ML030080277
| ML030080277 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/30/2002 |
| From: | Forbes J Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML030080277 (175) | |
Text
Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC committed to Nuclear Excellence December 30, 2002 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 10 CFR 50, Appendix E Section V MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Emergency Plan Implementing Procedures Furnished with this letter is a revision to the Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures. The following procedures are revised:
Procedure A.2-102 A.2-204 A.2-21 0 A.2-213 A.2-501 A.2-504 A.2-803 A.2-807 A.2-809 A.2-811 A.2-812 Procedure Title Notification of Unusual Event (NUE)
Off-Site Protective Action Recommendations Engineering Support in the TSC Responsibilities of the Emergency Director Communications During an Emergency Emergency Communicator Duties in the TSC and OSC Emergency Communications at the EOF Off-Site Dose Assessment and Protective Action Recommendations EOF Security Event Termination or Recovery in the EOF Off-Site Agency Liaison at the EOF Revision 17 15 7
9 14 3
5 8
3 3
3 Please post changes in your copy of the Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures. Superseded procedures should be destroyed. These revisions do not reduce the effectiveness of the Monticello Nuclear Generating Plant Emergency Plan.
Please contact Paul Hartmann, Senior Licensing Analyst, at 763-271-5172 if you require further information.
Jeffrey S. Forbes Site Vice President Monticello Nuclear Generating Plant c:
Regional Administrator - Ill, NRC (w/ two copies of enclosure)
NRR Project Manager, NRC (w/o enclosure)
Resident Inspector, NRC (w/o enclosure, EPIP dist. by Monticello Document Control)
Minnesota Dept. of Commerce (w/o enclosure) 2807 West County Road 75 e Monticello, Minnesota 55362-9637 Telephone. 763-295-5151
- Fax: 763-295-1454 A'O-L4 5
MONTICELLO NUCLEAR GENERATING PLANT A.2-102 TITLE:
NOTIFICATION OF UNUSUAL EVENT Revision 17 (NUE)
Page 1 of 9 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION P) 1.0 PU R PO SE........................................................
2.0 APPLICABILITY...................................................
3.0 ORGANIZATION AND RESPONSIBILITIES...........................
4.0 D ISC USSIO N......................................................
5.0 PRECAUTIONS....................................................
6.0 INSTRUCTIO NS...................................................
6.1 Im m ediate Actions...........................................
6.2 Continuing Actions...........................................
6.3 Emergency Class Escalation or Termination.....................
7.0 FIG U R ES.........................................................
7.1 Forms Utilized in this Procedure................................
AGE 2
2 2
3 3
3 3
7 8
9 9
Prepared By:
Reviewed BY:
I OC Review Req'd: Yes OCMeeting Number:
a ate: /&/s o.
Approved By:
Date./,
40
ýi-hs revision incorporates Volume F Memos:
I,,4 L
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated: *c-6 / O-331 RespSupv:
EP lAssoc Ref. A.2 J'SR" N I Freq" 1 1,rs I JARMS" A.2-102 FDoc Type: 1060 1Admin Initials:
Date: -
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MONTICELLO NUCLEAR GENERATING PLANT A.2-102 TITLE:
NOTIFICATION OF UNUSUAL EVENT Revision 17 (NUE)
Page 2 of 9 1.0 PURPOSE The purpose of this procedure is to provide instructions and guidance to the Duty Shift Manager (Interim Emergency Director) for implementation of the Monticello Emergency Plan during an Unusual Event.
Sections of this procedure which satisfy commitments M76060A, M82025A, M82026A, M82027A, and M82028A are marked with a $.
2.0 APPLICABILITY 2.1 An Unusual Event has been declared at the Monticello Nuclear Generating Plant.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Duty Shift Manager (Interim Emergency Director) is responsible for:
3.1.1 Implementation of this procedure.
3.1.2 Declaration of the emergency classification.
3.1.3 Implementation of the Emergency Plan and applicable EPIPs.
3.1.4 Serve as the Technical Advisor to the Control Room Supervisor and Control Room staff by maintaining a broad perspective of the event and providing technical/operational advice.
3.1.5 Determining the necessity for on-site protective actions, such as local, plant, or site evacuations.
3.1.6 Authorization of emergency radiation exposures.
3.1.7 Authorization to waive access security requirements for off-site emergency response personnel and vehicles.
3.2 The Duty Control Room Supervisor is responsible for:
3.2.1 Implementation of this procedure (in the absence of the Duty Shift Manager).
3.2.2 Direction and coordination of Operations group activities.
3.3 The Shift Emergency Communicator(s) is responsible for:
3.3.1 Conduct of emergency notifications, including 15 minute State/County and NRC notifications under the direction of the Shift Manager.
3.3.2 Conduct of notifications in accordance with 4 AWI-04.08.01 (EVENT NOTIFICATIONS).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-102 TITLE:
NOTIFICATION OF UNUSUAL EVENT Revision 17 (NUE)
Page 3 of 9 3.3.3 Coordination of off-site communications during the event under the direction of the Emergency Director.
4.0 DISCUSSION This procedure provides instructions for the coordination of emergency response activities under the direction of the Duty Shift Manager (Interim Emergency Director).
The procedure consists of three sections. Section 6.1 provides instructions for the immediate actions required for the declaration of an Unusual Event. Section 6.2 provides instructions for continuing or followup actions until the emergency event escalates or is terminated. Section 6.3 provides instructions for the escalation of the emergency classification or termination of the Unusual Event.
5.0 PRECAUTIONS 5.1 Continued surveillance and assessment of plant conditions throughout the event are necessary to ensure that the emergency classification is appropriately revised as conditions change.
5.2 All inquiries from the news media and/or general public should be directed to the Xcel Energy Communications Department. Emergency response organization personnel should not release information to the media or general public without prior approval of the Chief Nuclear Officer or designee.
5.3 In the case of an event that rapidly escalates then de-escalates in emergency classification (i.e. plant conditions rapidly degrade then recover) or, the event is initiated at a higher emergency class then rapidly de-escalates, the initial emergency notifications SHALL indicate the current emergency classification and the highest emergency classification reached during the course of the event.
5.4 Search and rescue of missing persons should take precedence over repair or corrective actions unless such actions are necessary to effect rescue or protect the immediate health and safety of the general public.
6.0 INSTRUCTIONS 6.1 Immediate Actions
"...
AfIOeN Notification of the State and Counties must be completed within 15 minutes of the declaration of an Notification of Unusual Event (NUE).
6.1.1 Page the Duty Shift Emergency Communicator (SEC) to the Control Room.
NOTE: The SEC should provide the Shift Manager with a copy of Form 5790-102-01 (NOTIFICATION OF UNUSUAL EVENT CHECKLIST).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-102 TITLE:
NOTIFICATION OF UNUSUAL EVENT Revision 17 (NUE)
Page 4 of 9 6.1.2 Initiate Form 5790-102-01 for the event.
6.1.3 Provide the SEC with the following information for completion of Form 5790-102-02 (MONTICELLO EMERGENCY NOTIFICATION REPORT FORM):
A.
The time that the NUE was declared.
B.
If the event involves a radioactive release.
C.
The Guideline number used to classify the NUE.
D.
Review and approve the completed Form 5790-102-02.
$ 6.1.4 Direct the SEC to proceed with emergency notification in accordance with 5790-102-04 (EMERGENCY CALL LIST - NUE).
6.1.5 If the emergency classification has security implications (e.g. Declared based on Guideline 17), ensure that the operator actions specified in C.4-L (RESPONSE TO SECURITY THREATS) are completed and exit this procedure and complete the actions specified in A.2-1 10 (RESPONSE TO A SECURITY THREAT).
6.1.6 Make (or direct) a public address (PA) announcement of the NUE declaration. The announcement should include a brief description of the situation, the reason for declaration and specific instructions for plant/site personnel. The announcement should be made to all site areas (using page access 305) and repeated a minimum of 3 times.
An example announcement is as follows:
"ATTENTION SITE PERSONNEL, AN UNUSUAL EVENT HAS BEEN DECLARED. THE UNUSUAL EVENT WAS DECLARED AS A RESULT OF (state reason for declaration). PERSONNEL SHOULD CONTINUE NORMAL DUTIES UNLESS OTHERWISE INSTRUCTED."
6.1.7 If the event involves a fire, medical emergency or missing/trapped personnel, consider activation of the Fire Brigade in accordance with the following instructions:
A.
A.3 Operations Manual, Fire Fighting Procedures B.
A.5-100 (ON-SITE MEDICAL EMERGENCIES)
C.
A.2-303 (SEARCH AND RESCUE)
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MONTICELLO NUCLEAR GENERATING PLANT A.2-102 TITLE:
NOTIFICATION OF UNUSUAL EVENT Revision 17 (NUE)
Page 5 of 9 6.1.8 If the event involves conventional (fire, toxic gas, etc.) and/or radiological hazards consider conducting a local evacuation of affected areas (or a Plant evacuation, if necessary) in accordance with EPIP A.2-301 (EMERGENCY EVACUATION). If an evacuation is conducted:
A.
Ensure personnel accountability is performed in accordance with the applicable section of EPIP A.2-205 (PERSONNEL ACCOUNTABILITY).
B.
Direct radiation protection and/or security to establish positive access controls for the evacuated area(s).
6.1.9 If the event includes radiological or chemistry implications, direct the Duty Shift Rad Prot Tech and/or Chemistry Tech to perform the necessary surveys and/or sampling.
6.1.10 If the event could involve radiological exposures (to response personnel) in excess of MNGP administrative or Federal limits, consider authorization of emergency exposures in accordance with EPIP A.2-401 (EMERGENCY EXPOSURE CONTROL).
6.1.11 Assess plant conditions and activities and consider implementation of STRICT PLANT STATUS CONTROLS. If implemented, make (or direct) a public address (PA) announcement regarding the initiation of Strict Plant Status Controls.
6.1.12 If local off-site emergency support (e.g. ambulance, Fire Department, LLEA, etc.) is required:
$ A.
Ensure the applicable agencies are notified (either by the Control Room staff or SEC).
B.
Consider suspending certain access-safeguard requirements (e.g. vehicle search, visitor badging, etc.) for emergency vehicles and personnel entering the Protected Area.
C.
As necessary, direct Security supervision (Duty Lieutenant) to suspend the access requirements for off-site vehicles/personnel.
~KjCAUTION K.i Notification of the NRC must be completed immediately after notification of the State, Counties and the MNGP ERO and no later than 1-hour after the declaration of the NUE.
$ 6.1.13 As requested by the SEC, assist with the notification of the NRC as follows:
A.
Provide operational and technical information for the completion of Form 3195 (EVENT NOTIFICATION WORKSHEET).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-102 TITLE:
NOTIFICATION OF UNUSUAL EVENT Revision 17 (NUE)
Page 6 of 9
$ 6.1.14
$ 6.1.15
$ 6.1.16 B.
Review the completed Form 3195, sign and date in the space provided.
C.
Direct the SEC to complete NRC notifications in accordance with Part C of Form 5790-102-04.
Upon completion of all initial emergency notifications direct the SEC to initiate and transmit Form 5790-102-03 (EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE) to the State of Minnesota and:
A.
Review, date and sign each completed Follow-up Message prior to transmittal.
B.
Transmit a Follow-up Message at least every 30 minutes or at a frequency specified by the State (Duty Officer or DEM).
Upon completion of the emergency notifications, direct the SEC to review the requirements for Event Notifications in accordance with 4 AWI-04.08.01 and:
A.
Determine if any individuals or organizations listed should be notified of the NUE (if not notified during the emergency notifications).
B.
Initiate Form 3389 (EVENT NOTIFICATIONS).
C.
Notify the identified organizations and complete Form 3389 indicating which organizations were notified and when.
Review Form 5790-102-06 (SECONDARY NOTIFICATION LIST) to assist in determining if any additional organizations should be notified to assist in the emergency response. If desired, direct the SEC to notify the identified organizations.
6.1.17 If a designated Emergency Director (e.g. Plant Manager or other ED) responds to the event and turnover of ED responsibilities (to the designated ED) is desired, formally turn over responsibilities as follows:
A.
Provide a status update to the relieving ED on:
- 1. Current plant conditions and implementations of abnormal and/or emergency operating procedures.
- 2.
A summary of the event and the status of emergency response actions underway or planned, including on-site protective actions.
- 3.
The current emergency classification and the status of Emergency Plan implementation.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-102 TITLE:
NOTIFICATION OF UNUSUAL EVENT Revision 17 (NUE)
Page 7 of 9 B.
Note the transfer of ED responsibilities in the Control Room and/or Control Room Supervisors Log.
6.2 Continuing Actions 6.2.1 Manage the operational and overall emergency response activities on-site until relieved by another qualified Emergency Director or the event is terminated.
6.2.2 Assume the responsibilities of Shift Technical Advisor (STA) and:
A.
Maintain a broad, overall operational perspective and provide technical/operational advice to the Control Room Supervisor and Operations staff throughout the event.
B.
Evaluate available data and information relative to the event to determine the actual and potential implications of the event from an operational perspective.
C.
If problems arise, assess the operational aspects of the problems and provide input to the Control Room staff on possible solutions or mitigating efforts.
D.
Maintain awareness of plant conditions and attempt to anticipate or predict transients. Advise the Control Room Supervisor and Control Room staff on methods to avoid or mitigate adverse transients.
E.
Assist the Control Room Supervisor and Control Room staff with prioritization of operational and emergency response activities.
6.2.3 Continuously remain aware of plant conditions and critical parameters.
Periodically, and if significant changes occur, compare plant conditions/parameters with the Emergency Action Levels (EALs) contained in EPIP A.2-101 (CLASSIFICATION OF EMERGENCIES).
6.2.4 Assess Operations Department staffing in the Control Room and augment as necessary.
$ 6.2.5 Throughout the event or until relieved by a designated Emergency Director, review, sign, and date completed Emergency Notification Follow-up Messages and direct the SEC to transmit the forms to the State of Minnesota.
6.2.6 Continuously monitor plant conditions throughout the event to determine if and when the NUE should be terminated or the emergency reclassified (to a higher emergency classification). Refer to Section 6.3 for event termination or reclassification instructions.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-102 TITLE:
NOTIFICATION OF UNUSUAL EVENT Revision 17 (NUE)
Page 8 of 9 6.3 Emergency Class Escalation or Termination 6.3.1 If the NUE is being terminated:
A.
Refer to the applicable section of EPIP A.2-602 (EVENT TERMINATION OR RECOVERY).
B.
Direct the SEC to complete a new Emergency Notification Report Form (Form 5790-102-02) and a new NUE Call-list (Form 5790-102-04) and:
- 1. Review and sign the completed forms prior to transmittal off-site.
$ 2.
Ensure all organizations notified during the initial emergency notifications (when the NUE was declared) are notified of the event termination.
- 3.
Direct the SEC to make the termination notifications and report when all notifications are complete.
C.
Direct the SEC to collect and assemble all forms completed during the event and forward to the emergency preparedness group for review and filing.
D.
Make (or direct) a public address (PA) announcement of the NUE termination. An example announcement is as follows:
"ATTENTION SITE PERSONNEL. THE UNUSUAL EVENT IS TERMINATED. RESUME NORMAL DUTIES."
E.
Complete Form 5790-102-01 and forward to the SEC for inclusion with other emergency records.
6.3.2 If reclassification of the event is necessary:
A.
Reclassify the event in accordance with EPIP A.2-1 01 (CLASSIFICATION OF EMERGENCIES).
B.
Implement the applicable procedure for the new emergency classification:
- 1. A.2-103 (ALERT)
- 2.
A.2-104 (SITE AREA EMERGENCY)
- 3.
A.2-105 (GENERAL EMERGENCY)
C.
Complete Form 5790-102-01 and retain as emergency records.
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MONTICELLO NUCLEAR GENERATING PLANT TITLE:
NOTIFICATION OF UNUSUAL EVENT I
(NUE)
A.2-102 Revision 17 Page 9 of 9 I
7.0 FIGURES 5790-102-01 5790-102-03 5790-102-06 FIGURE 7.1 Forms Utilized in this Procedure NOTIFICATION OF UNUSUAL EVENT (NUE) CHECKLIST EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE SECONDARY NOTIFICATION LIST 1.
- 2.
3.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION Revision 15 RECOMMENDATIONS Page 1 of 22 EMERGENCY PLAN IMPLEMENTING PROCEDURE -TABLE OF CONTENTS CTION SE Prepared By: 4.,1 n,-
Reviewed By:
OC Review Req'd:'YES OC Meeting Number: ý23 LI S el:-.'/a ie Approved By:
Date:/-,4§,*
-..FOR ADMNISTRATE UI E ONLY Ths-revision incorporates Volume F Memos:
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:
-Q -
a 3 L r
RespSum:
EP J
AssocyRef A2 19,SR" N IaFrel-1 ly JARMS:
A 2-204
_ __TD~oc Type. 1060 Ad1 ntas Date:l--&
I/mab 1.0 PU R PO SE........................................................
2.0 APPLICABILITY...................................................
3.0 ORGANIZATION AND RESPONSIBILITIES...........................
4.0 D ISC U SSIO N......................................................
5.0 PRECAUTIO NS....................................................
6.0 INSTRUCTIO NS...................................................
6.1 Initial PARs for General Emergency Classification................
6.2 PARS for Sherco Plant........................................
6.3 Off-site PARs Based on Projected Doses........................
6.4 Protective Action Recommendation for Liquid Releases...........
7.0 FIG U R ES.........................................................
7.1 Definitions Related to Protective Actions Recommendations.......
7.2 Discussion of Protective Action Recommendation................
7.3 Protective Action Guidelines (PAGs)............................
7.4 Emergency Worker Exposure Limits............................
7.5 Transport Time and Monthly Average Flowrates..................
7.6 Liquid Release Protective Action Criteria........................
7.7 Forms Utilized in Procedure...................................
PAGE 2
2 2
2 2
4 4
5 6
8 9
9 12 16 18 19 21 22
MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION
- 3evision 15 RECOMMENDATIONS Page 2 of 22 1.0 PURPOSE The purpose of this procedure is to provide instructions and guidelines to the Emergency Director (ED) and Radiological Emergency Coordinator (REC) for the formulation of off-site protective action recommendations for the general public during the early phase of an emergency.
2.0 APPLICABILITY 2.1 An emergency condition corresponding to an Unusual Event classification or higher has been declared at the MNGP, and 2.2 A release of radioactive material has occurred, is occurring, or is likely to occur.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Director (Duty Shift Manager or designated Emergency Director) is responsible for:
3.1.1 Implementation of this procedure if the REC position is not staffed.
3.1.2 Directing off-site communications with State and Local authorities and Federal agencies (before turnover to the EOF).
3.1.3 Approving off-site Protective Action Recommendations (PARs) to State and/or County authorities (prior to turnover of this responsibility to the Emergency Manager).
3.2 The Radiological Emergency Coordinator is responsible for:
3.2.1 Implementation of this procedure.
3.2.2 Making off-site Protective Action Recommendations (PARs) to State and/or County authorities (prior to turnover of this responsibility to the Radiation Protection Support Supervisor).
4.0 DISCUSSION 4.1 For definitions related to PARs, see Figure 7.1 4.2 For general discussion of PAR, see Figure 7.2 5.0 PRECAUTIONS 5.1 Declaration of a General Emergency requires immediate Protective Action Recommendations (PARs) to off-site agencies. Under these circumstances, NO dose projections are required for formulating the initial offsite protective action recommendation.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION 3evision 15 RECOMMENDATIONS Page 3 of 22 5.2 Implementation of protective actions for off-site areas is the responsibility of the State of Minnesota. If it is determined by the Emergency Director that immediate protective actions are required, and the State EOC is not activated, the recommendation should be made directly to the local authorities (i.e.,
Wright and Sherburne Counties). Upon activation of the State EOC all off-site protective action recommendations should be made to the State.
5.3 The protective actions outlined in this procedure are limited to actions for minimizing the exposure of the public to external and internal radiation exposure from plume passage, inhalation of the radioactive plume and from internal exposure from drinking water during the early phase of an emergency.
Other protective actions for minimizing public exposure via the ingestion pathway will be determined and implemented by the State.
5.4 The transmission of Off-site Protective action Recommendations to the State EOC (State Duty Officer and Counties if the State EOC is not activated)
SHALL be completed within 15 minutes of the PAR authorization.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION lIevision 15 RECOMMENDATIONS Page 4 of 22 6.0 INSTRUCTIONS No dose projections are required when making initial PAR during GENERAL EMERGENCY CONDITIONS.
6.1 Initial PARs for General Emergency Classification 6.1.1 Initiate Form 5790-102-02 (MONTICELLO EMERGENCY NOTIFICATION REPORT FORM).
A.
Complete Section 1.4 recommending an evacuation of a 2 mile radius and 5 miles downwind and advise the remainder of the plume EPZ to go indoors to monitor EAS broadcasts.
B.
Determine which geopolitical subareas are affected by referring to the Sector-Subarea Conversion Table on Form 5790-102-02.
C.
Ensure completion of Parts 1.0 and 2.0 of Form 5790-102-02 and submit the completed form to the ED for approval.
6.1.2 Ensure transmission of the recommendations, via telephone and telecopy, to the State EOC (State Duty Officer, Wright and Sherburne Counties if the State EOC is not activated) in accordance with EPIP A.2-501 (COMMUNICATIONS DURING AN EMERGENCY).
6.1.3 Approximately 30 minutes after making the recommendation, contact the State Planning Chief or State Duty Officer if State EOC is not activated to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented and indicate the completion status on the Radiation Protection Status Board.
6.1.4 Update the Emergency Director and TSC personnel (if activated and staffed) on the status of off-site Protective Action implementation.
6.1.5 After making initial Protective Action Recommendations (at the General Emergency Class) continually assess plant conditions and off-site dose projection results. Make subsequent off-site protective action recommendations based on projected off-site doses using the Protective Action Guidelines (PAGs) listed in FIGURE 7.3.
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rMONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION
- levision 15 RECOMMENDATIONS Page 5 of 22 6.2 PARS for Sherco Plant NOTE: To safely shutdown the Sherco Plant requires 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the unit(s) are tripped.
6.2.1 Throughout the event the REC (or Assistant REC) should review off-site projected doses and affected Sectors (Subareas) to determine if the Sherco Plant is or will be in the affected area.
NOTE: The Sherco Plant is located in the 5N subarea.
6.2.2 Formulate protective action recommendations for the Sherco Plant as follows:
A.
Recommendations based on Projected Dose (whole body):
- 1.
> 500 mrem (TEDE) - recommend evacuation of non-essential personnel from the Sherco site and shelter essential plant personnel during plant operation.
- 2.
> 1 Rem (TEDE) - recommend shutdown of the Sherco Plant(s). Immediate evacuation of non-essential personnel and sheltering of essential personnel during normal plant shutdown.
- 3.
> 5 Rem (TEDE) - recommend immediate evacuation of non-essential personnel and sheltering of essential personnel during emergency plant shutdown. Evacuate all personnel immediately after plant shutdown.
B.
Recommendations based on General Emergency:
- 1. If evacuation is implemented (in 5N) recommend evacuation of all non-essential personnel and sheltering of essential Sherco personnel. Recommend immediate initiation of plant shutdown.
6.2.3 If protective actions are required for the ShercoPlant, discuss the recommendations with the Emergency Director.
6.2.4 Monitor the progress of protective action implementation (at Sherco) to determine when they are completed.
6.2.5 Indicate any PARs recommended (and implemented) for the Sherco Plant on the RP Status Board in the TSC.
6.2.6 Advise the Emergency Director if conditions change (e.g., significant increase in release rate) which could change the protective action recommendations for the Sherco Plant.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION
- Revision 15 RECOMMENDATIONS Page 6 of 22 6.3 Off -site PARs Based on Projected Doses Do not delay recommending off-site protective actions while waiting for off -site monitoring results to verify the accuracy of the dose projection model.
Do not delay recommending off-site protective actions while trying to resolve questionable data (MIDAS Data or Field Team Data).
6.3.1 Continuously review dose projection data (4 day integrated maximum TEDE and Thyroid CDE) on Form 5790-102-03 (EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE) and compare with the Protective Action Guidelines in Figure 7.3. If an updated PAR, based on dose projections is required, proceed to Step 6.3.2. Continuously review meteorological data (wind direction and wind speed) on Form 5790-102-03 and determine the affected sectors. If an updated PAR, based on meteorological data is required, proceed to Step 6.3.2.
6.3.2 Initiate Form 5790-204-01 (MONTICELLO OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST) and complete the airborne release section.
6.3.3 Using current meteorological data (i.e., wind direction and wind speed), determine the affected Sectors, Geopolitical Subareas (using page 2 of Form 5790-204-01), population centers within the affected area and estimated plume arrival time in those areas.
6.3.4 Based on plant conditions, estimate the duration of the existing release or potential release.
6.3.5 Using available weather forecast data, evaluate the potential for wind direction and wind speed changes during the estimated duration of the release (and after). Determine what effect potential wind direction and wind speed changes would have on the affected areas identified in 6.3.3.
NOTE: Weather forecast information may be obtained from the National Weather Service. Refer to the Monticello and Prairie Island Emergency Preparedness Telephone Directory for telephone numbers.
