthers 8-304-3177 563-2032 r
P. T. Staehty 8-304-3021 526-3423 R. C. Marchinkoski 8-304-3173 635-4547 (Non-Exempt)
R. D. Bedard 8-304-3181 569-6333 G. J. Buyce 8-304-3172 224-4219 N. A. Corsi 8-304-3171 529-6198 l
R. B. Laffins 8-304-3171 546-6971 l
A. W. Love 8-304-3174 564-8233 W. A. McDermott 8-304-3172 635-2104 R. E. Nejfelt 8-304-3171 739-9043 D. 5. Oliva 8-304-3174 267-4924 J. J. Quinn 8-304-3173 872-3324 R. Waggoner 8-304-3173 873-9957 J.T. Remkiewicz 8-304-3173 688-1891 P. H. Crete 8-304-3181 346-7931 i
CONI 4.10 Rev.
20 l-Date: March 15,1993 Page: 8.B-1 of 3-
ATTACHMENT 8.B METEOROLOGICALTEAM, ENVIRONMENTALTEAM, AND OTHER PHONE NUMBERS WORK HOME Hot Line - EOC Office to Middletown PLAR (Auto Ring - no extension to dial)
Berlin EOC Berlin EOC Phones 666-3397 extension 3805 Work Center Extension 667-2274,667-8026 5199 Environmental Laboratories a.Teledyne 201/664-7070 J. David Martin 201/391-1676 Hewitt Jeter 2019 67-3359 l
- b. State of Connecticut Governor's Office 566-4840 State DEP Office 566-5134 State OEM Office 566-2074/3180 State DEP-EOC 524-5359 Telecopier 247-0664 DEP Telecopier 566-6413
- c. Yankee Atomic Environmental Lab 508079-6711 Dave McCurdy X2504 Estella Laurenzo X2501 l
Mark Kralian X2525 Jane Reilly X2507 Millstone (Tie Line 8-711-)
447-1791 Control Room - Unit 1 4252,4260 Control Room - Unit 2 4352,4360 Control Room - Unit 3 4322,6200 Chem. Lab.
4220,4576 MP1 HP 4222 MP2 HP 4555 MP3 HP 4265 EOC Extension - RCA Manager 443-8549 X4525 CONI 4.10 Rev.
20 Date: March 15,1993 Page: 8.B-2 of 3
l l
r ATTACHMENT 8.B l
l(
)
METEOROLOGICALTEAM, ENVIRONMENTALTEAM, AND OTHER PHONE NUMBERS l
WORK HOME Conn. Yankee (Tie Line 8-713-3) 267-2556 Control Room 211,212 D.J. Ray 693 l
W. F. Nevelos 506 M. D. Quinn 583 Chem. Lab.
510,544
^
HP 503 EOC Extension - (Tie Line 8-714-3 Dose Assessment or Direct 344-3 EE)
X-205 or 227 RCA Manager X-225 DEP X-232 or X-233 Local Nuclear Facilities
[^')
For HP support from other nuclear power plants (i.e., Vermont Yankee) contact INPO U
(404)953-0904. They will contact other utilities.
Bureau of Radiological nealth HOT LINE (518)474-2886 Lawrence B Czech (518)474-2846 Empire State Plaza, Albany NY 12237 General Dynamics - Electric Boat 433-5960 ABB/CE 688-1911 U. S. Coast Guard (617) 223-8444 (Boston) 442-4471 (New London)
Convex 628-4781 Test Departmer.!
665-6000 John Kosciuk (Cellular Phones) 5077 235-5412 800-512-9955 (Beeper)
Environmental Lab - Boat Crew
(
) John Swenarton 4534 535-2902 Greg Decker 5261 739-9177 Don Landers 5062 739-8407 CONI 4.10 Rev.
20 Date: March 15,1993 Page-8.B-3 of 3
O CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CON!) PROCEDURE i
CONI 10.04 EXERCISE PREPARATION 1
l O
I' THIS PROCEDURE CHANGE IS APPROVED, AND APPROPRIATE 10 C FR 5 0.54(q)
ACTIONS HAVE BEEN TAKEN.
N'44 A
Supervisor, Emer'gency krepare$ ness i
REVISION 1
EFFECTIVE DATE March 15,1993 CONCURRENCE A
Corporate Nucleal Emergency Plan O
Coordinator.