NOTE: If data used in the determination of the PAR is/was questionable, attempt to verify the data. DO NOT delay the issuance of the PAR. If after verification of questionable data a PAR revision is necessary, complete section 6.3 of this procedure.
6.3.6 If based on dose projections or field team data a PAR beyond the 10 mile EPZ is necessary, immediately contact the State Planning Chief to inform them of this condition. Document the PAR recommendation in the comments section of Form 5790-204-01 and attach a copy of the supporting Follow-up Message.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION revision 15 RECOMMENDATIONS Page 7 of 22 6.3.7 Indicate the recommendations on page 3 of Form 5790-204-01.
Indicate the recommendation in terms of Sectors and Subareas by completing and circling the applicable information as follows:
A.
Identify the affected keyhole by selecting a 3600 out to 2 or 5 miles. Determine the affected Sectors by including both Sectors on either side of the downwind Sector (two Sectors on either side should be included if the downwind direction is on a Sector line).
Record the 3 (or 4) affected Sectors on page 3 of the Monticello PAR Checklist.
B.
Identify the affected geopolitical subareas using the Sector-Subarea Conversion Chart (page 2 of Form 5790-204-01) and circle the affected subareas on the PAR Checklist.
6.3.8 Submit the completed page 3 of Form 5790-204-01 to the Emergency Director for approval. Review and discuss the recommendations with the Emergency Director as necessary.
NOTE: Prior to activation of the State EOC, protective action recommendations should be made directly to the State Duty Officer and Wright and Sherburne Counties (EOCs if activated). The State Duty Officer will coordinate the EAS message and PANs activation with counties. Once the State EOC is activated, all protective action recommendations SHALL be made directly to the State authorities.
6.3.9 The Emergency Director (or REC) should direct an Emergency Communicator to transmit the approved Monticello Off-Site Protective Action Recommendation Checklist, to the State EOC (Wright and Sherburne County EOCs only if the State EOC is not yet activated) in accordance with EPIP A.2-501.
6.3.10 When notified by the Emergency Communicator that the transmittal of the protective action recommendation has been made to the State Planning Chief (if State EOC is activated) or the State Duty Officer, Wright County and Sherburne County (if State EOC is not activated),
contact either the State Planning Chief or the State Duty Officer, Wright County and Sherburne County. Discuss the recommendations and explain the basis of the recommendations.
6.3.11 Approximately 30 minutes after making the recommendation, contact the State Planning Chief or State Duty Officer prior to State EOC activation, to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented and indicate the completion status on the Radiation Protection Status Board.
6.3.12 If, as a result of continuing assessment, dose projection results or meteorological conditions change significantly, re-evaluate the previously implemented protective actions and, if necessary, update the protective actions by issuing another recommendation.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION
ýevision 15 RECOMMENDATIONS Page 8 of 22 6.4 Protective Action Recommendation for Liquid Releases 6.4.1 Initiate Form 5790-204-01 and complete the Liquid Release Section.
6.4.2 Obtain the isotopic analyses of liquid samples taken at the Discharge Canal or release point.
NOTE: During a liquid release, samples may be taken at the discharge structure, mid-canal sample station, canal out-fall to the river, or as near the source of the release as possible. To ensure samples are representative of the material being released to the river, the Canal Sample Station is the preferred sampling location.
6.4.3 Determine the present Discharge Canal flow rate and river flow rate at the plant (refer to the applicable plant computer point for flow rates).
6.4.4 Determine the river flow rate at either the Coon Rapids Dam or the Minneapolis-St. Paul water intakes by contacting the Minneapolis Water Department (refer to the Monticello and Prairie Island Nuclear Emergency Telephone Directory for telephone numbers).
6.4.5 Using the curve RIVER FLOW vs TIME curve (FIGURE 7.5) estimate the time of release arrival at the Minneapolis-St. Paul water intakes based on current, actual river flow (if actual river flow is not available, use the monthly average river flow in FIGURE 7.5).
6.4.6 Using the MIDAS User Manual Procedures access the MIDAS liquid release model. Enter the isotopic and other applicable release data.
6.4.7 Using the MIDAS Liquid Release Dose Assessment printout, formulate off-site protective action recommendations in accordance with the guidelines in FIGURE 7.6.
6.4.8 Indicate the recommendations on page 3 of Form 5790-204-01 and submit the completed form for Emergency Director approval.
6.4.9 Transmit the recommendations to the State Planning Chief (State EOC if activated) in accordance with EPIP A.2-501.
6.4.10 Contact the State Planning Chief (in the State EOC if activated) to explain the basis for the recommendations.
6.4.11 Approximately 30 minutes after making the recommendation, contact the State Planning Chief to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION revision 15 RECOMMENDATIONS Page 9 of 22 7.0 FIGURES FIGURE 7.1 Definitions Related to Protective Actions Recommendations
- 1.
Affected Area is any area where radiation emanating from a plume, or from material deposited from the plume, can be detected using field instruments (also known as the footprint).
- 2.
Cloudshine is radiation from radioactive materials in an airborne plume.
- 3.
Committed Dose Equivalent (CDE) refers to the dose received over the 50 year period following an intake of radioactive materials.
- 4.
Committed Effective Dose Equivalent (CEDE) is the sum of the products of the weighted factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissue.
- 5.
Dose equivalent means the product of the absorbed dose in tissue, quality factors, and all other necessary modifying factors at the location of interest.
- 6.
Effective dose equivalent (EDE) is the sum of the product of the absorbed dose in tissue, quality factors, and all other necessary modifying factors at the location of interest.
NOTE: Deep Dose Equivalent (DDE) is considered equivalent to EDE if the exposure is uniform.
- 7.
Emergency Planning Zone (EPZ) is a defined area which facilitates emergency planning by State and local authorities to ensure that prompt and effective actions are taken to protect the public in the event of a radioactive release from the plant. The EPZ is defined for two areas:
B. Plume Exposure Pathway (10 Mile EPZ) is the 10 mile, 3600 radius around the plant in which the primary concern is short-term exposure from the plume. The principal sources of exposure in this area are 1) whole body external exposure to gamma radiation from the plume and deposited material from the plume, and 2) internal exposure from inhaled material from the plume.
C.
Ingestion Exposure Pathway (50 Mile EPZ) is a 50 mile, 3600 radius around the plant in which the principal exposure would be from ingestion of contaminated water or foodstuffs (such as milk or fresh vegetables).
- 8.
Evacuation is the removal of people from an area to avoid or reduce high-level, short term exposure, from a plume or from deposited activity.
- 9.
Geopolitical Subareas are subarea within the 10 Mile EPZ that are defined by predetermined geographic and/or political boundaries.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION
ýevision 15 RECOMMENDATIONS Page 10of22
- 10.
Groundshine is radiation exposure caused by radioactive materials deposited on the ground.
- 11.
Ingestion Pathway Projected Dose is the projected CEDE (ICRP-30) from consuming contaminated foodstuffs.
- 12.
Keyhole Area an area within the 10 Mile EPZ defined by a 3600 radius out to a specified distance of 2 or 5 miles and continuing in the downwind direction in 3 or 4 Sectors.
- 13.
Plume Projected Dose refers to future calculated doses from plume submersion, plume shine, plume inhalation and 4 days of ground deposition exposure.
- 14.
Protective Action is an action taken to avoid or reduce a projected dose.
- 15.
Protective Action Guide (PAG) refers to a dose (or commensurate dose rate) which warrants protective actions.
- 16.
Public Alert and Notification System (PANS) is the system used to alert the public within the 10 Mile EPZ of an emergency condition at the plant. Once alerted, the public would turn to local commercial media broadcast messages for specific protective action instructions. The PANS consists of the following systems:
A.
Fixed sirens for 100% coverage throughout the 5 mile EPZ and in population centers between 5 and 10 miles.
B. Local law enforcement emergency vehicles with sirens and public address capability driving route alerting in the 5 to 10 mile areas not covered by fixed sirens.
C.
National Oceanic and Atmospheric Administration (NOAA) alert radios in institutional, educational, and commercial facilities.
D. The Emergency Alert System (EAS) which accesses local television and radio stations.
- 17.
Recovery is the process of reducing radiation exposure rates and concentration of radioactive material in the environment to levels acceptable for unconditional occupancy.
- 18.
Relocation Projected Dose is the projected effective committed dose from 1 year of exposure to radioactive material deposited as fallout from a plume, including whole body exposure to gamma radiation (groundshine), and internal dose from inhalation of resuspended material, but excluding internal dose from consuming contaminated foodstuffs.
- 19.
Return refers to people permanently reoccupying their normal residence within an area that was evacuated during the emergency condition.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION 3evision 15 RECOMMENDATIONS Page 11 of 22
- 20.
Re-entry refers to temporary entry into a restricted (evacuated) area under controlled conditions.
- 21.
Secondary Evacuation refers to relocating people from areas to avoid or reduce relocation projected dose.
- 22.
Sector is one of 16, 22.50 sectors around the plant which compose the 10 Mile EPZ.
- 23.
Sheltering provides radiation protection from an airborne plume and/or deposited radioactive materials. Sheltering also ensures effective public 'notification, via media, should the need for evacuation occur.
- 24.
Total Effective Dose Equivalent (IEDE) is the sum of external EDE and CEDE.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION levision 15 RECOMMENDATIONS Page 12 of 22 FIGURE 7.2 Discussion of Protective Action Recommendation The following is a discussion of the various Protective Action Recommendations (PARs) that could be made to off-site authorities. The Protective Action Guidelines (PAGs) listed are derived from EPA guidelines (EPA 400).
A.
NO PROTECTIVE ACTIONS The recommendation for no protective actions is self-explanatory and is appropriate when projected plume doses do not exceed 1000 mrem (TEDE) or 5000 mrem (CDE) thyroid dose. For liquid releases, no protective actions are warranted if the concentration in raw river water at outflow of discharge canal is less than the concentration listed in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 (ODCM-04.01, Table 1).
B.
EVACUATION Evacuation is the movement of a population out of an area in order to reduce or eliminate direct or indirect radiation exposure. Timely evacuation of the population is the most effective protective action.
Initial PARs for a General Emergency involving loss of physical control or core damage are based on NRC Response Technical Manual RTM-93, Vol 1, Rev. 3,Section I.
Immediate evacuation of the general public is justified without dose projection.
EPA 400 indicates that evacuation of the general public will usually be justified when the projected dose to an individual is greater or equal to 1000 mrem TEDE (or 5000 Thyroid CDE). At these dose levels, the risk avoided due to the radiation exposure is usually much greater than the risk from evacuation itself.
Using the projected dose criteria stated above, Monticello Nuclear Generating Plant (MNGP) should recommend evacuation to the State. In turn, they will independently assess and implement protective actions based on our recommendation, their independent assessment, and current off-site evacuation constraints.
C.
CLOSURE OF WATER INTAKES Water Intakes PAG: Concentration in raw river water exceeds the value listed in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 (ODCM-04.01, Table 1).
Closure of the water intakes is an appropriate recommendation in the case of a liquid release to the river which is expected to result in river water concentrations exceeding the MPC limits for unrestricted areas.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION levision 15 9
RECOMMENDATIONS Page 13 of 22 FIGURE 7.2 Discussion of Protective Action Recommendation (Cont'd)
D.
SECONDARY EVACUATION Relocation PAG (in mrem): 2000 (TEDE)
To avoid social and family disruption and the complexity of implementing separate PAGs for individual members of the population, the relocation PAG may be applied for all members of the population. While the relocation PAG is based on projected doses to adults, infant relocation projected doses are not more than two times higher than the adult projected dose.
Based on EPA 400 PAGs, MNGP should recommend relocation of the general public from affected areas not previously evacuated when the projected dose is greater or equal to 2000 mrem CEDE from exposure or intake during the first year. This projected dose includes doses from external radiation, and inhalation of resuspended materials.
E.
RETURN Return is allowed at levels below the secondary evaluation PAG (2000 mrem TEDE).
The decision to return segments of the public from previously evacuated areas will be determined by appropriate off-site agencies. Various cautions and dose reduction techniques will be assessed and, if necessary, communicated to the people upon their return.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION 3evision 15 RECOMMENDATIONS Page 14 of 22 FIGURE 7.2 Discussion of Protective Action Recommendations (Cont'd)
F.
DESIGNATION OF THE AFFECTED PROTECTIVE ACTION AREA The designation of the affected protective action area depends on the nature and extent of the incident and existing meteorological conditions. The area will be described by designating an affected keyhole shaped area and the affected geopolitical subareas within the EPZ.
a Affected Keyhole Area The affected keyhole area should resemble a keyhole consisting of a 3600 area surrounding the plant out to a distance of 2 or 5 miles and continuing in the downwind direction out to a distance determined by the PAGs. The affected downwind portion of the keyhole should include 1 sector on either side of the affected sector (i.e., total of 3 sectors). If the downwind direction is on a sector line then 2 sectors on each side of the affected sector should be included (i.e.,
total of 4 sectors).
b Affected Geopolitical Subareas Geopolitical subareas are subareas of the 10 mile EPZ defined by predetermined geographic and/or political boundaries. The affected geopolitical subareas are defined by any and all subareas that intersect the affected keyhole area.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION 3evision 15 RECOMMENDATIONS Page 15 of 22 FIGURE 7.2 Discussion of Protective Action Recommendations (Cont'd)
G.
(EXPOSURE PATHWAYS, Incident Phases, and Protective Actions POTENTIAL EXPOSURE PATHWAYS PROTECTIVE ACTIONS AND INCIDENT PHASES
- 1.
External radiation from facility Sheltering Evacuation Control of access
- 2.
External radiation from plume Sheltering Evacuation EA LY Control of access
- 3.
Inhalation of activity in plume Sheltering Administration of stable iodine Evacuation Control of access
- 4.
Contamination of skin and Sheltering clothes INTE MEDIATE Evacuation Decontamination of persons
- 5.
External radiation from ground Evacuation deposition of activity Relocation Decontamination of land LT'IE and property
- 6.
Ingestion of contaminated food Food and water controls and water
- 7.
Inhalation of resuspended Relocation activity Decontamination of land and property NOTE 3:
Based on EPA 400-R-92-001, May 1992 NOTE 4:
The use of stored animal feed and uncontaminated water to limit the uptake of radionuclides by domestic animals in food chain can be applicable to any of the phases.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION 3evision 15 RECOMMENDATIONS Page 16 of 22 FIGURE 7.3 Protective Action Guidelines (PAGs)
PAG VALUES 1 RECOMMENDED COMMENTS PROTECTIVE ACTIONS Less than None required The State may choose
<1 REM (TEDE) to implement sheltering at their discretion. No recommendations are required from MNGP.
Greater than Recommend The State may chose WHOLE BODY2
>1 REM (TEDE) evacuation of the to implement sheltering PROJECTED general public, of the general public DOSE up to 5 REM (TEDE) or special population groups up to 10 REM (TEDE) if immediate evacuation is not practicable due to off-site constraints.
No sheltering recommendations are required from MNGP.
Less than None required The State may choose
<5 REM (CDE) to implement sheltering at their discretion. No recommendations are THYROID 3 required from MNGP.
(CDE)
Greater than Recommend The State may choose PROJECTED
>5 REM (CDE) evacuation of the to implement sheltering DOSE general public.
of the general public if immediate evacuation is not practicable due to off-site constraints.
No sheltering recommendations are required from MNGP.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE, PROTECTIVE ACTION 3evision 15 RECOMMENDATIONS Page 17 of 22 FIGURE 7.3 Protective Action Guidelines (PAGs) (Cont'd)
PAG VALUES 1 RECOMMENDED COMMENTS PROTECTIVE ACTIONS SKIN 4 Less than None required The State may choose (CDE)
<50 REM (CDE) to implement simple PROJECTED personal protective DOSE actions (washing). No recommendations are required from MNGP.
Greater than Recommend The State may choose
>50 REM (CDE) evacuation of the to implement sheltering general public of the general public or simple personal protective actions if immediate evacuation is not practicable.
NOTE 1:
Protective Action Guides are based on EPA 400-R-92-001, May 1992.
NOTE 2:
TEDE = Total Effective Dose Equivalent; is the sum of the effective dose equivalent from exposure to external source and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the Early Phase.
NOTE 3:
CDE = Committed Dose Equivalent to the Thyroid from radioiodine.
NOTE 4:
Committed Dose Equivalent to the skin from exposure to beta radiation from radioiodines and particulates.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION Revision 15 RECOMMENDATIONS Page 18 of 22 FIGURE 7.4 Emergency Worker Exposure Limits EXPOSURE LIMIT 1 EMERGENCY ACTIVITY1 COMMENTS 5 REM (TEDE)(2)(3)
All emergency activities This dose limit applies when a lower dose is not practicable through application of ALARA practices.
Protection of valuable This dose limit applies when property a lower dose is not practicable through application of ALARA practices.
Life saving or protection of Doses in excess of 25 REM large populations should be on a voluntary basis to persons fully aware of the risks involved.
NOTE 1:
Dose limits for emergency workers and activities are based on EPA 400-92-001, May 1992.
NOTE 2:
Sum of external effective dose equivalent and committed effective dose equivalent to non-pregnant adults from external exposure and intake during the duration of an emergency.
NOTE 3:
Exposure to the lens of the eye should be limited to 3 times the value listed and doses to the skin and/or extremities should be limited to 10 times the value listed.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION 3evision 15 F
RECOMMENDATIONS Page 19 of 22 FIGURE 7.5 Transport Time and Monthly Average Flowrates 80000 70000 60000 50000 40000 30000 20000 8000----------------------
7000 6000------------------
500-----------------
4000--------------
300----------------
200 0
~nv'r 60 50 40 30 20 10 TIME (HRS) TO MINNEAPOLIS INTAKE (MULTIPLY BY.9 FOR ST PAUL INTAKE)
I/mab LL 0
,_j LL LU w
w w
I VV*
MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION
ýevision 15 RECOMMENDATIONS Page 20 of 22 FIGURE 7.5 Transport Time and Monthly Average Flowrates (Cont'd)
MONTH JANUARY FEBRUARY MARCH APRIL MAY JUNE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVG RIVER FLOWRATE (CFS) 4663 4579 6336 10890 10157 7369 5352 3506 3334 5690 5438 4555 I/mab I
MONTICELLO NUCLEAR GENERATING PLANT I
A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION levision 15 RECOMMENDATIONS Page 21 of 22 FIGURE 7.6 Liquid Release Protective Action Criteria A.
PROTECTIVE ACTION BASED ON PROJECTED INTERNAL DOSE A. Concentration in Raw River: < Value listed in 10CFR20, Appendix B. - No protective action required.
B. Concentration in Raw River: > Value listed in 10CFR20, Appendix B. - Recommend closure of water intakes.
C. Projected Internal (Drinking) Dose:
< 250 mrem - No protective action required.
> 250 mrem - Preventive protective actions are necessary.
> 1000 mrem - Emergency protective actions are necessary.
B. PROTECTIVE ACTION BASED ON PROJECTED EXTERNAL DOSE A. Projected Total External Doses r250 mrem - No protective action required.
> 250 mrem - Preventive protective actions are necessary.
> 1000 mrem - Emergency protective actions are necessary.
NOTE: Obtain total external projected dose by calculating the swimming, boating and standing projected doses using the following time assumptions for shoreline activities.
Swimming - 3 hrs/day Boating
- 1 hrs/day Standing
-6 hrs/day RECOMMENDED PREVENTIVE PROTECTIVE ACTIONS A. Close Raw Water Intakes B. Restrict Intake of Drinking Water, and Foodstuffs obtained from River.
C. Restrict swimming and boating on River.
D. Restrict access to River.
E. Restrict use of River for irrigation and industry.
RECOMMENDED EMERGENCY PROTECTIVE ACTIONS A. Close Raw Water Intakes B. Condemn drinking water obtained from river.
C. Condemn affected foodstuffs (milk or meat from animals consuming contaminated water or foodstuffs).
D. Prevent access to river.
E. Condemn use of river for irrigation and industry.
F. Substitute uncontaminated water and foodstuffs for contaminated water and foodstuffs.
G. Condemn water usage from river.
Reference:
Minnesota Department of Health, Dose Assessment Manual: Part 2, Liquid Releases.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-204 TITLE:
OFF-SITE PROTECTIVE ACTION levision 15 RECOMMENDATIONS Page 22 of 22 FIGURE 7.7 Forms Utilized in Procedure NUMBER TITLE
- 1.
5790-102-02
- 2.
5790-204-01 MONTICELLO EMERGENCY NOTIFICATION REPORT FORM MONTICELLO OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST I/mab
MONTICELLO NUCLEAR GENERATING PLANT
' "A.2-21 0
TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 1 of 17 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION P) 1.0 PU R PO SE........................................................
2.0 APPLICABILITY...................................................
3.0 ORGANIZATION AND RESPONSIBILITIES...........................
4.0 D ISC U SSIO N......................................................
5.0 PRECAUTIO NS....................................................
6.0 INSTRUCTIO NS...................................................
6.1 Initial Activation and Staffing...................................
6.2 Continuing Actions...........................................
6.3 SPDS/ERIS Vax Instructions...................................
6.4 Activation of the Accident Management Team (AMT)..............
6.5 Activation of GE's BWR Nuclear Emergency Support Program.....
7.0 FIG U R ES.........................................................
7.1 Forms and Guidelines Utilized in this Procedure..................
7.2 Accident Management Team (AMT) Responsibilities..............
.GE 2
2 2
2 3
3 3
7 11 12 13 16 16 17 This*!
revision incorporates volumeF*iJ*
emos:-______FO__AMINSTRTIVUEONL________________________-__________:**:,
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ARMS:
A2-210 TDoc Type: 1060 1Admin Initials: k Date: -J4 134)
I/mab Prepared By:,
Reviewed By:
OC Review Req'd: YES 0 Meeting Number:r Approved By:
Date:
MONTICELLO NUCLEAR GENERATING PLANT A.2-210 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 2 of 17 1.0 PURPOSE The purpose of this procedure is to provide instructions and guidance for the activities of the engineering staff in the Technical Support Center (TSC) during an emergency.
2.0 APPLICABILITY 2.1 An emergency (Alert classification or higher) has been declared at the MNGP.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Engineering Group Leader is responsible for:
3.1.1 Overall direction and supervision of Engineering Group activities.
3.2 The Engineering Coordinator is responsible for:
3.2.1 Implementation of this procedure.
3.2.2 Coordination of Engineering Group activities including parameter trending, plotting and forecasting, system operational assessment and trouble shooting.
3.3 The TSC Engineering Staff is responsible for:
3.3.1 Proactive evaluation of the overall event including anticipating adverse events, forecasting trends and recommending preventive or corrective actions to avoid or mitigate accident consequences.
3.3.2 Trending and analysis of plant parameters, assessment of system availability, problem-solving and trouble shooting.
3.4 The minimum TSC Engineering Staff is defined as:
3.4.1 1 Mechanical System Engineer 1 Electrical System Engineer 1 Nuclear Engineer 2 Technical Communicator 1 Emergency Communicator 4.0 DISCUSSION This procedure structures the response of the TSC engineering group to an emergency by recommending a variety of accident assessment and evaluation activities that may be undertaken depending on the emergency situation. Of these activities, the most important is the evaluation of events which have or are occurring to gain a thorough understanding of the event and to investigate those aspects which are not understood or that deviate from the expected. This evaluation includes assessment of anticipated or potential events or transients which may adversely I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 3 of 17 affect accident mitigation efforts and the development of preventive or contingency plans to minimize their affect on mitigation efforts. It may also involve the prediction and analysis of potential system or component failures and development of contingency plans to manage failures should they occur. Other activities include the trending of critical plant control parameters, assessment of inoperable systems or components and general problem solving.
Due to the wide spectrum of possible accident scenarios, this procedure is general in nature and designed, in association with the Technical Support Guidelines (TSGs), to aid the engineering group in assisting the TSC staff in accomplishing accident mitigation. The term "accident mitigation" refers to those activities identified by the TSC staff which are intended to mitigate or minimize the consequences of the particular accident and may include cooling the Reactor, maintaining or regaining containment integrity, and terminating or reducing any radioactive release to the environment.
To effectively utilize resources and focus on solving individual problems that may arise, the concept of "task groups" is introduced. This concept involves the creation of task groups, consisting of engineering, I&C, mechanical or electrical maintenance and operations personnel (from the OSC) to evaluate or assess significant problems related to accident mitigation efforts (e.g. an inoperable component or system). Task group make-up depends on the problem, although the group "leader" should be an individual knowledgeable in the problem area (e.g. system engineer or alternate if available). One or several task groups may be used depending on the number of problems encountered.
5.0 PRECAUTIONS None 6.0 INSTRUCTIONS 6.1 Initial Activation and Staffing 6.1.1 Upon notification of an emergency, refer to the main ERO Tagboard to determine Engineering Coordinator assignment in accordance with Procedure A.2-001 (EMERGENCY ORGANIZATION).
6.1.2 Upon arrival in the TSC the Engineering Coordinator should assess engineering group staffing and augment as necessary. Request the assistance of the Support Group Leader if additional engineering personnel must be contacted.
6.1.3 Initiate Form 5790-210-01 (ENGINEERING GROUP LEADER CHECKLIST).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-210 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 1Page 4 of 17 NOTE: The Technical Support Guidelines (TSGs) describe enhancements (additional information and methods to support decision making) to technical support activities that are normally undertaken by the ERO staff in support of the control room. TSGs should be utilized by the TSC staff and Accident Management Team (AMT) to support implementation of the EOPs/SAMGs. AMT General Responsibilities and associated checklists are listed on Figure 7.2.
The TSGs consist of four interrelated assessments which address these enhancements in the following functions:
A.7-TSG-02 (CONTROL PARAMETER STATUS ASSESSMENT): obtaining and processing appropriate plant data in the ERO.
A.7-TSG-03 (PLANT STATUS ASSESSMENT): assessing current conditions in various areas of the plant where needed instruments or equipment are located.
A.7-TSG-04 (SYSTEM STATUS ASSESSMENT): evaluating the availability of systems needed to implement the EOPs/SAMGs.
A.7-TSG-05 (EOP/SAMG ACTION STATUS ASSESSMENT): prioritize system restoration and action timing as indicated by accident management strategies.
6.1.4 Evaluate all available data and information related to the event to:
A.
Determine what has or is happening, including its overall effect on plant operations.
B.
Determine if the events that have occurred or are occurring are completely understood.
C.
Investigate any aspects of the event that are not completely understood or that don't make sense (i.e. based on our understanding of the event, is there anything that doesn't fit or that was unexpected).
D.
Identify any anomalies in trends or data and determine their cause.
6.1.5 Based on the event evaluation:
A.
Predict upcoming transients or evolutions and evaluate their effect on accident mitigation.
B.
Anticipate transients or events which may adversely affect accident mitigation efforts and:
- 1. Recommend preventive actions to avoid the anticipated occurrence, or
- 2.
Develop and recommend contingency actions should the anticipated occurrence be unavoidable.
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MONTICELLO NUCLEAR GENERATING PLANT
'*;A.2-21 0
TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 5 of 17 NOTE: Suggested control parameter trend charts are provided in A.7-TSG-03 Figures 5.1 through 5.10.
C.
Forecast trends and determine the potential, adverse consequences of the trends to accident mitigation.
6.1.6 As qualified personnel become available:
NOTE: Refer to Form 5790-001-01 for qualified Evaluators.
A.
Assign an individual(s) to manipulate the SPDS terminal.
Individual(s) should be Evaluator qualified.
B.
Assign an individual(s) to trend, plot and forecast control parameters that are identified by the TSC Group Leaders as being significant to the event. Individual(s) should be Evaluator qualified.
C.
Assign an individual(s) to manipulate the Process Computer System (PCS) including the Transient Recording and Analysis (TRA) function.
NOTE: Assessment should include a determination of the event's actual or potential effect on plant operations and the formulation of preventive and/or corrective action plans necessary to avoid or minimize the consequences of the event. It should also include an assessment of inoperable systems or components crucial to accident mitigation and determine corrective actions or alternative methods to restore lost capabilities.
D.
Assign available Engineering Supervisors to assess the event in j their areas or expertise.
NOTE: Refer to Form 5790-001 -01 (EMERGENCY RESPONSE ORGANIZATION) for qualified Emergency Communicators and Technical Communicators.
I E.
Verify an adequate number of Emergency Communicators and Technical Emergency Communicators are assigned to fill the responsibilities described below.
- 1. Emergency Communicators are required to:
- a.
Assume the duties of Lead Emergency Communicator and report to the Emergency Director. (TSC Tag Board responsibility #20).
- b. Assume the duties of Assistant #1 Emergency Communicator and report to the Lead Emergency Communicator. (TSC Tag Board responsibility #21).
- c.
Assume the duties of Assistant #2 Emergency Communicator and report to the Lead Emergency Communicator. (TSC Tag Board responsibility #22).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 6 of 17
- d.
Assume the duties of Emergency Director Communicator and assist with the use of the EPIPs.
(TSC Tag Board responsibility #23).
- e.
Assume the duties of Assembly Point Coordinator in the event of a radiological release. (TSC Tag Board responsibility #24).
- f.
Man the OSC-TSC telephone link and maintain the OSC Personnel Availability and Team Tracking status boards. (OSC Tag Board responsibility #3).
- g.
Man the OSC radio console for the purpose of directing OSC teams (by radio).
- 2.
Technical Emergency Communicators are required to:
- a.
Man the TSC-Control Room-EOF telephone link in the I
TSC and maintain the Operational Status Board. The TSC Technical Communicator will add the OSC to complete a link. (TSC Tag Board responsibility #25).
- b.
Man the TSC-Control Room-EOF telephone link in the Control Room. (TSC Tag Board responsibility #26).
- c.
Man the TSC-OSC telephone link and maintain the Emergency Work Status Board. (TSC Tag Board responsibility #27).
- d.
Man the NRC FTS - Emergency Notification System (ENS) telephone in the TSC.
- e.
Man the TSC-Control Room-EOF-OSC telephone link in the OSC and maintain the Operational Status Board.
(OSC Tag Board responsibility #2) 6.1.7 Determine if off-site utility organizations (e.g. substation crews, corporate engineering, core analysis, etc.) may be required to assist in engineering assessment efforts. If so, coordinate contacting these organizations with the Lead Emergency Communicator.
6.1.8 If the duration of the event could exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, evaluate the engineering group staffing required to support 24-hour coverage. If and when requested by the Support Group Leader, coordinate the assignment of shift engineering personnel by completing Form 5790-106-03 (ERO SHIFT SCHEDULE-ENGINEERING GROUP) and forwarding the completed schedule to Support Group Leader.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 7 of 17 6.1.9 If 24-hour coverage will be required, coordinate the departure of "next shift" engineering personnel as follows:
NOTE: Ensure personnel are instructed to contact the Support Group Leader if their final destination, after departing the site, is a location other than their permanent residence (i.e. a telephone number at which they can be reached).
A.
Normal departure - Instruct personnel to depart the site using normal departure procedures.
B.
Evacuation - Coordinate the departure of "next shift" personnel (to the on-site or off-site Assembly Point or home) with other evacuees from the plant or site.
6.2 Continuing Actions 6.2.1 Continuously assess plant conditions and provide engineering advice to the Engineering Group Leader in support of TSC operation.
A.
TSGs should be utilized by the TSC staff and AMT to support implementation of EOPs/SAMGs. Refer to FIGURE 7.2 for general responsibilities.
6.2.2 Continually assess the engineering aspects of the event to anticipate potential problems that may be encountered. As problems arise, assess the engineering aspects of the problem according to its importance to accomplishing accident mitigation. Provide input to the Engineering Group Leader (or TSC Group Leaders) on possible solutions or alternative mitigation possibilities.
6.2.3 Direct the SPDS operator(s) to obtain data and information applicable to the event and:
A.
Assist in trending, plotting and forecasting of critical plant (control) parameters to identify adverse trends.
B.
Immediately report significant adverse trends (or data) to the Engineering Coordinator or Engineering Group Leader for assessment and forecasting (predicting) of potential significant events that could adversely affect the plant or accident mitigation efforts underway or planned.
C.
Provide control parameter trends to the TSC Operations Group for comparison with Emergency Operating Procedures/Severe Accident Management Guidelines (EOPs/SAMGs) implementation to aid in predicting upcoming operational evolutions.
D.
Periodically or when significant trends are identified, obtain hardcopy trends and distribute to all TSC Group Leaders for review.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 8 of 17 E.
When the immediate emergency phase is terminated, trend selected control parameters (over the duration of the emergency phase) to aid in the evaluation of the entire event.
6.2.4 Continuously remain aware of plant conditions and control parameters.
Periodically, and as significant changes occur, compare plant conditions/parameters with the Emergency Action levels (EALs) contained in EPIP A.2-101 (CLASSIFICATION OF EMERGENCIES).
Make recommendations regarding classification changes (based on plant conditions or control parameters) to the Emergency Director.
6.2.5 Coordinate engineering assessment activities as follows:
A.
For situations which are crucial to accident mitigation (e.g. a system or alternative is required immediately), the Engineering Coordinator and engineering group should evaluate the situation collectively and provide conclusions and recommendations promptly to the Engineering Group Leader.
B.
For situations where an immediate evaluation is not required (i.e.
a solution is not immediately crucial to accident mitigation) the formation of a TSC-OSC Task Group should be considered or the problem referred to the EOF Technical Support Group.
6.2.6 For plant systems or components that have or may become inoperable:
A.
Prioritize the system or components in order of their importance to accident mitigation.
B.
Develop preventive measures to avoid the failure or contingency plans in the event the failure is unavoidable.
C.
Determine corrective actions required to restore lost capabilities or alternative methods to accomplish the mitigation objective.
D.
For crucial mitigation objectives, which rely on alternate (i.e.
backup) systems or methods, develop a contingency plan to manage the consequences of a failure of the backup system or method.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-210 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 9 of 17 6.2.7 The formation and activities of TSC-OSC Task Groups should be coordinated as follows:
NOTE: The work space immediately outside the TSC is designated for Engineering group use. In addition, the Operations Training Room may be used for task group work space.
A.
A task group may consist of the following personnel as necessary:
- 1. System engineer (or alternate) if available.
- 2.
I&C electrical and/or mechanical maintenance personnel (from the OSC).
- 3.
Other engineering staff (as necessary).
- 4.
EOF Technical Engineering personnel (by telephone).
- 5.
General Electric or other vendor (by telephone).
B.
The task group should determine methods to prevent anticipated system or component failure or the reason(s) for actual system or component failure and what actions may be required to return the system or component to an operational status. The following resources should be considered in their evaluation:
- 1. Prints/drawings (Construction Drawing File, etc.).
- 2.
Technical Manuals or vendor literature.
- 3.
Maintenance History File (if applicable).
- 4.
Contacting the vendor directly or requesting the EOF Technical Engineering staff contact the vendor.
- 5.
On-scene inspection of the component or system by emergency teams dispatched from the OSC (the team may include or be solely comprised of task group personnel).
C.
The task group should proactively evaluate alternate systems, components or methods that may be used (in lieu of the inoperable system or component) to restore needed capabilities or accomplish mitigation objectives.
D.
Upon completion of their evaluation, the task group should make recommendations to the Engineering Coordinator or Group Leader on corrective maintenance/repair action or alternative methods of accomplishing accident mitigation (i.e. alternate systems or methods to perform the function of the inoperable system or component).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-210 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 IPage 10 of 17 E.
Members of the task group may be used to brief OSC teams prior to being dispatched from the OSC, they may participate on the OSC Emergency Team itself or, upon completion of the assignment, dissolve back into the TSC Engineering staff.
6.2.8 As the engineering staff makes recommendations to the Engineering Coordinator or Group Leader, the recommendations should be reviewed with the TSC Group Leaders. During the review, the Group Leaders should:
A.
Consider the recommendations in the overall emergency response and mitigation effort.
B.
Determine which preventive or corrective action recommendations should be pursued immediately (accident mitigation) and which may be deferred (recovery action list).
C.
Prioritize the actions to be taken in terms of other emergency response actions planned and available resources.
NOTE: The primary responsibility of the EOF Technical Engineering staff is to provide technical advice and support to the Emergency Manager and EOF Staff. This responsibility includes activities such as trending of critical plant (control) parameters (related to source term and containment integrity) in support of the RPSS. Secondary responsibilities include maintaining a "broad engineering perspective" of the incident and functioning as engineering "liaison" between the site and off-site technical services (e.g. equipment or component vendors) in addition to the support activities outlined below.
6.2.9 In some cases, the EOF Technical Engineering staff may be requested to support TSC engineering assessment and mitigation activities. The following are examples of items that may be referred to the EOF Technical Support Supervisor for consideration depending on TSC and EOF resources:
A.
Assessment of anticipated or potential events or transients which may adversely affect accident mitigation efforts and the development or preventive or contingency plans to minimize their affect on mitigation efforts.
B.
The evaluation of inoperable components or systems that are not immediately required to accomplish accident mitigation and that are identified as short-term or long-term "recovery" items.
C.
Assistance with assessment of major engineering problems which arise during the event (i.e. facility, system or component design specifications, etc.) which may require more detailed evaluation than the TSC staff can perform.
D.
Technical "liaison" with off-site technical vendor support on equipment or component needs and specifications (e.g. GE Emergency Support Program).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 11 of 17 E.
The operational and engineering analysis of postulated accident scenarios (i.e. what ifs) on the plant simulator to determine plant response characteristics for existing simulator models.
6.2.10 Refer to applicable A.7-TSGs for additional guidance.
6.2.11 The TSC Group Leaders should initiate corrective action(s) through the Emergency Work Request process. Refer to EPIP A.2-206 (WORK CONTROL DURING EMERGENCIES).
6.2.12 During TSC status updates the Engineering Group Leader should provide a review of inoperable components and systems critical to accident mitigation and a status of the engineering efforts to return the system to an operational status or alternative systems to accomplish accident mitigation. Form 5790-213-02 (EMERGENCY DIRECTOR STATUS UPDATE CHECKLIST) has a list of Engineering Group Items that should be addressed during a TSC Status Update.
6.2.13 Continuously re-evaluate priorities for the engineering staff and redirect the staff's effort as necessary.
6.3 SPDS/ERIS Vax Instructions 6.3.1 Using a PC terminal, log onto the MNGP Computer Network displaying the desktop screen.
6.3.2 From the computer terminal desktop "Start" menu, initiate the "VAXes" application by choosing "Business Applications", Kea 5.0", and "VAXes" from the sequential drop down menus.
NOTE: For drills/exercises in which the Simulator is used, log onto "Host" STONE to obtain simulator plant data.
6.3.3 Respond to the "Host" prompt by typing LARRY or MOE.
6.3.4 Respond to the USERNAME prompt by typing HQEC and pressing RETURN.
6.3.5 Respond to the PASSWORD prompt by typing HQEC and pressing RETURN.
6.3.6 Respond to the FILE NUMBER prompt by entering the number of the desired display (1-28).
6.3.7 Review the data display for desired information. Ensure the status code (displayed on the right of the screen) is code 1 indicating the data is good. If not, the accuracy of the data is questionable.
6.3.8 To change display screens (select other data), enter CTRL Y and respond to the WOULD YOU LIKE TO SELECT ANOTHER FILE prompt by entering Y and pressing RETURN.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 1Page 12 of 17 6.3.9 To exit the system enter CTRL Y and respond to the WOULD YOU LIKE TO SELECT ANOTHER FILE prompt by entering N and pressing RETURN.
6.4 Activation of the Accident Management Team (AM')
NOTE: If the event escalates into a severe accident, in general, considered to begin with the decision to flood primary containment, the Severe Accident Management Guidelines (SAMGs) must be entered. Decision making responsibilities transfer from the Control Room to the TSC. The Engineering Coordinator, as a member of the AMT, will now report to the Operations Group Leader.
6.4.1 Officially organize the Accident Management Team (AMT) in the TSC when the SAMGs are entered.
A.
The AMT is made up of the Operations Group Leader as the Decision Maker and the following Evaluators: Assistant Operations Group Leader, Engineering Coordinator, Nuclear Engineer, SPDS Operator(s), and Individual(s) to trend, plot and forecast control parameters.
- 1. General responsibilities and associated responsibility checklists are identified on FIGURE 7.2 (ACCIDENT MANAGEMENT TEAM RESPONSIBILITIES).
B.
The Engineering Coordinator as a member of the AMT will now report to the Operations Group Leader.
C.
For plant conditions to require entry into the SAMGs, all the defense in depth must have failed for one reason or another.
The operators have utilized all available resources and are still unable to establish and maintain conditions indicative of adequate core cooling. The event has exceeded the on shift capability and additional resources are needed to bring the event under control. The additional resources are provided by augmentation from the ERO outside the control room.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-210 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 13 of 17 6.5 Activation of GE's BWR Nuclear Emergency Support Program NOTE: GE Service Information Letter (SIL) 324 describes the Nuclear Energy BWR Nuclear Emergency Support Program. This program has access to the full resources of GE's engineering organizations in San Jose, California as well as GE personnel located elsewhere.
This program should be activated (i.e., the duty manager contacted) only during nuclear emergencies, or during site emergency drills for which services from GE Nuclear Energy are required. Expedited services not related to such nuclear emergencies are available through the local GE Nuclear Energy Service Representatives.
6.5.1 If the Engineering Group Leader (TSC) or the Technical Support Supervisor (EOF) determine that activation of GE's Emergency Support Program is necessary, make the recommendation to the Emergency Director or Emergency Manager.
6.5.2 If the Emergency Director or Emergency Manager concurs, proceed as described below:
A.
GE Nuclear Energy BWR Nuclear Emergency Support Program
- 1. Dedicated Emergency Communications Coverage
- a.
Dedicated emergency telephone communications coverage is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day, 365 days a year for requesting assistance from GE for actual BWR nuclear emergencies or site emergency drills. Refer to the Nuclear Emergency Telephone Directory for the telephone number to call for GE's BWR Nuclear Emergency Support Program. This number is monitored continuously by the Security Operations Center at GE Nuclear Energy, San Jose, CA.
- b.
During the telephone call to the Security Operations Center, the caller should give the Security Officer his or her name, telephone number, the name of the BWR utility and the name of the affected BWR. (For an actual
.nuclear emergency, BWR owners and operators may wish to dedicate a specific telephone number for communications exclusively with GE.) If the call is for a drill, no further action will be taken. If the BWR Nuclear Emergency Support Program is to be activated, the GE Security Officer will immediately contact a GE Nuclear Emergency Support Program Duty Manager by telephone.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 14 of 17
- 2.
Initial Telephone Contact
- a.
As soon as possible after a call concerning an actual BWR nuclear emergency, a GE Duty Manager will telephone the number provided by the BWR utility to the Security Officer. During this initial telephone contact, the BWR utility representative should define the scope of assistance desired from GE.
- 3.
BWR Nuclear Emergency Support Program activation
- a.
Upon activation of the BWR Nuclear Emergency Support Program, GE will perform the following, if requested:
- 1)
Form and dispatch to the affected site, by chartered jet aircraft (if required), a GE Emergency Response Team composed of GE personnel from the technical disciplines requested by the BWR utility representative. It is GE's intention that the Team arrive at the affected BWR site within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the time of the request. The BWR utility representative will arrange for the GE Emergency Response Team to pass through road blocks and plant security posts in a timely manner. GE will furnish to the BWR utility the name and social security number of each member of the Emergency Response Team.
- 2)
Form a Technical Support Team in San Jose composed of GE personnel from appropriate technical disciplines, and establish dedicated telephone communication with utility personnel at the affected BWR and with local GE Nuclear Energy personnel.
- 3)
Instruct local GE Nuclear Energy personnel to proceed immediately to the BWR site to establish dedicated communications with GE's Technical Support Center in San Jose, collect information requested by the Technical Support Team, and support the BWR utility as directed by the Technical Support Team until the Emergency Response Team arrives at the BWR site.
- 4)
Assist BWR utility personnel in recovering from the nuclear emergency.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 15 of 17 6.5.3 Contact the EOF Coordinator and request an Emergency Purchase Request be processed for the vendor support in accordance with applicable procedures.
6.5.4 Brief the Emergency Director and Technical Support Supervisor on the status of GE's response. Coordinate GE's support with the Technical Engineering Staff in the EOF.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 16 of 17 7.0 FIGURES FIGURE 7.1 Forms and Guidelines Utilized in this Procedure 5790-001-1 Emergency Response Organization 5790-106-3 ERO Shift Schedule - Engineering Group 5790-210-1 Engineering Coordinator Checklist 5790-210-2 AMT Responsibility Checklist - Operati6ns Group Leader 5790-210-3 AMT Responsibility Checklist - Assistant Operations Group Leader 5790-210-4 AMT Responsibility Checklist - Engineering Coordinator 5790-210-5 AMT Responsibility Checklist - Nuclear Engineer 5790-210-6 AMT Responsibility Checklist - SPDS Operator(s) & Trending Individual(s) 5790-213-2 Emergency Director Status Update Checklist A.7-TSG-02 Control Parameter Status Assessment A.7-TSG-03 Plant Status Assessment A.7-TSG-04 System Status Assessment A.7-TSG-05 EOP/SAMG Action Status Assessment
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
- 11.
- 12.
13.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 0 TITLE:
ENGINEERING SUPPORT IN THE TSC Revision 7 Page 17 of 17 FIGURE 7.2 Accident Management Team (AMT) Responsibilities TSC - Accident Management Team (AMT)
General Responsibilities Checklist Operations Group Leader Direct the AMT Form 5790-210-02 Recommend SAMG Actions:
-Torus Spray
- Drywell Spray
- Vent RPV
- Vent Containment
- Flood Containment Assistant Operations Group Leader SAMG Branch Determination Form 5790-210-03 Prioritize System Restoration/Repair Optimize Timing of SAMG Actions Engineering Coordinator Trend and Forecast Key Parameters Form 5790-210-04 Develop System Status Identify and Prioritize Needed Repairs Provide Plant Status to OGL Estimate RPV Injection Flow Rate Nuclear Engineer Confirm Reactor Shutdown Form 5790-210-05 Identify Fuel Damage Identify RPV Breach by Core Debris Estimate MDRIR SPDS Operator(s)
Establish Trend Charts Form 5790-210-06 Trending Individual(s)
Validate Data Evaluate/Utilize Alternate Data Sources Identify Approach to Action Limits I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 1 of 24 EMERGENCY PLAN IMPLEMENTING PROCEDURE -TABLE OF CONTENTS SECTION PW Prepared By:
Reviewed BY:
OC ReviewReq'd:
esOC Meeting Number:?3Vs, Approved By:
Dae FOR ADMINISTRATIVE USE N
This revision-iincorpora-tes v"olumeF Memos:.
y1Y--
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated.
02-2-3-71 I/mab
- .GE 2
2 2
2 3
3 1.0 PU R PO SE........................................................
2.0 APPLICABILITY...................................................
3.0 ORGANIZATION AND RESPONSIBILITIES...........................
4.0 D ISC U SSIO N......................................................
5.0 PRECAUTIO NS....................................................
6.0 INSTRUCTIO NS...................................................
6.1 Response to an Unusual Event................................
6.2 Response to an Alert (or higher)...............................
6.3 ED Activation and Staffing in the TSC...........................
6.4 Emergency Director Record-keeping 6.5 Transfer of Off-site Responsibilities.............................
6.6 TSC Status Updates and ED Briefings..........................
6.7 TSC O perations..............................................
6.8 Technical Assessment........................................
6.9 Radiological Assessment......................................
6.10 Emergency Notification Follow-up Messages....................
6.11 Emergency Classification Changes.............................
6.12 Off-site Protective Action Recommendations.....................
6.13 TSC Radiological Monitoring and Control........................
6.14 TSC Protective Actions and Evacuation.........................
6.15 Emergency Director Turnover..................................
6.16 Event Termination or Recovery.................................
7.0 FIG U R ES.........................................................
Resp Supv:
EP Assoc Ref: A2 1
2 ESRN Fre.1 / yrs ARMS:
A.2-213 Doc Type. 1060 Admin Initials:
Date 3
4 5
6 7
9 10 11 13 15 16 18 21 21 23 23 24
MONTICELLO NUCLEAR GENERATING PLANT A.2-213 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 2 of 24 1.0 PURPOSE This procedure outlines the duties and responsibilities of the Emergency Director and provides instructions and guidance for the conduct of Emergency Director activities in the Technical Support Center during a declared emergency at the Monticello Nuclear Generating Plant.
Sections of this procedure, which satisfy commitments M76060A and M90125A, are marked with a $.
2.0 APPLICABILITY 2.1 An emergency (Alert or higher classification) has been declared at the Monticello Nuclear Plant and the TSC is activated.
2.2 A designated Emergency Director has received a turnover from the Duty Shift Manager (Interim Emergency Director) and assumed the duties and responsibilities of Emergency Director.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Director is responsible for:
3.1.1 Implementation of this procedure and management of emergency response activities in the TSC.
3.1.2 Overall direction and coordination of MNGP's emergency response activities. (Prior to turnover of this responsibility to the Emergency Manager.)
3.1.3 Off-site communications with State and Local authorities and federal agencies (before turnover to the EOF).
3.1.4 Notification of new emergency classifications (prior to turnover of this responsibility to the Emergency Manager). The Emergency Director retains primary responsibility to classify or re-classify emergencies.
3.1.5 Making off-site Protective Action Recommendations (PARs) to State and/or County authorities (prior to turnover of this responsibility to the Emergency Manager).
4.0 DISCUSSION This procedure provides instructions for the various duties and responsibilities of the Emergency Director in the Monticello TSC. In some cases, this procedure references other procedures which provide more detailed instructions for the performance and coordination of Emergency Director tasks (e.g., Event Termination/Recovery).
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MONTICELLO NUCLEAR GENERATING PLANT A.2 TITLE:
RESPONSIBILITIES OFTHE EMERGENCY Revision 9 DIRECTOR Page 3 of 24 The instructions contained within each section of this procedure are presently in the "most probable" sequential order and, although presented in this sequence, they are intended to be implemented as the emergency situation dictates and as determined by the Emergency Director.
During the implementation of this procedure the Emergency Director must consider the three distinct phases in the Emergency Classification, Declaration and Notification process.