I
I CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE CONI 10.04 EXERCISE PREPARATION i
1.0 PURPOSE This procedure provides a method to prepare full-participation and partial-participation graded exercises.
2.0 APPLICABILITY This procedure applies to the Emergency Preparedness Department, the scenario l
t Development Group, the Exercise Planning Committee, the Management Conceptual Review Group and the Logistics and SupportWorking Group.
3.0 REFERENCES
3.1 Millstone cnd Haddam Neck Site Emergency Plans (in particular, section 8.2 -
" Tests, Drills and Exercises")
i 3.2 10 CFR 50, Appendix E (NRC regulation on Utility Exercises).
j O'
44 CFR 350 (FEMA regulation on State / local Exercises).
3.3 3.4 Memo from E. J. Mroczka to NEO Supervisor dated October 24,1988, subject
" Level of Effort."
4.0 DEFINITIONS None 5.0 RESPONSIBILITIES 5.1 The Director of Emergency Preparedness or his designee is responsible for the l
implementation of this procedure and assessing the role of Exercise Coordination.
5.2 The Scenario Development Group is responsible for the development of i
exercise event sequence, all technical data, mock-ups, controller scripts and I
I I
messages, and the training of controllers.
1 5.3 The Exercise Planning Committee is responsible for resolving all logistics problems and establishing appropriate interfaces with local and state officials.
4 5.4 The Management Conceptual Review Group is responsible for reviewing the scenario sequence of events and associated technical data.
i f~%
i
(")
5.5 The Logistics and Support Working Group is responsible for preparing exercise facilities and for informing station and corporate personnel of exercise development status.
l CONI-10.04 Rev.
1 Date: March 15,1993 m
i
6.0 INSTRUCTIONS The Director of Emerg(ency Preparedness will establish the following Exercise 6.1 Deve,lopment Groups see Figure 7.1) and will assign specific personnel to each position:
i 6.1.1 Exercise Coordinator-The Director of Emergency Preparedness or his l
designee.
6.1.2 Scenario Development Group-Consists of a lead person from the Emergency Preparedness Department, a Station Emergency Preparedness Coordinator, SRO, NUSCO Radiological Engineering, Reactor Engineering, station HP, and other appropriate technical disciplines.
Purpose:
Develop the Sequence of Events and technical data for both the exercise and rehearsal.
6.1.3 Exercise Planning Committee-Consists of a station, local, corporate and state representative.
Purpose:
Ensure exercise logistics and establish appropriate governmental interfaces.
6.1.4 Management Conceptual Review Group-Consists of key Nuclear Engineering Department representatives and Station Management.
Purpose:
reviews the sequence of events of the scenario to ensure that they are technically defensible and logical.
6.1.5 Logistics and Support Working Group - Consists of the Station Emergency Preparedness Coordinator (EPC) and Assistant.
Purpose:
Ensure that facilities are prepared and station / corporate personnel are g.
informed.
6.2 With the aid of 10 CFR 50, Appendix E and the six-year Exercise Objectives Schedule, the Station Emergency Preparedness Coordinator and the Scenario Development Group Leader shall develop a list of " draft objectives" approximately five months before the tentative exercise / drill date. Include in the objectives any findings from the previous exercise as well as any NRC open items.
Have the objectives approved by the Director of Emergency l
Preparedness, Station Management, and the Exercise Planning Committee.
6.3 Concurrently with objectives development, the Scenario Development Group Leader shall prepare a list of personnel types (e.g., Senior Reactor Operator l
(SRO), Radiological Engineering, Plant Health Physics, Plant Chemistry, Plant Security, Plant Maintenance, Plant Engineering, Reactor Engineering, Generation Civil / Mechanical / Electrical Engineering, Environmental Engineering, and POSL) for scenario technical development. Also, prepare a suggested list of participants and controllers for the exercise and rehearsal.
6.4 The Scenario Development Group Leader shall call all appropriate discipline l
supervisors and request their assistance in accordance with Reference 3.4.
Once approval has been granted, proceed with the issuance of a memo to appropriate managers, formally requesting assistance. As an alternative, an annual commitment of response shall be obtained.
I CONI-10.04 Rev.