Classification: The act of assessing the EALs to determine the appropriate classification which the ongoing events are categorized. This may take a reasonable length of time (5 to 15 minutes for most situations) depending upon the complexity of the situation. This 15 minute assessment period is consistent with the NRC Branch Position on Timeliness of Classification of Emergency Conditions, EPPOS No. 2.
Declaration: The act of formally declaring the classification based on the assessment of EALs. This is the point at which the classification time is set and the 10CFR50, App. E 15 minute off-site notification clock starts.
Notification: The act of making the notification(s) to the State, Wright and Sherburne Counties, NRC, etc.
5.0 PRECAUTIONS 5.1 When transferring off-site responsibilities from the TSC to the EOF, the various functions should be transferred simultaneously due to their inter-dependence (i.e., transferred as a package, at the same time, and not independently).
5.2 Emergency classification changes and Off-site Protective Action Recommendations (when made) SHALL be transmitted to the State and Counties within 15 minutes.
6.0 INSTRUCTIONS 6.1 Response to an Unusual Event
$ 6.1.1 When contacted by the Duty SEC, obtain a general description of the event including the following information (if applicable):
A.
The cause of the event and immediate corrective actions taken.
B.
Plant status before (and after) the event occurred (e.g.,
operating, shutdown, reduced power, etc.).
C.
On-site personnel status (e.g., injuries, contaminations, over exposures).
D.
If the event involves any radioactive releases above allowable limits.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-2 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 4 of 24 E.
Status of off-site notifications to State, Counties, NRC and whether the event warrants additional individual/organization notifications in accordance with 4 AWI-04.08.01 (EVENT NOTIFICATIONS).
6.1.2 The SEC will ask if (precautionary) notification of a Radiological Emergency Coordinator (REC) is necessary. Instruct the SEC to contact a REC if (in your opinion) the event involves or has significant potential to involve off-normal radiological consequences. The duty Shift Manager or Control Room Supervisor may be consulted to make this determination.
6.1.3 If located at the plant, consider responding to the Control Room, Work Execution Center Office or TSC (if warranted). If located off-site, provide the Duty SEC with the telephone (or pager) number at which you can be contacted (if you will not be reporting to the Plant).
NOTE: There is no requirement that the Emergency Director report to the Plant during a NUE 6.1.4 Maintain a heightened state of awareness throughout the event. If conditions degrade, respond accordingly. If the emergency classification escalates (to Alert or higher) refer to Section 6.2 of this procedure.
6.2 Response to an Alert (or higher) 6.2.1 Upon receipt of the Alert declaration (via PA announcement or pager activation) all designated Emergency Directors should report immediately to the TSC.
6.2.2 Upon arrival, refer to the TSC ERO Tag Board and determine the initial Emergency Director assignment as follows:
A.
If no one has assumed the ED position turn the ED tag and sign-in as Emergency Director.
B.
If the Plant Manager is present, he/she should assume the duties of Emergency Director.
C.
If the Plant Manager is not present, another qualified, designated Emergency Director should assume the duties until relieved by the Plant Manager.
D.
Read the ED task tag and turn it over, and sign-in to indicate the ED position is filled.
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MONTICELLO NUCLEAR GENERATING PLANT
-"j f.
A.2-21 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 5 of 24 6.2.3 Report to the Control Room for the most recent update of plant status and the turnover of Emergency Director responsibilities from the Duty Shift Manager.
A.
Upon assumption of Emergency Director duties, remain in the Control Room until the TSC reaches minimum staffing levels as identified in A.2-106 (ACTIVATION AND OPERATION OF THE TSC).
B.
Contact the TSC to determine if the following personnel are available in the TSC to meet minimum staffing criteria.
- 1. REC
- 2.
Lead SEC or EC
- 3.
Mechanical Engineer
- 4.
Electrical Engineer
- 5.
Nuclear Engineer 6.2.4 Report to the TSC when minimum staffing levels have been met.
6.3 ED Activation and Staffing in the TSC 6.3.1 Initiate Form 5790-213-01 (EMERGENCY DIRECTOR ACTIVATION CHECKLIST).
6.3.2 If necessary, establish contact with the Control Room (Shift Manager or Communicator) to determine any changes in plant status and emergency response actions in-progress. The Operations Group Leader (when staffed) will assume this duty.
6.3.3 Ensure the following key TSC emergency positions are being staffed (by qualified personnel). If any of the positions remain unfilled (after about 30 minutes) direct the Lead Emergency Communicator (EC) to contact qualified personnel (refer to 5970-001 -01 (EMERGENCY RESPONSE ORGANIZATION) to identify qualified candidates and the Monticello and Prairie Island Nuclear Emergency Telephone Directory for home/office/pager telephone numbers):
A.
Support Group Leader (TSC Coordinator)
B.
Operations Group Leader (OGL)
C.
Radiological Emergency Coordinator (REC)
D.
Engineering Group Leader (EGL)
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MONTICELLO NUCLEAR GENERATING PLANT A.2-213 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 6 of 24 E.
Maintenance Group Leader (MGL)
F.
Security Group Leader (SGL) 6.3.4 As TSC staffing progresses, begin assessing the event using available information from the following sources:
A.
Periodic discussions with the TSC Group Leaders.
B.
Review of completed EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE FORM(S), and OFF-SITE PROTECTIVE ACTION RECOMMENDATION FORM(S) generated by the REC (or transmitted from the EOF after off-site communications is turned-over).
C.
Review of critical plant parameters, plant process monitor and in-plant radiological data from SPDS.
D.
(CR-TSC-OSC-EOF) Technical Communicator link information being posted on Operation Status Board.
E.
TSC/EOF counterpart communications (e.g. REC/RPSS, Engineering Group Leader/Tech Support Supervisor, etc.) when the positions are staffed.
6.3.5 Continuously, during the course of the emergency, perform the duties of Emergency Director in accordance with the applicable section(s) of this procedure.
6.4 Emergency Director Record-keeping 6.4.1 Upon activation initiate the Emergency Director Log book.
6.4.2 When TSC Support Group staff are available, designate (or have the Support Group Leader assign) an individual to perform the duties of Emergency Director Recorder (ED Recorder) and maintain the Emergency Director Log. When staffed, the ED recorder should be positioned near the Emergency Director to facilitate the flow of information in a timely and accurate fashion.
6.4.3 Record significant events and make other entries into the Emergency Director Log in accordance with the following criteria:
A.
Significant events and the time(s) which they occur including changes in plant conditions, radiological releases, and adverse plant parameter trends.
B.
The general context of reports made to the Emergency Director and/or discussions (in-person and telephone) between the ED and other personnel (including the NRC, if present).
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MONTICELLO NUCLEAR GENERATING PLANT
-,A.23 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9
!2 tDIRECTOR Page 7 of 24 C.
Emergency notifications (e.g. Classification changes, Off-site Protective Action Recommendations) and the time(s) the notification forms were approved.
D.
Summarize major decisions made by the Emergency Director including the time the decision was communicated and its basis.
6.4.4 Periodically monitor the distribution of completed, approved forms in Sthe TSC (specifically to the ED and NRC) to ensure prompt dissemination of information (orms control and distribution is the responsibility of the Support group Leader).
6.4.5 Ensure all completed forms are filed in the appropriate container provided and retained as emergency records.
6.5 Transfer of Off-site Responsibilities When transferring off-site responsibilities from the TSC to the EOF, the various functions should be transferred simultaneously due to their inter-dependence (i.e.,
transferred as a package, at the same time, and not independently).
6.5.1 When the EOF is operational consider transfer of the following responsibilities from the TSC to the EOF:
A.
Performance of off-site dose projection (MIDAS) activities.
B.
Coordination of off-site radiological monitoring teams (including the Field Teams and Sample Couriers) for the purpose of MIDAS results comparison and validation.
C.
Off-site communications including the issuance and transmittal of the following emergency forms:
- 1.
EMERGENCY NOTIFICATION REPORT FORMS (for re-classification of the emergency and PARs at a General Emergency).
- 2.
EMERGENCY NOTIFICATION FOLLOW-UP MESSAGES (generated by MIDAS and issued periodically to the State Emergency Operations Center (EOC) Planning and Assessment Center (PAC)).
- 3.
OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLISTS (for off-site protective action recommendations based on projected dose).
D.
Responsibility for emergency class declaration and notification.
(This responsibility is assumed by the Emergency Manager concurrent with the responsibility for off-site communications).
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MONTICELLO NUCLEAR GENERATING PLANT A.2 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 8 of 24 6.5.2 Consult with the Emergency Manager regarding the transfer of off-site responsibilities. Suggest the Emergency Manager consult with the Radiation Protection Support Supervisor (RPSS) regarding the transfer.
6.5.3 Consult with the Radiological Emergency Coordinator (REC) and direct the REC to confer with the RPSS on the proposed transfer.
NOTE:
If possible, the transfer should be conducted when no off-site communications are being processed by the TSC (e.g. Follow-up Messages, etc.)
6.5.4 Direct the Lead EC and REC to prepare to transfer responsibility for off-site communications to the EOF.
6.5.5 When all parties are prepared, transfer responsibility for off-site communications (and other off-site related activities outlined in 6.5.1) and make an announcement to that effect in the TSC.
6.5.6 Confirm successful completion of the transfer with the REC and Lead EC.
6.5.7 Direct the ED Recorder to record the transfer of off-site responsibilities to the EOF in the ED Log.
6.5.8 In the event of an EOF evacuation or if other circumstances dictate, transfer the responsibility for off-site communications (specified in 6.5.1) back to the TSC by reversing the transfer process outlined in this section.
6.5.9 If (due to EOF evacuation or other circumstances) the responsibilities for off-site communication are transferred back to the TSC:
A.
Direct the Lead EC to immediately contact the appropriate State and County authorities and inform them that the TSC has assumed responsibility for off-site communications.
B.
Upon completion of the transfer, consider conducting a briefing in the TSC which includes a status report in the following areas:
- 1.
MIDAS operational status including the latest dose projection results.
- 2.
Off-site Monitoring team status including locations and recent survey results.
- 3.
Estimate of when the next EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE will be prepared for review (first follow-up transmission from the TSC).
- 4.
Status of notifying the State and counties of the transfer of off-site responsibilities.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 9 of 24
- 5.
The status of State and County EOC activations (i.e., which EOCs are staffed and operational and which are not).
- 6.
Communications equipment operational status including the status of any transmissions currently in progress.
C.
Review, approve and issue the various forms used for off-site emergency communications in accordance with the applicable section of this procedure.
6.6 TSC Status Updates and ED Briefings 6.6.1 During initial TSC activation and staffing, make periodic status announcements in the TSC which include:
A.
The current emergency classification.
B.
A narrative summary of the event (when known) including emergency response actions underway or planned and the present status of the reactor.
C.
The status of any on-site or off-site protective actions taken or initiated (e.g., plant evacuation, etc.)
D.
The Fitness-for-Duty verification of personnel responding to the TSC (during off-hours activation only).
6.6.2 Announce significant events in the TSC as they occur (versus waiting for a formal status update). For important events, such as significant increases in radiological release rates, etc. ensure all personnel in the TSC are aware of the occurrence.
6.6.3 During routine TSC operation, conduct periodic status updates (about every 30 minutes) as follows:
A.
Prior to the update, make an announcement in the TSC that an update will be conducted in 1-5 minutes. This will allow key TSC personnel time to prepare their input.
B.
Initiate Form 5790-213-02 (EMERGENCY DIRECTOR STATUS UPDATE CHECKLIST). Record the date and time of the status update on the form.
C.
Announce the beginning of the update in the TSC and request personnel keep background noise (in the TSC) to a minimum during the entire update.
D.
Using Form 5790-213-02 (as a guide) conduct the update.
E.
As personnel provide status reports in their respective area(s) note significant items and ask questions to ensure the current status is understood (Form 5790-213-02 may be used for notes).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-213 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 10 of 24 F.
If the NRC is present (in the TSC) they should provide their status reports (in each functional area) immediately after their MNGP counterpart.
G.
Upon completion of the status update announce the estimated time of the next scheduled update in the TSC.
H.
Direct the ED Recorder to note the update in the Emergency Director Log and retain the completed EMERGENCY DIRECTOR STATUS UPDATE CHECKLIST as emergency records.
6.6.4 Upon completion of TSC status update(s) contact the Emergency Manager in the EOF command center and provide a status report (with current information obtained during the TSC update).
6.6.5 Ensure the TSC Group Leaders update their personnel (e.g. OSC, Control Room, Access Control, etc.) with current information obtained during the TSC status update.
6.6.6 Direct the Lead Emergency Communicator to conduct periodic general status announcements in the Plant, and Site Administration Building via the PA system. The announcements should include the following information (if applicable):
A.
The current emergency classification and status of the plant (reactor).
B.
The extent of any off-site radiological releases and status of on-site and off-site protective actions taken.
C.
The habitability of the occupied areas including general area dose rates (if applicable).
6.6.7 If the need arises for private conference(s) outside the TSC (e.g., with NRC officials, ED turnover briefings, etc.) the NRC Conference Room (immediately outside the Command Center) or the Back-up OSC may be used if not occupied.
6.7 TSC Operations
$ 6.7.1 If off-site agencies or organizations respond to the TSC (e.g., NRC, State Health Department, etc.) direct the Support Group Leader to serve as the liaison for these organizations.
$ 6.7.2 Serve as the utility "point-of contact" for senior off-site officials present in the TSC (e.g., NRC Director of Site Operations, Site Team Leader, etc.) and:
A.
Include the officials in TSC Status Updates, Emergency Director briefings, discussions and ED turnover activities.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 11 of 24 B.
Confer with the officials on formulation of off-site protective action recommendations (if the EOF has not assumed this responsibility).
C.
Ensure the officials receive copies of completed forms and transmittals distributed in the TSC.
6.7.3 If radiological controls and/or protective actions are required in the TSC (e.g., transfer of TSC access, use of PCs, etc.) ensure the necessary actions are initiated in accordance with the applicable section(s) of this procedure.
6.7.4 Conduct periodic status dpdates in the TSC throughout the emergency in accordance with Section 6.6 of this procedure.
6.7.5 When the criteria for event termination or recovery are met direct the Support Group Leader to coordinate compiling the short-term and long-term recovery action lists developed by the TSC Group Leaders.
6.8 Technical Assessment 6.8.1 Direct the Engineering Group Leader to perform engineering and operational assessments of the event in accordance with EPIP A.2-21 0
"(ENGINEERING SUPPORT IN THE TSC) and:
A.
Continuously monitor critical plant parameters and indications (using SPDS and Technical Communicator link).
B.
Continuously man the EOF-OSC-TSC-CR Technical communications link and maintain the Operational Status Board in the TSC.
C.
Trend selected plant parameters critical to the event to determine adverse trends and predict (or anticipate) plant transients or potential releases (e.g., containment pressure, etc.)
D.
Evaluate the engineering and operational aspects of the event including the assessment of inoperable components and/or systems critical to accident mitigation and the determination of alternative methods or corrective actions to restore those capabilities.
6.8.2 Direct the Engineering Support Group to serve as the liaison (or primary contact) with off-site engineering and technical vendors and services required by the TSC (e.g. General Electric Emergency Support, A/E vendor, etc.) until the EOF is activated.
3/4...
6.8.3 If 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing is required, direct the Engineering Group Leader to coordinate the establishment of a ERO shift schedule for the TSC Engineering Staff with the Support Group Leader.
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MONTICELLO NUCLEAR GENERATING PLANT TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 1
DIRECTOR Page 12 of 24 6.8.4 Direct the Engineering Staff to continuously compare plant parameters, indications, events and trends with the Emergency Action Levels (EALs) contained in EPIP A.2-101 (CLASSIFICATION OF EMERGENCIES) and to make recommendations on classification changes immediately upon verification of indications.
6.8.5 Ensure the TSC Engineering Staff continuously mans the Emergency Notification System (ENS) link with NRC Headquarters (when required) and provides technical and operational information to the NRC as requested.
6.8.6 Direct the Engineering Group Leader to provide a status report on engineering and operational assessment during TSC status updates.
6.8.7 Direct the Engineering Group Leader to coordinate providing technical support to the TSC for the evaluation of inoperable systems or components, related to accomplishing accident mitigation objectives, and the determination of alternate methods to accomplish those objectives.
6.8.8 Ensure the Engineering Staff maintains a list of inoperable components, systems and/or facility damage identified throughout the event. When the criteria for event termination (or recovery) are met, direct the Engineering Group Leader to coordinate the development of short-term and long-term recovery item lists identifying those tasks required to return the plant (and/or immediate site) to a pre-accident state.
6.8.9 If applicable, ensure the TSC Engineering Staff and the Operations Group Leader follows the implementation of the EOPs (by the Control Room) to predict significant operational evolutions (e.g., containment venting) and verify proper EOP implementation.
6.8.10 If the Control Room indicates that Severe Accident Management Guidelines (SAMGs) have been entered, take the following steps:
A.
Direct the Operations Group Leader to assume the SAMG Decision Maker responsibilities.
B.
Direct qualified personnel to assume their SAMG Evaluator responsibilities.
C.
Ensure that SAMG Implementors (Control Room and OSC personnel) carry out their duties as directed by the Operations Group Leader.
D.
Announce the transition to the Severe Accident Management Guidelines in the TSC and ensure that the EOF is made aware of the transition.
E.
Monitor the activities of the SAMG Group and provide management support and/or assistance as requested.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-211 TITLE:
RESPONSIBILITIES OFTHE EMERGENCY Revision 9 DIRECTOR Page 13 of 24 6.9 Radiological Assessment 6.9.1 Direct the Radiological Emergency Coordinator (REC) to coordinate the activities of the Radiation Protection staff including:
A.
The coordination of RP Group staffing and emergency response activities in accordance with EPIP A.2-209 (RESPONSIBILITIES OF RADIOLOGICAL EMERGENCY COORDINATOR).
B.
Radiological accident assessment including the coordination of off-site dose projections, dose assessment and the formulation of off-site Protective Action Recommendations in accordance with EPIP A.2-204 (OFF-SITE PROTECTIVE ACTION RECOMMENDATIONS).
C.
Radiological habitability monitoring and control in the Plant including the formulation of protective action recommendations for Plant personnel in accordance with EPIP A.2-201 (ON-SITE PROTECTIVE ACTION).
6.9.2 Ensure the REC implements radiological monitoring and controls at the plant. Refer to Section 6.13 for Emergency Director instructions regarding:
A.
Radiological monitoring and control at the Plant.
B.
Establishment of Control Room EFT and TSC Emergency Ventilation System Boundaries.
C.
Plant habitability and protective actions for ERO personnel.
D.
Emergency exposure authorizations for ERO personnel.
6.9.3 Ensure the Radiation Protection Group continuously performs off-site dose projections throughout the event and formulates off-site protective action recommendations (as necessary). Refer to Section 6.12 of this procedure for Emergency Director instructions regarding the formulation and issuance of off-site protective action recommendations.
6.9.4 If 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing is required, direct the REC to coordinate the establishment of a ERO shift schedule for the Plant Radiation Protection Group with the Support Group Leader.
6.9.5 Direct the Radiation Protection Group to continuously monitor and compare actual (and potential) radiological releases (e.g. release rate, etc.) indications, events and trends with the Emergency Action Levels (EALs) contained in EPIP A.2-101 and to make recommendations on classification changes based on radiological conditions.
6.9.6 Direct the REC Assistant to continuously update the Radiological Status Board in the TSC using data from approved Emergency Notification Follow-up Messages and other appropriate sources.
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MONTICELLO NUCLEAR GENERATING PLANT A.2 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 14 of 24 6.9.7 Direct the REC to provide a status report on radiological assessment, meteorological conditions and plant habitability during TSC status updates.
6.9.8 When the REC submits Form 5790-102-03 (EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE) for approval, process the form in accordance with Section 6.10 of this procedure.
6.9.9 If making a change in emergency classification, review and approve Form 5790-102-02 (EMERGENCY NOTIFICATION REPORT FORM),
submitted by the REC, in accordance with Section 6.11 of this procedure.
6.9.10 If (and when) the REC submits Form 5790-204-01 (OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST) for approval, process the form in accordance with Section 6.12 of this procedure.
6.9.11 Ensure the Radiation Protection Group continuously mans the Health Physics Network (HPN) link with the NRC (when required) and provides radiological and meteorological information to the NRC as requested.
6.9.12 If the plant conducts a Site Evacuation (or removal of non-essential personnel from the site following a Plant Evacuation) direct the REC to coordinate the procession of evacuees from the site with the RPSS (and off-site authorities if off-site protective actions such as evacuation or sheltering have been implemented).
6.9.13 If habitability, environmental radiological conditions or other conventional hazards dictate, consider implementation of protective actions for ERO personnel based on REC recommendations. Refer to Section 6.14 of this procedure for Emergency Director instructions regarding personnel protective actions including:
A.
Use of protective anti-contamination clothing.
B.
Issuance and use of Potassium Iodide (KI) for ERO personnel.
C.
Emergency exposure authorizations (in excess of MNGP or NRC Limits).
D.
Plant or Site evacuation.
6.9.14 When the criteria for event termination or transition to Recovery is met direct the REC to coordinate the development of recovery item list(s) which identify short-term and long-term radiological considerations to be taken into account during the recovery phase.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-213 TITLE:
RESPONSIBILITIES OFTHE EMERGENCY Revision 9 DIRECTOR Page 15 of 24 6.9.15 If off-site radiological releases have occurred (in excess of ODCM limits) and when significant releases have been terminated consider increasing the frequency (and scope) of the MNGP Radiological Environmental Monitoring Program (REMP). Direct the REC to contact the RPSS to initiate REMP activities.
6.10 Emergency Notification Follow-up Messages NOTE: Emergency Notification Follow-up Message Forms are generated by computer (MIDAS) and transmitted to the State EOC PAC to aid in their dose projection calculations. Follow-up Messages should be issued about every 30 minutes and/or when significant changes in emergency classification, plant conditions or radiological releases occur.
6.10.1 Upon receipt of an Emergency Notification Follow-up Message (from the REC) review the form for completeness and:
A.
Note the date and time (at the top of Page 1) which indicates when the form was generated by MIDAS (question the REC on the issuance of follow-up messages that are more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> old).
B.
Ensure the proper (current) emergency class is indicated.
C.
Note the wind direction and affected sectors indicated on the form. Briefly compare the affected sectors and/or wind direction to those previously indicated to determine if new affected sectors are identified (due to wind shifts).
D.
Review the projected integrated dose section (bottom of Pagel) to determine if any projected off-site dose exceeds the Protective Action Guides (PAGs). If so, discuss the formulation of Off-site Protective Action recommendations, based on projected dose, with the REC.
6.10.2 If the NRC is present (in the TSC) briefly review the completed form with your NRC counterpart (if available) before issuing the form.
6.10.3 Discuss any questions regarding the information on the form with the REC.
6.10.4 Upon completion of the review (and when satisfied that the information contained on the form is accurate) sign, date and time the form (at the bottom of Page 2).
6.10.5 Either return the signed form to the REC (with instructions to have it transmitted) or forward the form delivered to the Lead EC for transmittal.
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IMONTICELLO NUCLEAR GENERATING PLANT A
A2-21 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 16 of 24 6.11 Emergency Classification Changes I Emergency classification changes SHALL be transmitted to the State and Counties within 15 minutes.
6.11.1 Classification -When informed of plant parameters, radiological release levels or events which indicate that a change in emergency classification may be appropriate evaluate the emergency classification change as follows:
A.
Confirm that the indications have been verified using redundant or coincidence indications.
B.
Review the applicable guideline(s), initiating condition(s) and Emergency Action Level(s) (EALS) in EPIP A.2-101 to determine the appropriate emergency class (if not already done by the TSC or EOF staffs).
C.
If multiple events and/or indications are involved re-classify the emergency based on the event (or indication) that results in the highest (most conservative) emergency classification.
D.
Consider the effect that combinations of events have, that, if taken individually, would constitute a lower emergency classification but collectively may exceed the criteria for a higher classification.
6.11.2 Make an announcement in the TSC that a change in emergency classification is being considered. If the TSC has responsibility for off-site communications, instruct TSC personnel to prepare for processing a classification change.
NOTE: The preliminary announcement of a potential classification change will aid the REC and Emergency Communicators in preparing to make the required 15 minute notifications to the State and Counties when the declaration occurs.
6.11.3 Confer with the TSC Group Leaders and Emergency Manager (if not already done) regarding the proposed change in emergency class.
6.11.4 If the NRC is present (in the TSC) review the proposed classification change with your NRC counterpart (this review is for information only and not to obtain concurrence).
6.11.5 If the evaluation outlined above has been completed (indicating a change in emergency classification is warranted) re-classify the emergency.
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MONTICELLO NUCLEAR GENERATING PLANT
ý',
A.2-213 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 17 of 24 6.11.6 Declaration - Declare the emergency class as follows:
A.
If the EOF has not assumed responsibility for off-site communication, then declare the emergency class.
- 1. Announce the new emergency classification in the TSC.
- 2.
Inform the REC of the new emergency class and the time of declaration.
- 3.
Ensure the new emergency classification is announced on the site PA system (Access #305)
B.
If the EOF has assumed responsibility for off-site communication immediately inform the Emergency Manager (EM) of the classification change. The EM is responsible for declaration and off-site notifications.
- 1. Announce the new emergency classification in the TSC.
6.11.7 Notification - If the EOF has not assumed responsibility for off-site notifications, make the off-site notifications as follows:
A.
Instruct the REC to complete Form 5790-102-02 indicating the new emergency classification and submit the form for review and approval.
CAUTIN B.
Review the completed Emergency Notification Report Form and:
- 1.
Verify the appropriate emergency classification is indicated.
- 2.
Verify the time of the emergency classification.
- 3.
If the new emergency class is a General Emergency, verify Off-site Protective Action Recommendations are specified on the form. Prior to (or simultaneously with) its transmittal, a telephone call should be initiated (by the ED or REC) to the Planning Chief (at State EOC PAC) to explain the basis for the recommendations (refer to Section 6.12 of this procedure for additional instructions).
- 4.
Sign the form in the space provided.
I/mab If the new emergency classification is General Emergency, Off-site Protective Action Recommendations are required and should be specified on the Emergency Notification Report Form which transmits the classification change.
MONTICELLO NUCLEAR GENERATING PLANT A.2 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 18 of 24 C.
Forward the approved Emergency Notification Report Form promptly to the Lead EC for immediate transmittal to the State and Counties (within 15 minutes of the re-classification).
6.11.8 Direct the TSC Emergency Communicators to announce the new emergency classification on the site PA system.
6.11.9 Direct the ED Recorder to record the emergency re-classification in the ED Log Book.
6.11.10 Ensure the new emergency classification is posted on the Organization Status Board in the TSC.
6.11.11 Direct the Lead EC to complete Form 3195 (EVENT NOTIFICATION WORKSHEET) reflecting the classification change and submit the completed form for review and approval.
6.11.12 Upon receipt of the completed Form 3195:
A.
Review the form for completeness.
B.
Sign, date and time the form in the space provided (SM signature box).
C.
Promptly return the approved form to the Lead EC with instructions to transmit the information to NRC Headquarters (via the ENS) immediately following state and local notifications and not to exceed one hour of the classification change.
6.12 Off-site Protective Action Recommendations 6.12.1 Continuously project off-site doses throughout the duration of the event (Integrated Dose section of the Emergency Notification Follow-up Message).
6.12.2 Direct the REC to formulate Off-site Protective Action Recommendations based on the following:
A.
Projected off-site dose(s) compared to MNGP Conservative Protective Action Guides (PAGs).
'CAUTION,.
Off-site Protective Action Recommendations SHALL be transmitted to the State and Counties within 15 minutes.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 19 of 24 6.12.3 Transmit Off-site Protective Action Recommendations (PARs) using the following forms:
A.
Off-site Protective Action Recommendations made (required) upon declaration of a General Emergency should be specified on Form 5790-102-02 and transmitted with the emergency classification change notification (within 15 minutes of the GE declaration).
B.
Off-site Protective Action recommendations made based on projected doses should be specified on Form 5790-204-01.
6.12.4 When the REC submits off-site protective action recommendations review the applicable form and:
A.
Verify the form is complete.
If protective actions are being recommended for subarea 5N, protective actions required for Sherco Plant personnel (located in the southwest corner of 5N) should be discussed with the Utility Management.
B.
Note the affected sectors (A-R) and affected Sub-Areas (e.g., 2, 5E, 5N, etc.) identified on the form.
6.12.5 Briefly discuss the basis for the recommendations with the REC, NRC (if present), and State or County authorities. Consider review of the following information as necessary:
A.
The Emergency Notification Follow-up Message (or MIDAS printout) which projected off-site doses exceeding the PAGs.
B.
The current (or forecast) meteorological conditions (e.g. wind shifts) which affect the recommendation.
C.
Identify population centers affected by the recommendations including:
- 1. When the population will be affected based on plume direction, wind speed, etc.
- 2.
Evacuation time estimates for the affected population.
- 3.
Special groups or facilities within the affected population of area that may require special consideration (e.g., hospitals, nursing homes, etc.).
D.
Review the protective actions required for Sherco Plant personnel if the recommendations include Subarea 5N.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-213 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 20 of 24 6.12.6 When the basis for the recommendations is understood sign, date and time the form in the space provided.
6.12.7 Determine who (Emergency Director or REC) will contact the State EOC PAC to explain the basis for the recommendations.
6.12.8 Promptly either return the signed form to the REC with instructions to have it transmitted to the State (or Counties prior to State EOC Activation).
6.12.9 Prior to (or simultaneous with) the transmittal of Off-site Protective Action Recommendations to the State ensure a call is initiated (by the ED or REC) to the State EOC PAC to explain the basis for the recommendations.
6.12.10 If the recommendations include Subarea 5N contact Generation management to determine the best course of action regarding the Sherco Plant in accordance with the criteria in EPIP A.2-204.
6.12.11 Ensure the protective action recommendations made are indicated on the Radiological Status Board in the TSC.
6.12.12 Ensure the EOF (Emergency Manager),and JPIC are informed of the off-site protective action recommendations being made.
6.12.13 Ensure the REC informs the NRC regarding the off-site protective actions via the HPN system.
6.12.14 Direct the ENS Technical Communicator to inform NRC Headquarters of the off-site protective actions via the ENS.
6.12.15 Direct the REC to monitor and follow-up on the implementation of the recommendations (with the State) and indicate the status of implementation on the status board and PAR Map in the TSC.
6.12.16 Periodically check on the status of protective action implementation. If, after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, protective actions have not been initiated (e.g. PANS activated) direct the REC to contact the State and determine the status of initiating protective actions.
6.12.17 If the protective actions actually implemented are different than those recommended ensure the EOF and JPIC are promptly informed of the protective actions taken.
6.12.18 Direct the REC to continue with off-site dose assessment and formulate subsequent off-site protective action recommendations based on projected dose and MNGP Protective Action Guides (PAGs).
6.12.19 Issue additional off-site protective action recommendations (as necessary) in accordance with the instructions in this section.
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MONTICELLO NUCLEAR GENERATING PLANT A.2 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 21 of 24 6.13 TSC Radiological Monitoring and Control 6.13.1 Ensure the REC continuously monitors radiological conditions in the TSC and immediate environs by:
A.
Conduct of periodic habitability surveys in occupied areas of the TSC, Control Room, OSC, Access Control and Security Building.
B.
Operation of the PIOPS CAM immediately outside the TSC by the elevator.
C.
Operation of the portable DARM in the TSC.
6.13.2 Ensure all TSC personnel are issued dosimetry which is periodically checked (prompt TSC personnel during briefings).
6.13.3 If personnel exposures approach MNGP annual administrative limits (2000 mrem TEDE) direct the REC to evaluate exposures and provide recommendations in accordance with EPIP A.2-401 (EMERGENCY EXPOSURE CONTROL), including:
A.
Evacuation of less essential ERO personnel.
B.
Logging of exposures and rezeroing dosimeters or issuance of "high range dosimetry to essential personnel.
C.
Authorization of emergency exposures (up to 5 rem TEDE) for essential personnel.
6.13.4 If significant releases are occurring (in excess of the Alert levels specified in EPIP A.2-1 01 ensure the REC coordinates the establishment of EFT and EVS boundaries.
6.13.5 If (and when) loose surface contamination levels exceed 1 OOODPM/100CM 2, ensure the REC establishes strict contamination control measures for the EFT and EVS boundaries in accordance with A.2-402 (ON-SITE RADIOLOGICAL MONITORING).
6.14 TSC Protective Actions and Evacuation 6.14.1 If elevated contamination levels are detected in the uncontrolled areas of the Plant, consider implementing the following protective actions based on REC recommendations.
A.
Direct the REC to post and control contaminated areas (and decontaminate if possible).
B.
Consider protective clothing use in the TSC.
C.
Ensure the REC (and TSC Radiation Protection staff) initiate strict contamination control measures including monitoring of food stuffs, etc. prior to consumption.
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MONTICELLO NUCLEAR GENERATING PLANT A.2 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 T
DIRECTOR Page 22 of 24 D.
Direct the REC to initiate personnel decontamination procedures, as necessary. Personnel may need to be sent to Access Control or the EOF for decontamination.
E.
Consider relocation of the OSC (to the backup OSC).
6.14.2 If elevated radiation levels exist in the Plant, consider implementing the following protective actions based on REC recommendations.
A.
Evacuation of non-EFT or EVS boundary areas of the Plant.
B.
Evacuation of non-essential personnel from the Site.
C.
Initiate exposure tracking and emergency exposure authorizations for essential TSC personnel.
6.14.3 If elevated airborne radiation levels exist in the TSC, consider implementing the following protective actions based on REC recommendations.
A.
Evacuation of non-EFT or EVS boundary areas of the Plant.
B.
Evacuation of non-essential personnel from the Plant.
C.
Initiate tracking of DAC Hours and emergency exposure authorizations for essential TSC personnel.
6.14.4 If thyroid doses of ERO personnel are projected to exceed 25 rem TEDE (FDA recommended level for KI use), consider issuance of Potassium Iodide (KI) to essential personnel (including Field Teams) and evacuation of non-essential ERO personnel.
6.14.5 If the TSC becomes uninhabitable for any reason, then:
A.
The Emergency Director should relocate to the Control Room.
B.
TSC staff should relocate to the EOF, Backup EOF or as directed by the ED.
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MONTICELLO NUCLE=AR GENERATING PLANT
,-1 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 T
DIRECTOR Page 23 of 24 6.15 Emergency Director Turnover 6.15.1 Upon arrival at the TSC the on-coming Emergency Director should initiate a Form 5790-213-03 (EMERGENCY DIRECTOR TURNOVER CHECKLIST) and complete the turnover in accordance with the checklist instructions.
6.16 Event Termination or Recovery 6.16.1 Continue to assess plant and environmental conditions throughout the event. When all of the following criteria are met consider termination of the emergency or the transition to the Recovery Phase:
A.
The plant is in a stable condition with at least one fission product barrier intact.
B.
No radioactive releases are being made to the environment in excess of plant ODCM limits.
C.
The potential for future degradation of plant conditions is small.
6.16.2 When the above conditions are satisfied, implement the applicable Section(s) of EPIP A.2-602 (EVENT TERMINATION OR RECOVERY).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-21 TITLE:
RESPONSIBILITIES OF THE EMERGENCY Revision 9 DIRECTOR Page 24 of 24 7.0 FIGURES None I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 IEMERGENCY Page 1 of 12 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION PA 1.0 PU R PO SE........................................................
2.0 APPLICABILITY...................................................
3.0 ORGANIZATION AND RESPONSIBILITIES...........................
4.0 D ISC USSIO N......................................................
5.0 PRECAUTIO NS....................................................
6.0 INSTRUCTIO NS...................................................
6.1 G eneral Instructions..........................................
6.2 Initial Notifications for a NUE..................................
6.3 Initial Notifications for Alert/SAE/General Emergency.............
6.4 Emergency Classification Changes.............................
6.5 Off-site Protective Action Recommendations.....................
6.6 Emergency Notification Follow-up Messages....................
6.7 Secondary (optional) Notifications..............................
6.8 Emergency Call Log Instructions................................
$ 6.9 Emergency Response Data System (ERDS) Activation and Term ination..................................................
7.0 FIG U R ES.........................................................
,GE 2
2 2
2 3
4 4
4 5
5 7
9 10 11 11 12 Prepared By:
Reviewed By:
AT OC Review Req'd: 'YES OC Meeting Number:
o-,
Approved By:
/
Date
////*, 2 FORUAMINISTRATI~VE P ONLY This revision incorporates Volume F Memos:
'U4" Yv-'
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:,.6'Q - 3 3 SL,'
Resp Supv EP lAssoc Ref. A.2 I
- SRý N I Frec" 1 Airs I ARMS
A 2-501 gDoc Type: 1060 1 Admin Initials:;,.
I Date:!-
k---
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 2 of 12 1.0 PURPOSE The purpose of this procedure is to provide instructions and guidance to the Emergency Communicators for the performance of off-site communications during an emergency at the Monticello Nuclear Generating Plant.
2.0 APPLICABILITY 2.1 An emergency (Unusual Event classification or higher) has been declared at the Monticello Nuclear Generating Plant and the Emergency Director (Shift Manager until relieved) has directed that emergency notification be made.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Director is responsible for:
3.1.1 Overall direction and control of emergency response activities including off-site emergency notifications.
3.2 The Duty Shift or Lead Emergency Communicator is responsible for:
3.2.1 Implementation of this procedure under the direction of the Emergency Director.
3.2.2 Coordination of off-site emergency notifications made from the plant during an Unusual Event or higher emergency classification.
3.3 Emergency Communicators are responsible for:
3.3.1 The conduct of off-site communications, during an emergency condition, under the direction of the Lead Emergency Communicator.
4.0 DISCUSSION The duty Shift Emergency Communicator (SEC) should initially assume the role of Lead Emergency Communication (EC) if an Alert classification (or higher) is declared.
The Lead EC is responsible to ensure initial emergency notifications, Emergency Notification Follow-up Messages, emergency classification changes and protective actions recommendations are properly communicated to off-site authorities under the direction of the Emergency Director (duty Shift Manager). Once initial notifications are complete and the Lead EC responsibilities have been turned over to another EC, then the duty SEC should assume his/her Emergency Response position.
During the course of an emergency the need to contact the off-site support organizations (that are not contacted in the initial notification process) may arise. If and when directed to contact other off-site organizations, the "secondary notification" list should be used for these optional notifications.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 3 of 12 5.0 PRECAUTIONS 5.1 The initial notification of State and County must be completed within 15-minutes after declaration of an emergency. The initial notification of the NRC should be completed immediately after other notifications and must be completed within one (1) hour after declaring an emergency (reference 10CFR50, Appendix E).
5.2 All inquiries from the news media and/or general public should be directed to the Joint Public Information Center (JPIC) at the State Emergency Operations Center (EOC). Emergency response organization personnel should not release information to the media or general public without prior approval of the Chief Nuclear Officer or designee.
5.3 Communications regarding the existence or severity of the event, or protective action recommendations should be made on circuits which cannot be readily intercepted by persons outside the established emergency organizations.
Telephone circuits SHALL serve as the primary means with radio as a backup method.
5.4 Communications by radio should be brief, factual, free of exclamatory or alarming expressions and worded so as to not cause undue anxiety.
5.5 Messages should be worded to avoid possible errors in transcription or interpretation. Avoid the use of technical jargon (particularly in communications with off-site agencies), ensure the message is complete, avoid the use of abbreviations (e.g. milli-rem vs mR), and read numbers individually (e.g. 100 as one-zero-zero).
5.6 During radio communications, preface each transmission with your title or name and the title or name of the receiving party (e.g. Monticello Technical Support Center to Monticello monitoring team number one).
5.7 All communications during drills, exercises or tests should begin and end with "This is a Drill" or "This is a Test".
5.8 Pager activations during drills and exercises SHALL NOT use the REAL activation Prefix of "999" for ERO Augmentation.
5.9 Instruction steps identified with a "$" SHALL be satisfactorily completed to meet NRC commitment M91163A requirements. If instruction cannot be satisfactorily completed, contact Emergency Director.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 4 of 12 6.0 INSTRUCTIONS 6.1 General Instructions 6.1.1 Obtain the applicable emergency classification folder and initiate Form 5790-501-03.
6.1.2 For declared emergencies (NUE or higher) the SEC should report immediately to the Emergency Director (duty Shift Manager until relieved).
6.1.3 For personnel safety, during declared emergencies (NUE or higher) with security implications, the SEC should perform all notifications from, and remain in, the Control Room.
6.1.4 During declared emergencies (NUE or higher) the Lead EC should initiate and maintain Form 5790-501 -01 in accordance with Section 6.8 of this procedure.
6.1.5 During declared emergencies (NUE or higher) the Lead EC, (Duty SEC until relieved) should coordinate the communications activities of other ECs responding to the event in accordance with A.2-504 (EMERGENCY COMMUNICATOR DUTIES IN THE TSC AND OSC).
6.2 Initial Notifications for a NUE NOTE: This section provides instructions for the conduct of initial emergency notifications for the declaration of an Unusual Event. Refer to Section 6.3 for Alert, Site Area or General Emergency initial notification instructions. Refer to Section 6.4 for emergency classification change notification instructions.
6.2.1 Obtain Form 5790-102-02 (MONTICELLO EMERGENCY NOTIFICATION REPORT FORM) and Form 5790-102-04 (EMERGENCY CALL LIST - NUE).
6.2.2 Complete Parts 1.0 and 2.0 of Form 5790-102-02 with information provided by the Emergency Director. Both Parts 1.0 and 2.0 of the form should be completed prior to the 15 minute notifications.
6.2.3 Submit the Form 5790-102-02 for Emergency Director review and approval.
6.2.4 Make the initial 15-minute notification to the State and Counties in accordance with the instructions on Form 5790-102-04.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 5 of 12 6.3 Initial Notifications for Alert/SAE/General Emergency NOTE: This section provides instructions for the conduct of initial emergency notifications for the declaration of an Alert, Site Area or General Emergency.
Refer to Section 6.4 for notification instructions for emergency classification changes.
6.3.1 Obtain Form 5790-102-02 and Form 5790-104-04 (EMERGENCY CALL LIST - ALERT/SITE AREA/GENERAL).
6.3.2 Complete Parts 1.0 and 2.0 of Form 5790-102-02 with information provided by the Emergency Director.
6.3.3 Submit Form 5790-102-02 for Emergency Director review and approval.
6.3.4 Make the initial 15-minute notification to the State and Counties in accordance with the instructions on Form 5790-104-04.
6.4 Emergency Classification Changes NOTE: Classification change notification of state and county authorities must be completed within 15 minutes after reclassification. The notification of the NRC (via ENS) should be completed immediately after other notifications and must be completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the reclassification (refer to 10CFR50, App E).
6.4.1 If the TSC is not operational, complete all steps in this section. If the TSC is operational, start your actions with Step 6.4.4.
6.4.2 Obtain and complete parts 1.0 and 2.0 of Form 5790-102-02 with information provided by the Emergency Director.
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~.:~K? CAUTIION If notifications are being made for a General Emergency classification, off-site protective actions recommendations SHALL be included in the initial emergency notifications or classification change notification (Section 1.4 of Form 5790-102-02).
MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 6 of 12 NOTE: Proper close-out from a NUE or Alert classification is termination. Close-out of Site Area Emergency may be termination or recovery depending on the extent of plant damage. Close-out of a General Emergency involves a transition to the Recovery Phase which would be coordinated by the EOF if activated. Refer to EPIP A.2-602 (EVENT TERMINATION OR RECOVERY) for additional information.
6.4.3 Submit the completed Form to the Emergency Director for review and approval signature. Proceed to Step 6.4.6.
6.4.4 If the TSC is operational, obtain the applicable Emergency Classification Folder and provide the REC with Form 5790-102-02 and the applicable emergency guideline labels.
6.4.5 Receive the approved Form 5790-102-02 from the Radiological Emergency Coordinator or Emergency Director.
6.4.6 Review the form for completeness and verify that the form has been approved and signed by the Emergency Director.
6.4.7 Obtain the applicable Emergency Call list for the notification as follows:
A.
For escalation to an Alert, Site Area or General Emergency use Form 5790-104-04.
B.
For termination of an Unusual Event use Form 5790-102-04.
C.
For termination of an Alert or Site Area Emergency use Form 5790-104-04.
D.
For recovery from a Site Area or General Emergency use Form 5790-104-04.
6.4.8 Prior to making the state and county notifications determine if the State EOC or either County EOC is activated. Once EOCs are activated, notifications should be made to those facilities and not to the State Duty Officer or County Sheriff Dispatchers.
NOTE: The State and County EOCs attain full operational capability at different times.
When operational, the EO~s relieve the Duty Officer and dispatchers of communications responsibilities with the utility.
6.4.9 Contact the state and counties, via conference call or individual notifications in accordance with the instructions on the applicable Form 5790-102-04 or Form 5790-104-04.
6.4.10 Make the appropriate page announcement for the classification change or termination. Use the scripted announcement found in the applicable emergency classification folder.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 7 of 12 6.5 Off-site Protective Action Recommendations 6.5.1 Transmit initial off-site protective action recommendations for a General Emergency in accordance with Section 6.3 (Initial Notification for Alert/SAE/General Emergency) or Section 6.4 (Emergency Classification Changes) of this procedure. For revisions to Protective Action Recommendations refer to Section 6.5.2.
NOTE: The transmission of Protective Action Recommendations to the State EOC (State Duty Officer and Counties if State EOC is not activated ) SHALL be completed within 15 minutes of the PAR authorization.
6.5.2 Transmit off-site follow-up PARs (revision of initial PARs) at a General Emergency as follows:
A.
Obtain the completed Form 5790-204-01 (MONTICELLO OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST) from the Radiological Emergency Coordinator (REC) or the Emergency Director.
B.
Review the checklist for completeness and verify the REC and Emergency Director have signed the checklist.
C.
Verify the Emergency Director or REC initiates a call to the Minnesota State Planning Chief at the State EOC to explain the basis for the recommendation.
D.
Transmit the protective action recommendation as follows:
- 1. Prior to State EOC activation:
- a.
Contact the State Duty Officer and both counties (conference call or individually) and read the text of FORM 5790-204-01 (PROTECTIVE ACTION RECOMMENDATION CHECKLIST). Inform them a telecopy will be sent to STATE EOC and County Dispatcher.
- b. Telecopy page 3 of Form 5790-204-01 to STATE EOC, both County EOCs and Dispatchers EOF and utility executive management at the JPIC using the broadcast method by inserting the form into the telecopier (face down) and pressing the FUNC, 8, *, then rapid keys 02, 03, 04, 057,08, P9 0, and then START/COPY key when last remote location is entered.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 8 of 12
- c.
When telecopy transmission is complete, obtain the telecopy transaction report which prints out automatically after transmission. Verify the report applies to the telecopy transmission by checking the date, time and fax numbers (if indicated) listed on the report.
- d.
Confirm by telephone that the counties have received the telecopied recommendation.
- 2.
After State EOC activation:
- a.
Contact the Minnesota State Planning Chief at the State EOC and read the text of Form 5790-204-01. Inform the coordinator that the recommendation is being telecopied to the State EOC.
- b.
Telecopy page 3 of Form 5790-204-01 to the State EOC.
- c.
Confirm (by telephone) that the Minnesota State Planning Chief has received the recommendation.
6.5.3 Telecopy Form 5790-204-01 to the Monticello EOF (if not already done *-'
in Section 6.5.2).
6.5.4 When telecopy transmission is complete, obtain the telecopy transaction report which prints out automatically after transmission.
Verify the activity report applies to transmission by checking the date, time and fax numbers (if indicated) listed on the activity report.
6.5.5 Inform the Emergency Director and REC (if staffed) that the protective action recommendation has been transmitted.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 9 of 12 6.6 Emergency Notification Follow-up Messages NOTE 1:
An Emergency Notification Follow-up Message should be developed and transmitted "every thirty minutes. Additional Emergency Notification Follow-up Message should be transmitted as necessary if conditions warrant or are requested by the State Planning Chief..
NOTE 2:
The Emergency Notification Follow-up Messages can be generated by one of two methods. At the NUE classification both pages of the Follow-up Message are completed by the SEC. At the Alert, Site Area and General Emergency classifications, the Emergency Follow-up Message is generated by computer (MIDAS) and completed by the REC. In either case, the Follow-up Message is then submitted to the ED for approval and subsequent transmittal to the State EOC.
6.6.1 Depending on the emergency classification, obtain and complete Form 5790-102-03 (EMERGENCY NOTIFICATION FOLLOWUP
-MESSAGE) as follows:
A.
For NUE classification:
- 1. Obtain a blank Form 5790-102-03 from the file in the TSC or Control Room.
- 2.
Complete the form using information provided by the Emergency Director (Shift Manager), Shift Chemist or other shift personnel.
B.
At Alert, Site Area or General Emergency:
- 1. Obtain the completed Form 5790-102-03 from the Radiological Emergency Coordinator.
6.6.2 Review completed Emergency Notification Follow-up Message for completeness, deliver it to the Emergency Director to review, time and date, and sign.
6.6.3 Notify the State (Duty Officer or State Planning Chief of Emergency Notification Follow-up Message transmission as follows:
A.
At a NUE (prior to State EOC activation):
- 1. Contact the State Duty Officer by telephone. Inform the duty officer that a Follow-up Message is being telecopied to the State EOC. If the event is occurring during normal working hours direct the duty officer to contact the plant Duty SEC if the transmission.is not received.
B.
At an Alert, Site Area or, General Emergency (after State EOC activation):
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 10 of 12
- 1.
Contact the Minnesota State Planning Chief by telephone.
Inform the coordinator that a Follow-up Message is being telecopied to the State EOC and to contact the plant REC if the transmission is not received.
6.6.4 Telecopy the Emergency Notification Follow-up Message to the State EOC, EOF and utility executive management at the JPIC using the broadcast method by inserting the Follow-up message into the telecopy (face down) and pressing the FUNC, 8,
- keys, then press the 4, 0,5, and 07 Rapid Keys and then press the START/COPY key to transmit.