1 Date: March 15,1993 Page: 2 of 4 j
1 l
l
\\
p 6.5 The Exercise Coordinator shall:
)
6.5.1 Prepare a weekly meeting schedule approximately 120 to 150 days prior to the exercise date to ensure that the Scenario Development l
Group can meet to discuss exercise details. Minimize personnel time commitments by restricting attendance to the necessary disciplines.,
6.5.2 Conduct monthly Exercise Planning Committee meetings for all i
l exercises having off-site official involvement to discuss status and resolve problems. Initiate this approximately 120 days prior to the exercise date.
6.5.3 Conduct a Management Conceptual Review Group meeting following the preparation of the Sequence of Events and prior to detailed data development.
6.5.4 Develop and distribute a project schedule to all scenario developers. A generic exercise schedule is hsted for reference purposes in Figure 7.2.
Modify this schedule for the exercise under consideration. Enter dates for the exercise and rehearsal. The schedule program will determine all other dates.
6.5.5 Ensure that meeting notes are prepared and circulated confidentially following each scenario development meeting.
6.5.6 Have the State of Connecticut OEM issue a letter to each off-site community indicating that they will be contacted concerning scenario (m) development and requesting them to name a controller.
6.5.7 Ensure training of !ocal and state of'icials commences at least eight (8) weeks prior to the exercise.
6.5.8 Ensure that a meeting place is arranged for the local / state Post-Exercise Critique and that invitations are sent out.
6.5.9 Schedule the controllers / evaluators to perform a walk-through of the exercise prior to the exercise and the rehearsal. Send a letter to the off-site controllers inviting them to a walk-through of the controller's package about one (1) week prior to the exercise.
6.5.10 Schedule a critique following the exercise and assign the updates of the station, corporate, and state / local commitment follow lists to include all critique items with priority for resolution. This should include NRC/ FEMA critique items.
6.5.11 Prepare "Thank you" letters to be sent to all controllers (on site and off site) and to local Chief Executive Officers expressing appreciation for their assistance.
6.5.12 Ensure that the critique items are circulated to appropriate disciplines for implementing corrective actions.
CONI-10.04 Rev.
1 Date: March 15,1993 Page: 3 of 4 l
6.5.13 Place the master and one copy of the exercise controller manual along with the exercise project book in the appropriate Emergency Response filing system. The project book should include schedule information, project personnel listings, assignment handouts, completed assignments, meeting notes,Telecons and all written correspondence.
One complete copy of the exercise controller manual is to be sent to Nuclear Plant Records for permanent storage.
6.6 The Scenario Development Group shall follow the scenario preparation guidance listed in Attachment 8.A.
7.0 FIGURES Fiaure No.
Fioure Title 7.1 Exercise Development Group 7.2 Generic Exercise Schedule 8.0 ATTACHMENTS Attachment No.
Attachment Title 8.A Emergency Plan Exercise Scenario Guidelines O
l l
CONI-10.04 Rev.
1 Date: March 15,1993 Page: 4 of 4
u' o
O FIGURE.1 EXERCISE DEVELOPMENT GROUP Management Exercise Planning o Utility Managers Conceptual Review o ExerciseCoordinator Committee Group o Station Mgmt. Person y
l o KeyStateOfficial a.-----
_a o Key Local Community Official Review and approve Exercise sequence of events Coordinator I
I I
Scenario Logistics and Support Exercise Development Group Working Group Controllers / Evaluators Leader Organization o lead Emergency Preparedness Coordinator - Station o Lead Emergency Preparedness Coordinator - Technical o Exercise Coordinator o As Assigned o. Senior Reactor Operator o Station Emergency o RadiologicalEngineer Preparedness Coordinator (s) o Station Health Physicist o Thermal Hydraulic Engineer (PRA) o Training Coordinator (RO/5RO) o Civil Engineer (Generation) o Mech. Engineer (Generation) o Electrical Engineer (Generation) o PublicInformationOfficer o SecurityOfficer -
o Plant Maintenance o PlantChemistry o Meteorologist CONI 10.04 Rev.
1
- Date:
March 15,1993 Page:
7.1-1 of 1
- _. _ _ -. ~
~m-._.....__.-m.._m.
s _. ~. _ -..
m._ _ ____ m
.m.