6.6.5 When telecopy transmission is complete, obtain a telecopy transaction report which is printed when operation is complete. Verify the activity report applies to the transmission by checking the date, time and fax numbers (if indicated) listed on the activity report.
6.6.6 Upon completion of the Follow-up Message transmission inform the Emergency Director.
6.7 Secondary (optional) Notifications 6.7.1 Form 5790-102-06 (SECONDARY NOTIFICATION LIST) should be used by an Emergency Communicator (EC) in either of the following cases:
A.
Immediately upon completion of all initial emergency notifications (required as a result of an emergency declaration, NUE or higher) the Lead Emergency Communicator and Emergency Director (Shift Manager) should review Form 5790-102-06 to determine if other organizations should be contacted, based on the event.
B.
The Emergency Director, TSC Group Leaders or other ERO personnel may request specific organizations be contacted. In this case, Form 5790-102-06 may be used as an aid by an SEC to lookup the organization's telephone number.
6.7.2 Complete Form 5790-102-06 as follows:
A.
Obtain a blank Form 5790-102-06 from the controlled forms file in the TSC or Control Room.
B.
Review the form to identify the organization(s) to be notified (as requested by the Emergency Director or other ERO personnel).
6.7.3 When organizations listed on Form 5790-102-06 are contacted, the time of the contact and a brief description of the information exchanged should be documented in Form 5790-501 -01 in accordance with Section 6.8 of this procedure.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 11 of 12 6.8 Emergency Call Log Instructions 6.8.1 Upon declaration of an emergency (NUE or higher) the duty SEC should initiate a log of emergency communications not documented on other forms or checklists as follows:
A.
Form 5790-501 -01 should be used.
B.
The log should be maintained by the Lead EC or another EC designated by the Lead SEC.
C.
The following information should be recorded for all incoming or outgoing communications, with non-NMC organizations, which are handled by the EC(s) and not recorded on other forms or checklists:
- 1. The date and time of the communication.
- 2.
The name of the organization and individual contacted.
- 3.
A brief description of the reason for the communication and/or the information exchanged.
- 4.
The initials of the EC making the communication.
$ 6.9 Emergency Response Data System (ERDS) Activation and Termination 6.9.1 Activate the ERDS communication link to NRC Operations within one hour of an Alert or higher classification. The line is established via the instructions found in 5790-104-04.
6.9.2 ERDS Termination A.
If the NRC terminates the link, a message "NRC responded with TERMINATE", is displayed, no further action is required. Ensure the terminal server is logged out by entering <LOG> <RETURN>.
B.
If the site desires to terminate the line enter <Ctrl Y>
<RETURN>. This initiates a terminate message to the NRC and no further action is required. Ensure the terminal server is logged out by entering <LOG> <RETURN>.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-501 TITLE:
COMMUNICATIONS DURING AN Revision 14 EMERGENCY Page 12 of 12 7.0 FIGURES None I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 I
IN THE TSC AND OSC Page 1 of 12 EMERGENCY PLAN IMPLEMENTING PROCEDURE -TABLE OF CONTENTS SECTION P,
1.0 2.0 3.0 4.0 5.0 6.0 Prepared By:
L Reviewed By:
OC Review Req'd: YES OC Meeting Number:
1,c-
[*./_
Approved By:
J
,9F Date 17
~~FOR-ASMINISTAIE~~1Y y
'~
AGE 2
2 2
2 2
3 3
4 5
6 7
8 8
9 10 11 12 12 This revision incorporates Volume F Memos:
A ii-
'b,....
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:,r2-- 33-7 RespSupv EP IAssocRef: A2 I [SR: N Freq:
11 yrs I
ARMS:
A.2-504 tDoc Type:
1060 1 Admin Inital-s: \\., -t" Date: l:'t."*,lf-.a I/mab PU R PO S E........................................................
APPLICABILITY...................................................
ORGANIZATION AND RESPONSIBILITIES...........................
D ISC USSIO N.........................
PRECAUTIONS....................................................
INSTRUCTIONS...................................................
6.1 Initial Activation Instructions...................................
6.2 Lead Emergency Communicator Instructions....................
6.3 Emergency Director Communicator Instructions..................
6.4 TSC Plant Status Technical Communicator Instructions...........
6.5 Plant Status Technical Communicator (Control Room - Simulator Control Room for drills) Instructions............................
6.6 OSC Plant Status Technical Communicator Instructions...........
6.7 TSC Emergency Work Status Communicator Instructions.........
6.8 OSC Emergency Work Status Communicator Instructions.........
6.9 OSC Radio Console Communicator Instructions.................
6.10 Emergency Notifications System (ENS) Communicator Instructions.
6.11 Assembly Point Coordinator Instructions........................
6.12 Communicator Shift Turnover Instructions.......................
MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 2 of 12 1.0 PURPOSE This procedure provides instructions and guidance for the conduct of various communication functions at the Technical Support Center (TSC) and Operations Support Center (OSC) during an emergency at the MNGP.
2.0 APPLICABILITY An Alert or higher emergency has been declared at the MNGP and the TSC/OSC has been activated.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 TSC/OSC Emergency Communicators and Technical Emergency Communicators are responsible for performing the duties described in this procedure as directed by the appropriate TSC or OSC personnel.
4.0 DISCUSSION Personnel qualified to fill these positions are identified in the Emergency Communicators section of Form 5790-001-01 (EMERGENCY RESPONSE ORGANIZATION).
5.0 PRECAUTIONS 5.1 The initial notifications to the State and Counties must be completed within 15 minutes after the declaration or re-classification of an emergency. The initial notification of the NRC should be completed immediately after State, County, and ERO notifications and must be completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaring or re-classification of an emergency.
5.2 The transmission of off-site Protective Action Recommendations (PARs) to the State EOC (State Duty Officer and Counties if the State is not activated)
SHALL be completed within 15 minutes of the PAR authorization by the Emergency Director.
5.3 All inquiries from the news media and/or general public should be directed to the Joint Public Information Center (JPIC) at the State Emergency Operations Center (EOC). Emergency response organization personnel should not release information to the media or general public without prior approval of the Chief Nuclear Officer or designee.
5.4 Communications regarding the existence of severity of the event, or protective action recommendations should be made on circuits that cannot be readily intercepted by persons outside the established emergency organizations.
Telephone circuits SHALL serve as the primary means with radio as a backup method.
5.5 Communications by radio should be brief, factual, free of exclamatory or alarming expressions and worded so as to not cause undue anxiety.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 3 of 12 5.6 Messages should be worded to avoid possible errors in transcription or interpretation. Avoid the use of technical jargon (particularly in communications with off-site agencies), ensure the message is complete, avoid the use of abbreviations (i.e., millirem vs. MR) and read numbers individually (i.e., 100 as one-zero-zero).
5.7 All communications during drills, exercises, or tests should begin and end with "THIS IS A DRILL" or "THIS IS A TEST'.
6.0 INSTRUCTIONS 6.1 Initial Activation Instructions 6.1.1 Upon activation of the TSC/OSC all communicators should report to the TSC.
6.1.2 The Communicator positions should be staffed in the following order.
NOTE: The Assembly Point Coordinator position should be staffed immediately IF a plant or site evacuation is in progress. The Assembly Point Coordinator position may be staffed prior to the declaration of a plant or site evacuation in anticipation of the need for a plant or site evacuation.
A.
Lead Emergency Communicator - Tagboard #20 B.
Assistant Emergency Communicators -Tagboard #21 & #22 C.
Emergency Director Communicator - Tagboard #23 D.
Plant Status Communicator - TSC -Tagboard #25 E.
Plant Status Communicator - Control Room - Tagboard #26 F.
OSC Plant Status Communicator - OSC Tagboard #2 G.
TSC Work Status Communicator - Tagboard #27 H.
OSC Work Status Communicator - OSC Tagboard #3 I.
OSC Radio console Communicator J.
Emergency Notification System (ENS) Communicator K.
Assembly Point Coordinator - Tagboard #24 I/mab
'MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 4 of 12 6.2 Lead Emerqiency Communicator Instructions 6.2.1 Report to the TSC Tagboard, review the instructions on Tag #20, and assume the Lead Emergency Communicator duties by turning over Tag #20.
6.2.2 The Lead Emergency Communicator should establish residence in the TSC Communications Room.
6.2.3 Determine the status of initial notifications in progress.
A.
Assess the notifications in progress or completed by the duty Shift Emergency Communicator(s) (SECs) via Form 5790-104-04 (EMERGENCY CALL LIST -ALERT/SITE AREA/GENERAL) and provide necessary assistance to the SEC in completion of the initial notifications.
6.2.4 Obtain staffing of the TSC Emergency Communicator positions.
A.
Two Assistant Emergency Communicators should be assigned (TSC Tagboard #21, #22). If these positions are not filled, contact the Engineering Coordinator or Support Group Leader and request that these positions are filled.
NOTE: All five 3739 extensions must be activated at the same time or the callers will not receive a busy signal. If there are more phones ringing than can be answered, leave some of the phones off the hook.
6.2.5 Activate the five incoming 3739 extensions in the TSC communications room prior to or during the initial notification process.
6.2.6 When time permits, activate the TSC - Control Room Intercom and the TSC - State EOC Low Band Radio. This equipment is in the TSC communications room.
6.2.7 Assume responsibilities for off-site notifications.
A.
Once the 2 Assistant Emergency Communicator positions are filled and the SECs are ready to turnover communication duties, assume responsibility for all off-site communications from the TSC. The duty SECs should be released to their assigned emergency response duties once this transfer has occurred.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 5 of 12 B.
The Lead Emergency Communicator should review all emergency forms, used for off-site communications, for accuracy and completeness prior to their transmission.
NOTE: Upon completion of the initial emergency notifications, Emergency Follow-up Messages should be transmitted at 30 minute intervals or as directed by the State.
C.
Transmit Emergency Notification Follow-up Messages in accordance with the instructions provided in A.2-501 (COMMUNICATIONS DURING AN EMERGENCY).
D.
Maintain the emergency Call Log in accordance with the instructions provided in A.2-501.
E.
If or when changes in emergency classification occur (i.e.,
escalation or termination), make the notifications in accordance with A.2-501.
6.2.8 Transfer of off-site communications to the EOF.
A.
An EOF Off-Site Communicator should contact you to determine the status of off-site notifications and determine the appropriate timing for transfer of off-site communication responsibilities.
Transfer should not occur while emergency notifications are in progress (i.e., notification of a classification change).
Do not transfer off-site communications responsibilities to the EOF until you have completed Part B (Immediate Notifications) and Part C (NRC Notifications) of Form 5790-104-04for the current emergency classification.
B.
Transfer responsibilities as appropriate.
C.
After the transfer of off-site communications to the EOF a TSC Emergency Communicator should monitor transmissions and communications from the EOF (i.e., Emergency Follow-up Messages, Classification Changes etc.) and ensure that copies of the transmissions are routed to the appropriate personnel in the TSC.
6.3 Emergency Director Communicator Instructions 6.3.1 Report to the TSC Tagboard, review the instructions on Tag #23, and assume the duties by turning over Tag #23.
6.3.2 Assist the Emergency Director with the use of Emergency Plan Implementing Procedures.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 6 of 12 6.3.3 Review and monitor the implementation of A.2-213 (RESPONSIBILITIES OF THE EMERGENCY DIRECTOR).
6.3.4 Monitor and inform the ED of emergency communications in progress.
6.4 TSC Plant Status Technical Communicator Instructions 6.4.1 Report to the TSC Tagboard, review the instructions on Tag #25, and assume the duties by turning over Tag #25.
6.4.2 This communicator will establish communications with Technical Communicators in the Control Room (Simulator Control Room for drills/exercises), OSC, and EOF.
6.4.3 The assigned communicator should establish residence at the phone near the TSC Operational Status Board. If a white board is covering the status board it must be removed. A headset is stored at the communicator's phone. Directions for use of the headset are posted near the phone.
6.4.4 When the communication link has been established with the Control Room or Simulator Control Room obtain technical and operational data related to the event including:
A.
Reactor and containment systems and component status.
B.
Critical plant parameters (i.e., temperatures, flows, water levels, etc.).
C.
EOP/SAMG implementation status.
D.
Accident mitigation strategies employed by the Control Room.
E.
As necessary, monitor the SPDS terminal to supplement the information obtained from the Control Room.
F.
Continuously update and maintain the TSC Operational Status Board.
NOTE: Use the Bell to obtain the attention of the TSC staff prior to announcing significant operational events.
G.
If significant operational events occur (i.e., ECCS failure, radioactive release, etc.), immediately announce the event in the TSC.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 7 of 12 6.4.5 Adding other technical icommunicators to the link.
A.
As the technical communicator positions are staffed in the OSC and EOF, they will be calling into the TSC to join the communication link. Complete the following steps to add another communicator to the link.
- 1. When an in-coming call is received, inform the party(s) currently on the link that you will be adding another and placing them on hold. Push the phone's conference button once, this places members currently on the link on hold.
- 2.
Answer the in-coming call by pushing the phone's 1126 button that is flashing slowly. Determine who is being added to the link and ask them to hold while you add them to the link.
- 3.
Push the phone's conference button once and verify that all of the conference members are on the link.
- 4.
Repeat the above steps as necessary to complete the link.
6.5 Plant Status Technical Communicator (Control Room - Simulator Control Room for drills) Instructions 6.5.1 Report to the TSC Tagboard, review the instructions on Tag #26, and assume the duties by turning over Tag #26.
6.5.2 This communicator Will establish communications with Technical Communicator in the TSC.
6.5.3 Obtain a telephone headset and necessary administrative supplies from the TSC cabinet.
6.5.4 The assigned communicator should establish residence at the Control Room or Simulator Control Room back-counter.
6.5.5 Install the headset on the Plant Status Communicator telephone (Control Room extension 1478, Simulator Control Room extension 1815) and establish the link with the TSC Technical Communicator by calling extension 1126.
6.5.6 When the communication link has been established, obtain the technical and operational data related to the event as requested by other members of the link.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 8 of 12 6.6 OSC Plant Status Technical Communicator Instructions 6.6.1 Report to the OSC Tagboard, review the instructions on Tag #2, and assume the duties by turning over Tag #2.
6.6.2 Obtain necessary administrative supplies (markers, etc.) from the OSC File cabinet.
6.6.3 Establish residence near the OSC Operational Status Board.
6.6.4 Install the headset on the Plant Status Communicator telephone (1260) and establish the link with the TSC Technical Communicator by calling extension 1126.
6.6.5 When the communication link has been established, obtain technical and operational data related to the event including:
A.
Reactor and containment systems and component status.
B.
Critical plant parameters (i.e., temperatures, flows, water levels, etc.).
C.
EOP/SAMG implementation status.
D.
Accident mitigation strategies employed by the Control Room.
E.
As necessary, monitor the SPDS terminal to supplement the information obtained from the Control Room.
F.
Continuously update and maintain the OSC Operational Status Board.
G.
If significant operational events occur (i.e., ECCS failure, radioactive release, etc.), immediately announce the event in the OSC.
6.7 TSC Emergency Work Status Communicator Instructions 6.7.1 Report to the TSC Tagboard, review the instructions on Tag #27, and assume the duties by turning over Tag #27.
6.7.2 Obtain necessary administrative supplies (markers, etc.).
6.7.3 Establish residence near the TSC Emergency Work Status Board.
6.7.4 Install the headset on the TSC-OSC Communicator telephone (1461) and establish contact with the OSC Team Tracking Board by calling extension 1219.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 9 of 12 6.7.5 When the communication link is established begin updating the TSC Emergency Work Status Board with available information on emergency teams already dispatched by the Control Room or OSC (if any).
6.7.6 Monitor emergency response discussions in the TSC to determine when Operators or an OSC Team may be needed.
6.7.7 When the TSC requests an Emergency Team be dispatched (Operators from the Control Room or an OSC Team), notify the OSC Communicator and:
A.
Inform the OSC Communicator that a team has been requested and the details of the team assignment and the priority assigned to the task (by the TSC).
B.
Identify the Team Number (next team number in order) assigned by the OSC Communicator. Do not reuse OSC Team numbers to avoid confusion.
6.7.8 Update the TSC Emergency Work Status Board with the Team Number, Priority and task description.
6.7.9 When the team is dispatched, monitor the team progress. Inform the TSC of team progress as requested.
6.7.10 Report any problems encountered by the team immediately to the TSC Group Leaders.
6.7.11 Continuously maintain the TSC Emergency Work Status Board.
6.7.12 As teams complete their missions and report back to the OSC, obtain missions results and update the TSC Emergency Work Status Board by indicating the completion status on the team on the Board.
NOTE: Do not erase completed tasks from the Board unless space is needed for new team and then erase the oldest completed task from the Board.
6.8 OSC Emergency Work Status Communicator Instructions 6.8.1 Report to the OSC Tagboard, review the instructions on Tag #3, and assume the duties by turning over Tag #3.
6.8.2 Obtain necessary administrative supplies (markers, etc.) from the OSC File cabinet.
6.8.3 Establish residence near the OSC Personnel Availability Board and the OSC Team Tracking Board.
6.8.4 Install the headset on the OSC-TSC Communicator telephone (1219) and establish contact with the TSC Emergency Work Status Board Communicator (1461).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 10 of 12 NOTE: When the 2-way link is established and the operational test of the OSC radio console is complete, inform the OSC Coordinator that you are prepared to direct OSC teams.
6.8.5 When the TSC requests an OSC Team be dispatched:
A.
Inform the OSC Coordinator an OSC Team has been requested and the details of the team assignment.
B.
Assign a Team Number (next team number in order) and inform the TSC Emergency Work Status Board keeper. Do not reuse OSC Team numbers to avoid confusion.
C.
Record the job (team mission) on the 0SC Team Tracking Board (adjacent to the team number).
D.
As the OSC Coordinator assigns personnel to the team, relocate their name tag from the OSC Personnel Availability Board to the OSC Team Tracking Board.
6.8.6 Provide information regarding the OSC emergency team progress to the TSC.
6.8.7 Report problems encountered by the OSC teams immediately to the OSC Coordinator.
6.8.8 Continuously maintain the OSC Team tracking Board and the OSC Personnel Availability Board.
6.8.9 As OSC teams complete their missions and report back to the OSC, remove their entry from the 0SC Team Tracking Board and relocate the name tags to the OSC Personnel Availability Board.
NOTE: Do not erase completed tasks from the Board unless space is needed for new team and then erase the oldest completed task from the Board.
6.9 OSC Radio Console Communicator Instructions 6.9.1 Activate the OSC radio console and perform an operations test of the console as follows:
A.
Set the console to the scan mode (indicated by a triangle being highlighted on the LED display above the SCAN button).
B.
Contact one of the OSC portable radios on Talk Groups 1A (Cont. Room) and 5D (Misc.).
6.9.2 As teams are dispatched from the OSC ensure that they are issued a portable radio (set to talk group 5D) and establish radio communications with the team prior to the team's departure from the 0SC.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 11 of 12 6.9.3 Maintain continuous radio contact with the OSC team(s) and direct the team(s) as directed by the OSC Coordinator.
6.9.4 If necessary, when communicating with the OSC teams, use the phonetic alphabet:
A ALPHA J JULIET S SIERRA B BRAVO K KILO T TANGO C CHARLIE L LIMA U UNIFORM D DELTA M MIKE V VICTOR E ECHO N NOVEMBER W WHISKEY F FOXTROT 0 OSCAR X X-RAY G GOLF P PAPA Y YANKEE H HOTEL Q QUEBEC Z ZULU I
INDIA R ROMEO 6.9.5 Report problems encountered by the OSC teams immediately to the OSC Coordinator.
6.10 Emergency Notifications System (ENS) Communicator Instructions NOTE: The ENS link with the NRC Headquarters SHALL be continuously staffed at the Alert classification (or higher) as requested by the NRC. The link could be maintained in the Control Room, TSC, or EOF depending on the resources available and the availability of timely information.
6.10.1 Obtain a telephone headset and necessary administrative supplies from the TSC Supply cabinet.
6.10.2 Establish residence in the TSC Engineering Support area, near the FTS-ENS telephone.
NOTE: The NRC may request continuous staffing of the ENS link upon completion of the initial NRC notification.
6.10.3 If staffing the ENS during initial TSC activation, determine if the initial NRC notification has been completed by the TSC Emergency Communicator staff. If the initial notification has not been completed, provide assistance as necessary to complete the notification. If the initial notification is complete, determine if continuous staffing of the ENS is required.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-504 TITLE:
EMERGENCY COMMUNICATOR DUTIES Revision 3 IN THE TSC AND OSC Page 12 of 12 6.11 Assembly Point Coordinator Instructions 6.11.1 Report to the TSC Tagboard, review the instructions on Tag #24, and assume the duties by turning over Tag #24.
6.11.2 Perform the duties of the Assembly Point Coordinator in accordance with A.2-302 (ACTIVATION OF THE ASSEMBLY POINTS).
6.12 Communicator Shift Turnover Instructions 6.12.1 Check in with the Engineering Coordinator upon arrival at the TSC to determine communication assignments.
6.12.2 Oncoming Communicators should review the TSC Chronological Flipcharts, Status Boards, and other available information prior to or during their turnover discussions.
6.12.3 When generally familiar with the event status the oncoming Communicator(s) should conduct a turnover review with their counterparts which should include (as applicable):
A.
The status of communication activity in-progress in their respective areas including telephone notifications and fax transmissions.
B.
Recently transmitted forms or notifications.
C.
The status of links and the names of individual contacts on the link.
D.
Emergency Call Logs for their respective area.
E.
The status of ENS links and NRC counterparts.
6.12.4 Upon completion of the turnover the oncoming Communicator should assume the duties and inform the Support Group Leader of the turnover.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 1EOF Page 1 of 13 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION p)
P U R PO S E........................................................
A PPLICABILITY...................................................
ORGANIZATION AND RESPONSIBILITIES...........................
D ISC U SS IO N......................................................
PRECAUTIO NS....................................................
INSTRUCTIO NS...................................................
6.1 Off-site Communicator Instructions.............................
6.2 EOF-TSC-CR Technical Communicator Instructions..............
6.3 EOF-JPIC Technical Communicator Instructions.................
6.4 Field Team Radio Communicator Instructions....................
6.5 Emergency Notifications System (ENS) Communicator Instructions.
6.6 Health Physics Network (HPN) Communicator Instructions........
6.7 Communicator Shift Turnover Instructions.......................
1.0 2.0 3.0 4.0 5.0 6.0 AGE 2
2 2
3 3
4 4
7 8
8 11 12 13 Prepared By: e Reviewed By:
OC Review Req'd: YES OC Meeting Number:
3 aj te:
Approved By:
Date*
i
- i FORADMINISTRATIVE USEON This revision incorporates Volume F Memos: C T
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:,0-Q-3622 I/mab Resp Supv EP Assoc Ref: A 2 1,6R N Freq: 1 1 yrs I
ARMS:
A 2-803 TDoc Type: 1060
- AdminIlnitials:
Date'-
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 2 of 13 1.0 PURPOSE This procedure provides instructions and guidance for the conduct of various communication functions at the EOF during an emergency at the MNGP.
Steps in this procedure satisfy commitment M90125A. Procedure steps satisfying these commitments are identified with a $.
2.0 APPLICABILITY 2.1 An Alert has been declared at the Monticello plant and the EOF has been activated and staffed, and; 2.2 The EOF will be assuming responsibility for emergency communications including off-site communications and direction of the MNGP and PI Field Teams.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Manager is responsible for:
3.1.1 Overall direction and coordination of MNGP's emergency response activities (after turnover from the Emergency Director).
3.2 The EOF Off-Site Communicators are responsible for:
3.2.1 The conduct of Emergency (off-site) communications with State and local authorities and federal agencies (after turnover from the TSC).
3.2.2 Transmitting emergency communications generated by the EOF including emergency classification changes, Off-site Protective Action Recommendations and Emergency Followup Messages.
3.3 The EOF-TSC-CR Technical Communicator is responsible for:
3.3.1 Establishing and maintaining a communications link between the Control Room, Technical Support Center, OSC, and EOF for the purpose of obtaining technical and operational information.
3.3.2 Maintaining the Operational Status Board in the EOF Command Center.
3.4 The EOF-JPIC Technical Communicator is responsible for:
3.4.1 Establishing and maintaining a communications link between the Joint Public Information Center and EOF for the purpose of keeping Utility I"
Executive Management informed.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 3 of 13 3.5 The ENS Communicator is responsible for:
3.5.1 Establishing and maintaining an open communications link with the NRC (as directed) using the FTS-Emergency Notification System (ENS) for the purpose of transmitting operational and technical data and information pertinent to the event.
3.6 The HPN Communicator is responsible for:
3.6.1 Establishing and maintaining an open communications link with the NRC (as directed) using the FTS-HPN line for the purpose of transmitting radiological data and information pertinent to the event.
3.7 The Field Team Radio Communicator is responsible for:
3.7.1 Establishing and maintaining radio contact with MNGP and PI off-site monitoring (field) teams and directing team activities.
4.0 DISCUSSION This procedure provides guidance for the various communicator positions staffed in the Emergency Operations Facility. It also provides instructions for the processing and transmittal of the forms used for Emergency Notification Followup Messages, Emergency Classification Changes, Off-Site Protective Action Recommendations and NRC notifications made throughout the course of an emergency from the EOF.