-.-m.
FIGURE 7.2 GENERIC EXERCISE SCHEDULE seey Asi Ast Aug Sep Det is.e ' Status 20 29 3 to IT 24 1 a 15 22 29 5 12 19 26 3 9 16 23 30 F 14 21 28 Project Stort Ce Acc ire Devotepment Teen 944 a
Canytete feed pte DGA, T4 BC Developebjectives MS, Ufft C Develop scenerle Dev Teen Digittee leape TO E
Dewetop Refuserest CE. dea.T* 8
.e Objectiveo Approved 944 C
. =
Dettver 10Dd Pts 78 C
.a 100 d Pts Sue Dete it e.
Scenerle Approved DGA em Complete 65d Pts C3.DGA.fo DC 8'""
Dettver 65d Pectase Dea, te et Devoley St/in Scenerles SJC, IES DC 65d Ptg Due Date DGA, it Beous Catner twente femame IEE9.tJII.e 4 Identify Centrollere vive. De4 RC Devotep Print Isotria DGA C
e.
Recolve let Ceemente DG4 pC Bevloe to genroset Dev Toen C 8"""
Print Cettete 8eftgemrusste CB DC amme Print Cettete Es genresate it, CS SC
.e Dettver Beli sternate CS C
8 Conduct Regieerset Driefe C
e.
Consheet seheerset Dev foam e
Deliver En seenuele TE, CB C
8 Pleyere Orlef 8
Cerutset Onette Drlef DEA, EJfl~ pp 8
Conduct Offelte Drlof IEE8 EJII Cerukset FEst4 Drief IEEB, DG4 R 8
Censhset est Drlof dea, WT88 R 8
Cerukset Esercise Dev foam C Eserclee Claessut
. CS,asts,te aC
.e Project Complete C
t D Dano 8'ee gent
_ glect time ("E--), or CONI 10.04 Rev.
1 Date:
March 15,1993 Page:
7.2-1 of 1
ATTACHMENT 8.A EMERGENCY PLAN EXERCISE SCEN ARIO GUIDELINES i
1.
Allow adequate time between changes in emergency classification to allow state and locals to implement and demonstrate their emergenc,y plan requirements, such as public notification, protective action decision makmg, implementation of protective actions, etc. The minimum time between changes in emergency classification should be about sixty to seventy-five minutes. If we intend to have a scenario that moves i
faster, that should be on an infrequent basis and the scenario should be advertised as a fast-moving stenario (realism in meteorology can be included in these cases).
2.
The number of arbitrary unrelated failures of station equipment should be limited to avoid mindsets or frustration on the part of operators and emergency responders.
Such failures result in very low probability events that stretch credibility. Hence, these unrelated failures should be separated in time by about 20 minutes, and this provides reasonable challenge to allow for information flow, less confusion, and the OSC/TSC to demonstrate their functions.
3.
The mindset that every exercise should result in a General Emergency with evacuation should be avoided. For exercises other than full-participation, take more probable events with Site-Area Emergency as the highest classification. Discuss alternatives to full-participation exercises with the NRC for similar realistic scenarios that end at GENERAL EMERGENCY Bravo.
4.
The initiation of evacuation or take shelter protective actions in the scenario should occur for off-site radiation doses that are at the more appropriate EPA guidelines, i.e.,
O evacuation should not occur until the five rem whole body dose is projected or is occurring at the site boundary.
5.
Scenarios that result in exceeding the 10-mile EPZ planning basis should be avoided; i.e., no plume protective actions (evacuation, take shelter) beyond the 10-mile EPZ.
6.
Controller intervention to delay the start of equipment, closure / opening of valves, etc. should be realistic; i.e., if it would take 15 minutes to close a valve then do not exceed this time. If you fail meters / breakers to close valve then repair times should be realistic.
7.
Discipline staff assigned to serve on the Scenario Development Group should have explicit instructions to have their Supervisor / Manager review and sign-off their input to ensure quality control.
8.
Confidentiality of scenario development and processing of documents for NRC/ FEMA submittal should be stressed (e.g., Nuclear Licensing staff review processing and fielding NRC questions should disqualify them from participation). Have Nuclear Licensing staff designated in advance to handle material.
9.