The Emergency (Off-Site) Communicators are responsible to ensure that Emergency Notifications Followup Messages, emergency classification changes and Protective Action Recommendations are properly communicated to off-site authorities under the direction of the Emergency Manager and supervision of the EOF Coordinator.
The Xcel Energy Communications Department is responsible to provide briefings and press releases to the news media in conjunction with state and federal authorities.
The Emergency Manager (and EOF-JPIC Technical Communicator) will provide information on plant status to the Communications Department as necessary. The Emergency Manager (and Technical Communicator) are responsible to ensure information provided to the JPIC is current and consistent with information provided to off-site emergency organizations.
5.0 PRECAUTIONS 5.1 All inquiries from the news media or general public should be directed to the Joint Public Information Center. Emergency Response Organization personnel should not release information to the news media or general public without prior approval of the Chief Nuclear Officer or designee.
5.2 Communications regarding the existence or severity of the event, or protective action recommendations should be made on circuits which cannot be readily intercepted by persons outside the established emergency organizations.
Telephone circuits SHALL serve as the primary means with radio as a backup method.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 4 of 13 5.3 Communications by radio should be brief, factual, free of exclamatory or alarming expressions and worded so as to not cause undue anxiety.
5.4 Messages should be worded to avoid possible errors in transcription or interpretation. Avoid the use of technical jargon (particularly in communications with off-site agencies), ensure the message is complete, avoid the use of abbreviations (e.g., milli-rem vs. mR), and read numbers individually (e.g., 100 as one-zero-zero).
5.5 During radio communications, preface each transmission with your title or name and the title or name of the receiving party (e.g., Monticello Field Team Communicator to Monticello Monitoring Team Number One).
5.6 All communications during drills, exercises or tests should begin and end with "THIS IS A DRILL" or "THIS IS A TEST'.
6.0 INSTRUCTIONS 6.1 Off -site Communicator Instructions NOTE: There are two communicators assigned as Off-site Communicators. The two assigned individuals share the responsibilities associated with the position.
6.1.1 Report to the EOF Tagboard, review the instructions on Tag #12 or Tag
- 13 and assume the duties by turning over the appropriate tag and signing on the Tagboard.
6.1.2 Obtain the Off-site Communicators 3-ring binder. This binder contains the procedural guidance and forms required to conduct the off-site communicator job.
6.1.3 Monitor communications transmissions (initial and follow-up messages) from the TSC.
6.1.4 Through communications with the Lead Emergency Communicator in the TSC, monitor the status of off-site agency activation (e.g., State and County Emergency Operations Centers).
6.1.5 When directed by the EOF Coordinator (or Emergency Manager),
prepare to transfer the responsibility for off-site communications as follows:
A.
Contact the Lead Emergency Communicator in the TSC to determine the status of communications in progress and which off-site agencies are currently being contacted (i.e., are the State County EOC's activated). Verify that the TSC has completed Parts B and C of Form 5790-104-04 (EMERGENCY CALL LIST-ALERT/SITE AREA/GENERAL) for the initial classification/notification.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 5 of 13 B.
Inform the EOF Coordinator when you are prepared to assume off-site communication responsibilities from the TSC.
6.1.6 When directed by the EOF Coordinator, assume the responsibility for off-site communications from the TSC as follows:
I/mab Do not assume off-site communications for off-site communications until you have verified that Parts B (Immediate Notifications) and Part C (NRC Notifications) of Form 5790-104-04 have been completed by the TSC and that there are no emergency notifications in progress during the time of transfer.
A.
Contact the Lead Emergency Communicator in the TSC and verify that they are ready to transfer off-site communications. If the Lead Emergency Communicator concurs, assume the responsibility for off-site communications.
NOTE: Since the State and Counties come to full operation at different times, you should inform the individuals or facilities that are in control at the time of the transfer of off-site responsibilities.
B.
Contact the State (Duty Officer or Emergency Operations Center) and Counties (Sheriffs Dispatchers or Emergency Operations Centers). Inform them that the EOF has assumed off-site communications responsibility and that all requests for information and transmission of data should be directed to the EOF. Confirm the status of their activation, who has responsibility now and if applicable when their EOC(s) will be activated.
C.
Notify the NMC Executive Spokesperson, at the State EOC, that the EOF has assumed responsibility for off-site communications.
6.1.7 Initiate and maintain an emergency call log using Form 5790-501 -01 (EMERGENCY CALL LOG FORM) as follows:
A.
The following information should be recorded for all incoming or outgoing communications with non-NMC organizations which are handled by the Off-site Emergency Communicator and are not recorded on the forms or checklist.
- 1.
The date/time of the communication.
- 2.
The name of the organization or individual contacted.
- 3.
A brief description of the reason for the communication and/or the data exchanged.
- 4.
The initials of the Emergency Communicator making the communication.
MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 6 of 13 6.1.8 As directed, transmit Form 5790-102-03 (EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE) as follows:
A.
Receive the approved Form 5790-102-03 from the Emergency Manager or the Radiation Protection Support Supervisor (RPSS).
B.
Review the form for completeness and verify the form was approved by the Emergency Manager (EM) for transmission.
C.
Transmit the approved Form 5790-102-03 in accordance with the instructions provided in Form 5790-803-02 (EOF PAR/FOLLOW-UP MESSAGE CALL-LIST).
},
- -CAU"TON I
I Notifications of reclassification to the State and Counties SHALL be completed within 15 minutes of the reclassification declaration.
6.1.9 If changes in emergency classification occur (e.g., escalation or termination), transmit Form 5790-102-02 (MONTICELLO EMERGENCY NOTIFICATION REPORT FORM) as follows:
A.
Receive the approved Form 5790-102-02 from the Emergency Manager or the Radiation Protection Support Supervisor.
B.
Review the form for completeness and verify the form was approved by the Emergency Manager (EM) for transmission.
C.
Transmit the approved Form 5790-102-02 in accordance with the instructions provided in Form 5790-803-01 (EOF RECLASSIFICATION CALL-LIST).
Off-site Protective Action Recommendations (PARs) SHALL be communicated to the State and Counties within 15 minutes of the PAR authorization.
6.1.10 If Off-site Protective Action Recommendations are required, transmit Form 5790-204-01 (OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST) as follows:
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`--CAUTION 7i--Q`
Initial Off-site Protective Action Recommendations (PARs) for a General Emergency SHALL be included and transmitted with the classification change on Form 5790-102-02 (MONTICELLO EMERGENCY NOTIFICATION REPORT FORM) in accordance with section 6.1.9 of this procedure.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 7 of 13 A.
Receive the approved Form 5790-204-01 (OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST) from the Emergency Manager or the Radiation Protection Support Supervisor.
B.
Review the form for completeness and verify the form was approved by the Emergency Manager (EM) for transmission.
C.
Transmit the approved Form 5790-204-01 in accordance with the instructions provided inForm 5790-803-02.
6.2 EOF-TSC-CR Technical Communicator Instructions 6.2.1 Report to the EOF Tagboard, review the instructions on Tag #24 and assume the duties by turning over the tag and signing in on the Tagboard.
6.2.2 Establish residence at the phone near the EOF Operational Status Board.
6.2.3 Install the headset on the Technical Communicator phone (ext. 1431) and establish the link with the TSC Technical Communicator by calling extension 1126. Directions for the use of the headset are posted near the phone. If you have problems with the phone contact the EOF Coordinator.
6.2.4 When the communication link has been established, obtain technical and operational data related to the event including:
A.
Reactor and containment systems and component status.
B.
Critical plant parameters (i.e., temperatures, flows, water levels, etc.).
C.
EOP/SAMG implementation status.
D.
Accident mitigation strategies employed by the Control Room.
E.
As necessary, monitor the SPDS terminal to supplement the information obtained from the communication link.
F.
Continuously update and maintain the EOF Operations Status Board.
NOTE: Use the bell to obtain the attention of EOF staff prior to announcing significant operational events.
G.
If significant operational events occur (ECCS failure, radioactive release, etc.), immediately announce the event in the EOF.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 8 of 13 6.3 EOF-JPIC Technical Communicator Instructions 6.3.1 Report to the EOF Tagboard, review the instructions on Tag #25 and assume the duties by turning over the tag and signing in on the Tagboard.
6.3.2 Establish residence at the Technical Communicator phone, portable telephone extension 1506, near the Technical Communicator Station.
NOTE: The JPIC phone (612-330-2923) is a shared line. If you have difficulties establishing this link, call the JPIC Executive Spokesman at 651-229-2525.
6.3.3 When the communication link has been established, obtain technical and operational data related to the event from the EOF Operational Status Board, EOF SPDS, Emergency Manager, and other information sources available in the EOF. Continuously update the JPIC.
6.3.4 If requests for information are made from the JPIC, obtain and provide the necessary information or forward the request to EOF personnel that can provide the information.
6.3.5 If significant operational events occur (ECCS failure, radioactive release, etc.), verify the information is accurate and once verified pass the information on via the link.
NOTE: A copy of Form 5790-801-02 (EMERGENCY MANAGER STATUS UPDATE CHECKLIST) may be used to compile information during the EOF Status Update.
6.3.6 Following EOF Status Updates, provide a summary of the information provided in the update to the JPIC.
6.4 Field Team Radio Communicator Instructions 6.4.1 Report to the EOF Tagboard, review the instructions on Tag #8 and assume the duties by turning over the tag and signing in on the Tagboard.
6.4.2 Obtain the necessary administrative supplies (pens, and board markers) from the EOF Administrative Supply Locker.
6.4.3 Obtain a supply of Form 5790-202-01 (OFF-SITE SURVEY RESULTS DATA SHEET) and Form 5790-410-03 (GROUND DEPOSITION SAMPLE RESULTS LOG) from the EOF controlled forms file.
6.4.4 Establish residence in the EOF Dose Assessment Room.
6.4.5 Activate the Field Team Radio console and perform an operational test of the console by contacting the Field Team Communicator (in the TSC) and the Field Teams.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 9 of 13 6.4.6 Monitor TSC-Field Team transmissions and begin updating the Off-Site Survey Results board and Survey Point Map (in the Dose Assessment Room) with survey results and Field Team location information.
6.4.7 If necessary, obtain current information (wind direction, wind speed, release rates, etc.) from recently issued Emergency Notification Follow-up Messages (issued by the TSC) faxed to the EOF to aid in familiarization with current release rates, meteorology and field team survey results.
6.4.8 When radio operational tests are complete and radio contact established with the Off-Site Field Teams, inform the Rad Prot Sup Supv.
6.4.9 When directed by the RPSS (Assistant RPSS or EOF Coordinator) coordinate the transfer of Field Team control to the EOF as follows:
A.
Contact the Field Team Communicator in the TSC to coordinate the transfer.
B.
Confirm (check) radio contact with all Field Teams.
C.
Confirm cellular telephone numbers with Field Teams for back-up communications.
D.
When directed, assume control of the Field Teams and inform all Field Teams (by radio) that they are under your direction.
E.
Notify the RPSS when transfer of Field Team control is complete.
6.4.10 Designate Field Teams as Monticello Field Teams (1 and 2) and Prairie Island Teams (3 and 4).
6.4.11 Direct the Field Teams to conduct plume search and survey/sampling activities as directed by the RPSS. Refer to A.2-41 0 (OUT-OF-PLANT SURVEYS) for specific information regarding the types of surveys/samples that may be requested of the Field Teams.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5
G EOF Page 10 of 13 6.4.12 When communicating sample point locations to the Field Teams use the phonetic alphabet as follows:
A ALPHA B
BRAVO C CHARLIE D DELTA E ECHO F
FOXTROT G
GULF H
HOTEL I
INDIA J JULIET K KILO L
M N
0 P
LIMA MIKE NOVEMBER OSCAR PAPA Q QUEBEC R ROMEO S SIERRA T TANGO U UNIFORM V VICTOR W WHISKEY X X-RAY Y YANKEE Z ZULU 6.4.13 Continuously maintain the Off-Site Survey Results board and Survey Point Map with information obtained from the field teams.
6.4.14 Record all survey/sample results on the Form 5790-202-01 or Form 5790-410-03 as applicable.
6.4.15 If requested by the RPSS, fill-in the off-site survey results portion (top of page 2) of Form 5790-102-03 (EMERGENCY NOTIFICATION FOLLOWUP MESSAGE) and forward the form to the RPSS for review.
6.4.16 Periodically update all Field Teams with current information regarding:
A.
Meteorological data including wind direction and wind speed.
B.
Radiological release rates and dose projection information (e.g.,
projected dose rates, etc.)
C.
Emergency classification changes.
D.
Off-Site Protective Actions including recommendations made and actions implemented by off-site authorities.
E.
Current plant conditions.
6.4.17 When directing the teams, observe the radiological precautions outlined in A.2-41 0 regarding exposure limits, protective clothing, respirator use and cold weather instrument operating instructions.
6.4.18 Periodically prompt the teams to read their dosimeters and report individual cumulative exposure received. Inform the RPSS if any Field Team members approach administrative exposure limits.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 11 of 13 6.5 Emergency Notifications System (ENS) Communicator Instructions NOTE: The ENS link with NRC Headquarters SHALL be continuously staffed at the Alert classification (or higher) as requested by the NRC. The link could be maintained in the Control Room, TSC or EOF depending on the resources available and availability of timely information.
6.5.1 Report to the EOF Tagboard, review the instructions on Tag #26 and assume the duties by turning over the tag and signing in on the Tagboard.
6.5.2 Establish residence at the phone (FTS phone extension 380-7010) near the Technical Communicator station in the EOF.
6.5.3 If manning the FTS-ENS during initial EOF activation, determine if the one-hour NRC notification has been made (by the plant) by contacting the Lead Emergency Communicator in the TSC. If the NRC notification has been made, determine if continuous manning of the FTS-ENS is required.
NOTE: The NRC may request continuous manning of the ENS link upon completion of the one-hour NRC notification.
6.5.4 If continuous manning of the FTS-ENS has been requested (by the NRC), determine which MNGP emergency response facility will be the "primary" ENS contact point.
6.5.5 When the FTS-ENS is required to be continuously manned, inform the Technical Support Supervisor and EOF Coordinator.
6.5.6 Continuously man the FTS-ENS (in the EOF Command Center) and provide operational and technical information requested by the NRC.
6.5.7 Continuously monitor the EOF Status boards, SPDS, trend charts and other EOF information sources to obtain the necessary information.
6.5.8 Forward technical and/or operational questions (posed by the NRC) to appropriate members of the EOF Technical Support staff.
NOTE: The ENS Communicator is responsible for the completion of Form 3195 (EVENT NOTIFICATION WORKSHEET). Assistance may be provided by others in the EOF Technical Support area or Radiation Protection Support area.
6.5.9 If changes in emergency classification occur (escalation or termination), complete Form 3195. If necessary, refer to 4AWI-04.08.02 (10CFR50.72 and 10CFR73.71 IMMEDIATE NOTIFICATION) for instructions on completing Form 3195. The completed Form 3195 SHALL be reviewed and signed by the Emergency Manager prior to communicating the information to the NRC. Communicate the classification change to the NRC via the ENS link.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 12 of 13
$ 6.5.10 Serve as the liaison with the NRC FTS-ENS Monitor (located in Classroom 9 of the EOF) and assist in clarifying information or responding to questions posed by the NRC.
6.5.11 Report any operational problems encountered with the ENS link to the Technical Support Supervisor.
6.6 Health Physics Network (HPN) Communicator Instructions 6.6.1 Report to the EOF Tagboard, review the instructions on Tag #6 and assume the duties by turning over the tag and signing in on the Tagboard.
6.6.2 Obtain a headset (for an analog telephone) and any necessary administrative supplies from the EOF Administrative Supply Locker.
6.6.3 Establish residence at the RPSS station in the EOF Command Center (near the FTS-HPN telephone).
6.6.4 Contact the Monitoring Section Leader (MSL) or Radiological Emergency Coordinator (REC) in the TSC to determine if continuous manning of the FTS-HPN link is required (if requested by the NRC).
NOTE: The emergency response facility responsible for off-site communications (e.g.,
Follow-up Messages, PARs, etc.) should man the HPN link since the information transmitted on the HPN is primarily focused on health physics implications, such as, PARs, dose projections, etc.
6.6.5 Coordinate the continuous manning of the FTS-HPN link with the MSL (or REC) in the TSC.
6.6.6 When directed, man the FTS-HPN link in the EOF and provide health physics related information to the NRC via the link including:
A.
On-site protective actions taken (e.g., plant evacuation, etc.)
B.
Over-exposures, personnel contaminations, etc.
C.
Radiological release rates, projected doses off-site and the results of environmental surveys taken by Field Teams.
D.
Results of State survey teams (if known).
6.6.7 Continuously monitor the EOF RP Status board, Emergency Notification Follow-up Messages, Off-Site Survey Results Status Board and other sources to obtain the necessary information for the HPN.
6.6.8 Forward health physics (PAR, etc.) questions (posed by the NRC to the RPSS).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-803 TITLE:
EMERGENCY COMMUNICATIONS AT THE Revision 5 EOF Page 13 of 13 6.6.9 If off-site protective actions are recommended, ensure the NRC is notified of the recommendations and the actual off-site protective actions taken by the State (and counties).
$ 6.6.10 Serve at the liaison with the NRC HPN Monitor (located in Classroom 9 of the EOF) and assist in clarifying information or responding to questions posed by the NRC over the HPN link.
6.6.11 Report any operational problems encountered with the HPN link to the RPSS.
6.7 Communicator Shift Turnover Instructions 6.7.1 Upon arrival in the EOF, oncoming Communicator(s) should check-in with the EOF Coordinator to determine communications assignments.
6.7.2 Oncoming Communicators should review the Chronological Flipchart and all EOF Status Boards prior to or during their turnover discussions.
6.7.3 When generally familiar with the event status the oncoming Communicator(s) should conduct a turnover review with their off-going counterparts which includes (as applicable):
A.
The status of communications activities in-progress in their respective areas including telephone notifications and fax transmissions.
B.
Recently transmitted forms or notifications (e.g., Emergency Follow-up Messages, PARs, Classification Changes, etc.)
C.
The status of the telephone link and the name(s) of individual contacts on the link.
D.
Emergency Call Log(s) for their respective areas.
E.
Field Team location(s) and status including surveys/samples requested and recent survey/sample results.
F.
The status of ENS/HPN links and NRC counterparts.
6.7.4 Upon completion of the turnover, review the oncoming Communicator should assume the duties and inform the EOF Coordinator of the turnover.
6.7.5 Ensure the EOF Organizational Status Board is updated as necessary with the on-duty Communicator(s).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 1 of 33 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE...
2 2.0 APPLICABILITY..........................................
2 3.0 ORGANIZATION AND RESPONSIBILITIES...........................
2 4.0 DISCUSSIO N......................................................
3 5.0 PRECAUTIONS....................................................
4 6.0 INSTRUCTIONS..........................................
5 6.1 Initial PARs for General Emergency Classification................
5 6.2 PARS for Sherco Plant........................................
6 6.3 Off-site PARs Based on Projected Doses........................
7 6.4 Protective Action Recommendation for Liquid Releases...........
9 6.5 Ground Deposition Assessment................................
10 6.6 Return Dose Assessment.....................................
11 6.7 General Instructions for Field Team Deployment.................
11 6.8 Field Team Deployment During Airborne Releases...............
12 6.9 Field Team Deployment for Ground Deposition Assessment.......
14 6.10 Dose Assessment and Field Team Deployment for Ingestion Pathway 15 7.0 FIG U R ES.........................................................
16 7.1 Definitions Related to Protective Actions Recommendations.......
16 7.2 Discussion of Protective Action Recommendations...............
19 7.3 Protective Action Guidelines (PAGs)............................
22 7.4
-Emergency Worker Exposure Limits............................
24 7.5 Transport Time and Monthly Average Flowrates..................
25 7.6 Liquid Release Protective Action Criteria........................
27 7.7 Ground Deposition Modeling...................................
28 7.8 Secondary Evacuation Dose Projection.........................
30 7.9 Relocation Protective Action Guidelines.........................
32 7.10 Forms Utilized in Procedure................................
33 Prepared By: 14
/
Reviewed By:
OC Review Req'd. YES OC Meeting Number:
Approved By:
Date: 1 2 2 t FOR ADMI 1!TRATIVEUSE ONLY _'K Tis revision incorporates Volume F_____Memos:____________________
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:
02-7.5-1
,Resp Supv:
EP lAssocRef A 2 N
y JARMS:
A 2-807 IDoc Type 1060 IAdminlnitials:
DL-LIate 10L.
Al*-
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MONTICELLO NUCLEAR GENERATING PLANT A-2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 2 of 33 1.0 PURPOSE This procedure provides instructions and guidance for the conduct of off-site dose assessment and formulation of off-site Protective Action Recommendations at the Monticello EOF.
Steps in this procedure satisfy commitment M90125A.
2.0 APPLICABILITY 2.1 An Alert has been declared at the Monticello plant and, 2.2 The EOF has been activated, staffed and has assumed the responsibility for off-site communication, dose assessment and Field Team coordination.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Manager (EM) is responsible for:
3.1.1 The approval of off-site Protection Action Recommendations prior to their transmittal to the State (or local) authorities.
3.2 The Radiological Protection Support Supervisor (RPSS) is responsible for:
3.2.1 Implementation of this procedure.
3.2.2 Overall direction and coordination of EOF Rad Prot Support group activities including off-site dose projections, dose assessment, and the formulation of off-site protective action recommendations.
$ 3.2.3 Making recommendations regarding off-site Protective Actions to the Emergency Director (ED) and discussing the basis for off-site Protective Action Recommendations with the State Planning Chief and NRC.
3.3 The Assistant RPSS is responsible for:
3.3.1 Assisting the RPSS with the coordination of EOF Radiation Protection Support Group activities including dose projections, assessment and Field Team direction.
3.4 The MIDAS Operator is responsible for:
3.4.1 The conduct of off-site dose projections using the MIDAS (or backup) Y.,
methods including the generation of periodic Emergency Notification Follow-up Messages for transmittal to the State.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 3 of 33 3.5 The Field Team Coordinator is responsible for:
3.5.1 Direction and coordination of Monticello and Prairie Island Field Teams under the supervision of the RPSS (or Assistant RPSS).
3.6 The Field Team Communicator is responsible for:
3.6.1 The coordination of Monticello and Prairie Island Field Teams via radio under the direction of the Field Team Coordinator.
4.0 DISCUSSION 4.1 Summary Dose assessment refers to the integrated process of dose projection, collection of field measurements and meteorological data, comparison of projected data to field data, and consideration of plant status to develop a working knowledge of the current and near-term radiological environment resulting from a radioactive release.
The radiological forecast developed in the dose assessment process provides the input for making appropriate recommendations to protect the health and safety of the public.
The responsibility for dose assessment is initially assigned to the TSC. The Radiological Emergency Coordinator (REC) formulates protective action recommendations which are forwarded to State or County officials through the ED. After the EOF is activated, the EM is responsible for dose assessment. At the decision of the EM, the dose assessment function transfers from the TSC to the EOF.
The decision to transfer dose assessment responsibilities from the TSC to the EOF will be based on the emergency situation, the EOF equipment status and staffing of the Radiation Protection Support Group. The transfer is implemented by informing the TSC, directing the RPSS to assume the responsibility and closely coordinating the transfer with the REC.
4.2 For definitions related to PARs, see FIGURE 7.1 4.3 For general discussion of PARs, see FIGURE 7.2 I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 4 of 33 5.0 PRECAUTIONS 5.1 Declaration of a General Emergency requires immediate initial protective action recommendations (PARs) to off-site agencies. Under these circumstances, NO dose projections are required for formulating the initial off-site protection action recommendation.
5.2 Implementation of protective actions for off-site areas is the responsibility of the State of Minnesota. If it is determined by the EM that immediate protective actions are required, and the State EOC is not activated, the recommendation SHALL be made directly to the local authorities (i.e., Wright and Sherburne Counties). Upon activation of the State EOC all off-site protective action recommendations SHALL be made to the State.
5.3 The protective actions outlined in this procedure are limited to actions for minimizing the exposure of the public to external and internal radiation exposure from plume passage, inhalation of the radioactive plume and from internal exposure from drinking water during the early phase of an emergency.
Other protective actions for minimizing public exposure via the ingestion pathway will be determined and implemented by the State.
5.4 Exposures of Field Team personnel should be in accordance with administrative control levels. They should have proper dosimetry, which is frequently checked, remain alert to their own exposure and request relief if cumulative exposure approaches administrative control levels. The ED may authorize exposure limit extensions if necessary (refer to EPIP A.2-401). All exposures should be maintained ALARA.
5.5 Monticello Field Teams should not be recalled from field monitoring until Prairie Island teams have relieved them in the field.
5.6 The transmission of Off-site Protective Action Recommendations to the State EOC (State Duty Officer and Counties if the State EOC is not activated)
SHALL be completed within 15 minutes of the PAR authorization.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 5 of 33 6.0 INSTRUCTIONS I.r l....
- -2 cAUTiON,'f No dose projections are required when making initial PAR during GENERAL EMERGENCY CONDITIONS.
"6.1 Initial PARs for General Emergency Classification 6.1.1 Initiate Form 5790-102-02 (MONTICELLO EMERGENCY NOTIFICATION REPORT FORM).