Rapid shifts in wind direction are not recommended for full-participation exercises as routine conditions. If rapid changes in meteorology are intended, advertise that this is what will occur in exercises (see # 1 above).
- 10. Ensure that a state individualis involved in the scenario preparation and reviews it for compatibility with state emergency response capabilities and objectives.
O CONI 10.04 Rev.
1 Date: March 15,1993 Ph.8 A-1 Ef 1
i CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE f
CONI 10.05 MANAGEMENT OF DRILL AND EXERCISE CRITIQUE ITEMS O
THIS PROCEDURE CHANGE IS APPROVED,
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AND APPROPRIATE 10CFR50.54(q) p/
j' ACTIONS HAVE BEEN TAKEN.
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Supervisor, Emeig'ency d(epared/ ness
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REVISION 1
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4 EFFECTIVE DATE March 15,1993 CONCURRENCE O'-
Corporate Nucigar Emergency Plan Coordinator
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CORPORATE ORGANIZATION FOR NUCLEAR INCIDENTS (CONI) PROCEDURE Q
CONI 10.05 MANAGEMENT OF DRILL AND EXERCISE CRITIQUE ITEMS j
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1.0 PURPOSE i
To ensure that annual Emergency Plan drill and exercise critique items are resolved j
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in a timely fashion.
i' 2.0 APPLICABILITY This procedure applies to the Emergency Preparedness Department.
3.0 REFERENCES
3.1 Millstone and Haddam Neck Site Emergency Plans.
l 3.2 NUREG 0654/ FEMA-REP-1, Rev.1, " Criteria for Preparation and Evaluation of i
Radiological Emergency Response Plans and Preparedness in Support of l
Nuclear Power Plants.
j 3.3 INPO Emergency Preparedness Drill and Exercise Manual /INPO 88-019.
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f 4.0 DEFINITIONS None 5.0 RESPONSIBILITIES i
i' 5.1 It is the responsibility of the Lead Station Emergency Preparedness Coordinator (EPC) to identify and assemble all on-site drill and exercise critique items for review and prepare a Commitment Follow List.
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5.2 It is the responsibility of the Supervisor of Emergency Preparedness - Off-Site l
Programs, to assemble a Commitment Follow List for state and local town i
crmque items.
t 5.3 it is the responsibility of the Director of Emergency Preparedness to advise the appropriate levels of management of their need to address problems and commitments within their area of responsibility.
6.0 INSTRUCTIONS 6.1 After each Emergency Plan drill or exercise critique, the Lead Station EPC and i
the Supervisor of Emergency Preparedness - Off-Site Programs will list critique comments. -They will then review them to determine their appropriate resolution at a separate meeting with the Director of Emergency O
Preparedness and the appropriate level of management (e.g., Station j
Directors, Manager of General Nuclear Training, etc.).
CONI 10.05 Rev.
1 Date: March 15,1993 Page: 1 of 2
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The State and local town list will be reviewed with the State Office of i
Emergency Management (OEM).
6.2 At these meetings, due dates will be assigned for each approved commitment based upon its priority and the resources necessary to accomplish the cited action. A person will be assigned to accomplish each commitment follow item.
6.3 Commitment Follow Lists (CFL) will be generated by the Supervisor of Emergency Preparedness - Off-Site Programs and the Lead On-Site EPC, who will track each commitment's progress and ensure that the appropriate discipline assistance is obtained to meet the due dates. The CFL Form (Figure 7.1) may deviate in layout to allow for computerization.
i 6.4 The Supervisor of Emergency Preparedness - Off-Site Programs and the Lead On-Site EPC will update the Commitment Follow Lists (one for each site, corporate, and state / local) as needed; but, at least twice per year.
I 7.0 FIGURES l
Fiaure No.
Fiaure Title 7.1 Post Drill / Exercise Commitment Follow List 8.0 ATTACHMENTS None 9
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CONI 10.05 Rev.
1 Date: March 15,1993 Page: 2of2
O FIGUREp.1 O
l POST DRILUEXERCISE COMMITMENT FOLLOW LIST CFCODE = ResponsibleIndividual(s)
CF #
Description CF Code Due Date Action Complete
Response
CONI 10.05 Rev.
1 Date:
March 15,1993 Paga:
7.1-1 of 1
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