A.
Complete Section 1.4 recommending an evacuation of a 2 mile radius and 5 miles downwind and advise the remainder of the plume EPZ to go indoors to monitor EAS broadcasts.
B.
Determine which geopolitical subareas are affected by referring to the Sector-Subarea Conversion Table on Form 5790-102-02.
C.
Ensure completion of Parts 1.0 and 2.0 of Form 5790-102-02 and submit the completed form to the EM for approval.
6.1.2 Ensure transmission of the recommendations, via telephone and telecopy, to the State EOC (State Duty Officer, Wright and Sherburne Counties if the State EOC is not activated) in accordance with EPIP A.2-803 (EMERGENCY COMMUNICATIONS AT THE EOF).
6.1.3 Approximately 30 minutes after making the recommendation, contact the State Planning Chief or State Duty Officer if State EOC is not activated to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented and indicate the completion status on the Radiation Protection Status Board.
6.1.4 Update the EM and EOF personnel (if activated and staffed) on the status of off-site Protective Action implementation.
6.1.5 After making initial Protective Action Recommendations (at the General Emergency Class) continually assess plant conditions and off-site dose projection results. Make subsequent off-site protective action recommendations based on projected off-site doses using the Protective Action Guidelines (PAGs) listed in FIGURE 7.3.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 6 of 33 6.2 PARS for Sherco Plant NOTE: To safely shutdown the Sherco Plant requires eight (8) hours after the unit(s) are tripped.
6.2.1 Throughout the event the RPSS (or Assistant RPSS) should review off-site projected doses and affected Sectors (Subareas) to determine if the Sherco Plant is or will be in the affected area.
NOTE: The Sherco Plant is located in the 5N subarea.
6.2.2 Formulate protective action recommendations for the Sherco Plant as follows:
A.
Recommendations based on Projected Dose (whole body):
- 1.
> 500 mrem (TEDE) - recommend evacuation of non-essential personnel from the Sherco site and shelter essential plant personnel during plant operation.
- 2.
> 1 Rem (TEDE) - recommend shutdown of the Sherco Plant(s). Immediate evacuation of non-essential personnel and sheltering of essential personnel during normal plant shutdown.
- 3.
> 5 Rem (TEDE) - recommend immediate evacuation of non-essential personnel and sheltering of essential personnel during emergency plant shutdown. Evacuate all personnel immediately after plant shutdown.
B.
Recommendations based on General Emergency:
- 1. If evacuation is implemented (in 5N) recommend evacuation of all non-essential personnel and sheltering of essential Sherco personnel. Recommend immediate initiation of plant shutdown.
6.2.3 If protective actions are required for the Sherco Plant, discuss the recommendations with the EM.
NOTE: Generation management will implement the required protective actions for Sherco personnel through established management channels.
6.2.4 Monitor the progress of protective action implementation (at Sherco) to determine when they are completed.
6.2.5 Indicate any PARs recommended (and implemented) for the Sherco Plant on the RP Status Board in the TSC.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND OFF-ITE OSE SSESMENTAND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 7 of 33 6.2.6 Advise the EM if conditions change (e.g., significant increase in release rate) which could change the protective action recommendations for the Sherco Plant.
6.3 Off-site PARs Based on Proiected Doses I/mab
~CAUTION Do not delay recommending off-site protective actions while waiting for off-site monitoring results to verify the accuracy of the dose projection model. Do not delay recommending off-site protective actions while trying to resolve questionable data (MIDAS Data or Field Team Data).
6.3.1 Continuously review dose projection data (four (4) day integrated maximum TEDE and Thyroid CDE) on Form 5790-102-03 (EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE) and compare with the Protective Action Guidelines in FIGURE 7.3. If an updated PAR, based on dose projections is required, proceed to Step 6.3.2. Continuously review meteorological data (wind direction and wind speed) on Form 5790-102-03 and determine the affected sectors.
If an updated PAR, based on meteorological data is required, proceed to Step 6.3.2.
6.3.2 Initiate Form 5790-204-01 (MONTICELLO OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST) and complete the airborne release section.
6.3.3 Using current meteorological data (i.e., wind direction and wind speed), determine the affected Sectors, Geopolitical Subareas (using page 2 of Form 5790-204-01), population centers within the affected area and estimated plume arrival time in those areas.
6.3.4 Based on plant conditions, estimate the duration of the existing release or potential release.
6.3.5 Using available weather forecast data, evaluate the potential for wind direction and wind speed changes during the estimated duration of the release (and after). Determine what effect potential wind direction and wind speed changes would have on the affected areas identified in 6.3.3.
NOTE: Weather forecast information may be obtained from the National Weather Service. Refer to the Monticello and Prairie Island Nuclear Emergency Preparedness Telephone Directory for telephone numbers.
NOTE: If data used in the determination of the PAR is/or was questionable, attempt to verify the data. DO NOT delay the issuance of the PAR. If after verification of questionable data a PAR revision is necessary, complete Section 6.3 of this procedure.
MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 8 of 33 6.3.6 If based on dose projections or field team data a PAR beyond the 10 mile EPZ is necessary, immediately contact the State Planning Chief to inform them of this condition and document in comments section of Form 5790-204-01. Attach a copy of the supporting Follow-up Message to Form 5790-204-01.
6.3.7 Indicate the recommendations on page 3 of Form 5790-204-01.
Indicate the recommendation in terms of Sectors and Subareas by completing and circling the applicable information as follows:
A.
Identify the affected keyhole by selecting a 3600 out to 2 or 5 miles. Determine the affected Sectors by including both Sectors on either side of the downwind Sector (two Sectors on either side should be included if the downwind direction is on a Sector line).
Record the 3 (or 4) affected Sectors on page 3 of the Monticello PAR Checklist.
B.
Identify the affected geopolitical subareas using the Sector-Subarea Conversion Chart (page 2 of Form 5790-204-01) and circle the affected subareas on the PAR Checklist.
6.3.8 Submit the completed page 3 of Form 5790-204-01 to the EM for approval. Review and discuss the recommendations with the ED as necessary.
NOTE: Prior to activation of the State EOC, protective action recommendations should be made directly to the State Duty Officer and Wright and Sherburne Counties (EOCs if activated). The State Duty Officer will coordinate the EAS message and PANs activation with counties. Once the State EOC is activated, all protective action recommendations SHALL be made directly to the State authorities.
6.3.9 The ED (or RPSS) should direct an Emergency Communicator to transmit the approved Off-Site Protective Action Recommendation Checklist, to the State EOC (Wright and Sherburne County EOCs only if the State EOC is not yet activated) in accordance with EPIP A.2-803.
6.3.10 When notified by the Emergency Communicator that the transmittal of the protective action recommendation has been made to the State Planning Chief (if State EOC is activated) or the State Duty Officer, Wright County and Sherburne County (if State EOC is not activated) contact either the State Planning Chief or the State Duty Officer, Wright County and Sherburne County. Discuss the recommendations and explain the basis of the recommendations.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 9 of 33 6.3.11 Approximately 30 minutes after making the recommendation, contact the State Planning Chief or State Duty Officer prior to State EOC activation, to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented and indicate the completion status on the Radiation Protection Status Board.
6.3.12 If, as a result of continuing assessment, dose projection results or meteorological conditions change significantly, re-evaluate the previously implemented protective actions and, if necessary, update the protective actions by issuing another recommendation.
6.4 Protective Action Recommendation for Liquid Releases 6.4.1 Initiate Form 5790-204-01 and complete the Liquid Release Section.
6.4.2 Obtain the isotopic analyses of liquid samples taken at the Discharge Canal or release point.
NOTE: During a liquid release, samples may be taken at the discharge structure, mid-canal sample station, canal out-fall to the river, or as near the source of the release as possible. To ensure samples are representative of the material being released to the river, the Canal Sample Station is the preferred sampling location.
6.4.3 Determine the present Discharge Canal flow rate and river flow rate at the plant (refer to the applicable plant computer point for flow rates).
6.4.4 Determine the river flow rate at either the Coon Rapids Dam or the Minneapolis-St. Paul water intakes by contacting the Minneapolis Water Department (refer to the Monticello and Prairie Island Nuclear Emergency Preparedness Telephone Directory for telephone numbers).
6.4.5 Using the curve RIVER FLOW vs TIME curve (FIGURE 7.5) estimate the time of release arrival at the Minneapolis-St. Paul water intakes based on current, actual river flow (if actual river flow is not available, use the monthly average river flow in FIGURE 7.5).
6.4.6 Using the MIDAS User Manual Procedures access the MIDAS liquid release model. Enter the isotopic and other applicable release data.
6.4.7 Using the MIDAS Liquid Release Dose Assessment printout, formulate off-site protective action recommendations in accordance with the guidelines in FIGURE 7.6.
6.4.8 Indicate the recommendations on page 3 of Form 5790-204-01 and submit the completed form for ED approval.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 10 of 33 6.4.9 Transmit the recommendations to the State Planning Chief (State EOC if activated) in accordance with EPIP A.2-803.
6.4.10 Contact the State Planning Chief (in the State EOC if activated) to explain the basis for the recommendations.
6.4.11 Approximately 30 minutes after making the recommendation, contact the State Planning Chief to determine what protective actions are actually being implemented. Continue to track the status of the protective action until completely implemented.
6.5 Ground Deposition Assessment 6.5.1 Perform ground deposition projections as follows:
NOTE: The purpose of this step is to obtain a rough estimate of ground deposition. If estimates of curies released are not available, proceed with Field Team deployment.
A.
Determine the number of microcuries of iodine and particulate material (i.e., not noble gases) that were released.
B.
Refer to FIGURE 7.7 to calculate the projected ground deposition. Using the guidance in FIGURE 7.7 develop a footprint, or map of the area, that could have ground contamination levels above 1 uCi/m2.
C.
Record Field Team ground deposition survey results on Form 5790-410-03 (GROUND DEPOSITION SAMPLE RESULTS LOG).
6.5.2 As exposure rate data is obtained, calculate relocation projected doses using the conversion factor of 5000 mrem per mR/hr (i.e., 5000 mrem relocation projected dose per 1 mR/hr initial gamma exposure rate 1 meter above the ground).
NOTE: This conversion factor may be conservative. The factor depends on the isotopic distribution and decay time of the ground deposition. With actual isotopic data, a better conversion factor can be calculated using the data in FIGURE 7.8.
6.5.3 As smear samples are analyzed and isotopic data is obtained use FIGURE 7.8 to refine the relocation projected doses.
6.5.4 Plot the relocation projected doses on a map. (Consider using a dedicated map to avoid confusion).
6.5.5 Determine the appropriate protective action recommendations in accordance with FIGURE 7.9.
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MONTICELLO NUCLEAR GENERATING PLANT A-2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 11 of 33 6.6 Return Dose Assessment 6.6.1 As soon as resources allow, obtain dose rate surveys and smear samples per EPIP A.2-41 0 (OUT-OF-PLANT SURVEYS) in evacuated areas that are believed to be outside the footprint.
6.6.2 As the priority for return to evacuated areas within the known footprint increases (per the States recommendation), obtain dose rate surveys and smear samples within the affected (evacuated) areas in accordance with A.2-41 0.
6.6.3 Use FIGURE 7.8 and calculate relocation projected doses based on known (measured) ground deposition.
6.6.4 Plot the relocation projected doses on a map.
6.6.5 Refer to FIGURE 7.9 and develop Protective Action Recommendations regarding return to evacuated areas as appropriate.
6.6.6 Indicate the recommendation on Form 5790-204-01.
A.
Submit the completed form to the Emergency/Recovery Manager for approval and processing.
6.7 General Instructions for Field Team Deployment 6.7.1 Identify the team(s) as Monticello Field Team 1 and 2 and direct the team(s) to establish and maintain radio communication with the Field Team Communicator in the EOF.
6.7.2 When the Prairie Island Field Teams arrive identify the PI teams as Field Team 3 and 4.
6.7.3 Determine the starting point of the survey based on the release point, source term, magnitude of the release, wind direction, and dose projection data (if available).
6.7.4 Dispatch the team(s) to the selected survey/sample points to conduct surveys/sampling in accordance with EPIP A.2-410.
6.7.5 Direct the team(s) to transmit survey/sample results (by radio) to the Field Team Communicator in the EOF.
6.7.6 Direct the Field Team Communicator to record survey results on Form 5790-202-01 (OFF-SITE SURVEY RESULTS DATA SHEET) or Form 5790-410-03.
6.7.7 Direct the Field Team Communicator to periodically update the team(s) on plant conditions, emergency classification changes, protective actions and meteorological information as it becomes available.
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6.7.8 Direct the team to check personal dosimetry and request relief if their exposure approaches administrative limits.
6.7.9 Direct the team(s) in the use of protective measures (including Anti-C clothing, respiratory protection and exposure control) in accordance with the following guidelines:
A.
Direct protective clothing and respirator (with GMR-l canisters) use if:
- 1.
Substantial airborne activity and ground contamination is suspected or observed and the affected sectors have been evacuated; or
- 2.
A General Emergency has been declared and measured dose rates are more than 100 mrem/hr True Beta.
B.
Direct the implementation of ALARA exposure control measures as follows:
- 1.
Field Teams should not linger in areas greater than 100 mrem/hr;
- 2.
Field Teams should not proceed into areas projected to be greater than 1000 mrem/hr unless directed by the REC;
- 3.
Field Teams should not proceed into areas projected to be greater than 10,000 mrem/hr.
6.7.10 Based on initial survey results request backup surveys or confirmatory sampling as necessary.
6.7.11 Upon completion of Field Team survey operations, direct the team(s) to report to the Emergency Operations Facility for exposure processing, de-briefing and re-assignment.
6.8 Field Team Deployment During Airborne Releases NOTE: For events that do not involve a radioactive release off-site monitoring is required to confirm that a release (above normal limits) is not occurring.
6.8.1 Dispatch the Field Teams in the downwind direction to conduct a search for the plume in accordance with EPIP A.2-41 0.
~ CAUTION~.7~-:J Do not allow the Field Team(s) to sit idle. Teams should traverse the projected path of the plume in downwind affected sectors rather than remain in one location awaiting plume arrival.
6.8.2 When the plume is located (positive meter deflection) instruct the team(s) to perform dose rate surveys in accordance with EPIP A.2-410.
I/mab MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 12 of 33 I
MONTICELLO NUCLEAR GENERATING PLANT A 2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 13 of 33 6.8.3 Based on the results of the dose rate survey(s) determine if the team is in the plume (positive beta reading) or if the plume is elevated (gamma only).
6.8.4 When the plume is encountered (i.e., positive beta reading) direct the team(s) to obtain airborne particulate, gaseous and Iodine airborne, and ground deposition samples. Instruct the team to analyze the samples (in low background area) and transmit the field analysis results to the EOF.
6.8.5 Upon completion of the field analysis direct the team to retain the samples or deliver them to the EOF Count Room for further analysis.
NOTE: A sample courier may be used to transport samples from the team(s) to the applicable Count Room.
6.8.6 Direct the Field Team Communicator to record all survey results on Form 5790-202-01 or Form 5790-410-03.
6.8.7 Track and plot the movement of the plume on the Radiological Survey Point map as follows:
A.
Using current meteorological conditions (wind speed, direction, etc.) project the path of the plume; B.
Using available MIDAS data (GAMMA & THYROID PROJECTED DOSE REPORT and PROJECTED DOSE
SUMMARY
REPORT) project the location of the leading edge and trailing edge (if "puff" release) of the plume; C.
Using the team(s), locate the leading edge of the plume; D.
Using the field team(s), locate the lateral boundaries (sides) of the plume; E.
Using the team(s), verify that upwind ("backdoor") areas near the site are not affected by the release; F.
For "puff' releases, direct the team(s) to locate the trailing edge of the plume; 6.8.8 Compare off-site monitoring results for consistency with State survey results as applicable. Reconcile inconsistencies in data and/or re-survey areas of concern as necessary.
6.8.9 Determine the centerline dose rate by directing a team to traverse through the plume, while monitoring enroute.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 14 of 33 NOTE: This survey should be coordinated with the MIDAS dose projection run in an attempt to verify the projection by comparing survey results to the projection data.
6.8.10 Compare off-site survey results with dose projections for consistency.
Reconcile major inconsistencies in data and/or re-survey areas of concern as necessary.
NOTE: A factor of < 100 is appropriate to use as the reasonable deviation when comparing model vs. actual field data.
6.8.11 Direct the Field Team Communicator to periodically update the team(s) on plant conditions, emergency classification changes, protective actions and meteorological information as it becomes available.
6.9 Field Team Deployment for Ground Deposition Assessment 6.9.1 Deploy Field Teams to obtain ambient dose rates and collect samples (in accordance with A.2-41 0) in areas that are not evacuated, but within the footprint.
6.9.2 Concentrate first on areas suspected of having the highest deposition.
6.9.3 Priority should be given to initially performing dose rate surveys, with more detailed smear surveys to follow. Target areas with dose rates above 0.2 mrem/hr or direct frisker readings above 20,000 CPM for collection of smear samples.
6.9.4 Enough dose rate surveys/smear samples should be obtained to have confidence that "hot spots" have not been overlooked. Ten survey points per square mile is suggested as a minimum in areas where roads will allow this to be practical.
6.9.5 Ensure that areas not within the projected footprint are surveyed sufficiently to verify that the affected area has been identified completely.
6.9.6 Plot the Field Team results on a map. Compare them to the ground deposition projections, and direct follow-up surveys as appropriate to ensure the affected area is identified.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 15 of 33 6.10 Dose Assessment and Field Team Deployment for Ingestion Pathway 6.10.1 Contact the EOC of each affected State and see if they have sample collection needs of particular priority that MNGP could satisfy.
NOTE: MNGP survey teams have the capability of performing dose rate, smear, liquid, soil/snow and air sampling and analysis. If there is a need for more sophisticated environmental samples, contact Teledyne and implement the letter of agreement. Once notified, Teledyne will dispatch a team to the affected site. They will also make their laboratories available for use should we need to send samples for analysis.
6.10.2 Direct the Field Teams to obtain samples according to the State(s) needs or to collect samples to confirm the results of the State(s) survey team.
6.10.3 Ingestion pathway dose projections should not be performed. Instead concentrate available resources on the collection, analysis, and transmittal of results to the States of smear, liquid, soil and/or snow samples.
6.10.4 Ingestion pathway protective actions will be determined by the State of Minnesota.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 16 of 33 7.0 FIGURES FIGURE 7.1 Definitions Related to Protective Actions Recommendations
- 1.
Affected Area is any area where radiation emanating from a plume, or from material deposited from the plume, can be detected using field instruments (also known as the footprint).
- 2.
Cloudshine is radiation from radioactive materials in an airborne plume.
- 3.
Committed Dose Equivalernt (CDE) refers to the dose received over the 50 year period following an intake of radioactive materials.
- 4.
Committed Effective Dose Equivalent (CEDE) is the sum of the products of the weighted factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissue.
- 5.
Dose equivalent means the product of the absorbed dose in tissue, quality factors, and all other necessary modifying factors at the location of interest.
- 6.
Effective dose equivalent (EDE) is the sum of the product of the absorbed dose in tissue, quality factors, and all other necessary modifying factors at the location of interest.
NOTE: Deep Dose Equivalent (DDE) is considered equivalent to EDE if the exposure is uniform.
- 7.
Emerqency Planning Zone (EPZ) is a defined area which facilitates emergency planning by State and local authorities to ensure that prompt and effective actions are taken to protect the public in the event of a radioactive release from the plant. The EPZ is defined for two areas:
A. Plume Exposure Pathway (10 Mile EPZ) is the 10 mile, 3600 radius around the plant in which the primary concern is short-term exposure from the plume. The principal sources of exposure in this area are 1) whole body external exposure to gamma radiation from the plume and deposited material from the plume, and 2) internal exposure from inhaled material from the plume.
B. Ingestion Exposure Pathway (50 Mile EPZ) is a 50 mile, 3600 radius around the plant in which the principal exposure would be from ingestion of contaminated water or foodstuffs (such as milk or fresh vegetables).
- 8.
Evacuation is the removal of people from an area to avoid or reduce high-level, short term exposure, from a plume or from deposited activity.
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MONTICELLO NUCLEAR GENERATING PLANT A-2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 17 of 33 FIGURE 7.1 Definitions Related to Protective Actions Recommendations (cont'd)
- 9.
Geopolitical Subareas are subarea within the 10 Mile EPZ that are defined by predetermined geographic and/or political boundaries.
- 10.
Groundshine is radiation exposure caused by radioactive materials deposited on the ground.
- 11.
Ingestion Pathway Projected Dose is the projected CEDE (ICRP-30) from consuming contaminated foodstuffs.
- 12.
Keyhole Area an area within the 10 Mile EPZ defined by a 3600 radius out to a specified distance of 2 or 5 miles and continuing in the downwind direction in 3 or 4 Sectors.
- 13.
Plume Proiected Dose refers to future calculated doses from plume submersion, plume shine, plume inhalation and 4 days of ground deposition exposure.
- 14.
Protective Action is an action taken to avoid or reduce a projected dose.
- 15.
Protective Action Guide (PAG) refers to a dose (or commensurate dose rate) which warrants protective actions.
- 16.
Public Alert and Notification System (PANS)' is the system used to alert the public within the 10 Mile EPZ of an emergency condition at the plant. Once alerted, the public would turn to local commercial media broadcast messages for specific protective action instructions. The PANS consists of the following systems:
A. Fixed sirens for 100% coverage throughout the 5 mile EPZ and in population centers between 5 and 10 miles.
B. Local law enforcement emergency vehicles with sirens and public address capability driving route alerting in the 5 to 10 mile areas not covered by fixed sirens.
C.
National Oceanic and Atmospheric Administration (NOAA) alert radios in institutional, educational, and commercial facilities.
D. The Emergency Alert System (EAS) which accesses local television and radio stations.
- 17.
Recovery is the process of reducing radiation exposure rates and concentration of radioactive material in the environment to levels acceptable for unconditional occupancy.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 18 of 33 FIGURE 7.1 Definitions Related to Protective Actions Recommendations (cont'd)
- 18.
Relocation Projected Dose is the projected effective committed dose from 1 year of exposure to radioactive material deposited as fallout from a plume, including whole body exposure to gamma radiation (groundshine), and internal dose from inhalation of resuspended material, but excluding internal dose from consuming contaminated foodstuffs.
- 19.
Return refers to people permanently reoccupying their normal residence within an area that was evacuated during the emergency condition.
- 20.
Re-entry refers to temporary entry into a restricted (evacuated) area under controlled conditions.
- 21.
Secondary Evacuation refers to relocating people from areas to avoid or reduce relocation projected dose.
- 22.
Sector is one of 16, 22.50 sectors around the plant which compose the 10 Mile EPZ.
- 23.
Sheltering provides radiation protection from an airborne plume and/or deposited radioactive materials. Sheltering also ensures effective public notification, via media, should the need for evacuation occur.
- 24.
Total Effective Dose Equivalent (TEDE) is the sum of external EDE and CEDE.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 19 of 33 FIGURE 7.2 Discussion of Protective Action Recommendations The following is a discussion of the various Protective Action Recommendations (PARs) that could be made to off-site authorities. The Protective Action Guidelines (PAGs) listed are derived from EPA guidelines (EPA 400).
- 1.
NO PROTECTIVE ACTIONS The recommendation for no protective actions is self-explanatory and is appropriate when projected plume doses do not exceed 1000 mrem (TEDE) or 5000 mrem (CDE) thyroid dose. For liquid releases, no protective actions are warranted if the concentration in raw river water at outflow of discharge canal is less than the concentration listed in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 (ODCM-04.01, Table 1).
- 2.
EVACUATION Evacuation is the movement of a population out of an area in order to reduce or eliminate direct or indirect radiation exposure. Timely evacuation of the population is the most effective protective action.
Initial PARs for a General Emergency involving loss of physical control or core damage are based on NRC Response Technical Manual RTM-93, Vol 1, Rev. 3,Section I.
Immediate evacuation of the general public is justified without dose projection.
EPA 400 indicates that evacuation of the general public will usually be justified when the projected dose to an individual is greater or equal to 1000 mrem TEDE (or 5000 Thyroid CDE). At these dose levels, the risk avoided due to the radiation exposure is usually much greater than the risk from evacuation itself.
Using the projected dose criteria stated above, MNGP should recommend evacuation to the State. In turn, they will independently assess and implement protective actions based on our recommendation, their independent assessment, and current off-site evacuation constraints.
- 3.
CLOSURE OF WATER INTAKES Water Intakes PAG: Concentration in raw river water exceeds the value listed in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 (ODCM-04.01, Table 1).
Closure of the water intakes is an appropriate recommendation in the case of a liquid release to the river which is expected to result in river water concentrations exceeding the MPC for unrestricted areas.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 20 of 33 FIGURE 7.2 Discussion of Protective Action Recommendations (Cont'd)
To avoid social and family disruption and the complexity of implementing separate PAGs for individual members of the population, the relocation PAG may be applied for all members of the population. While the relocation PAG is based on projected doses to adults, infant relocation projected doses are not more than two times higher than the adult projected dose.
Based on EPA 400 PAGs, MNGP should recommend relocation of general public from affected areas not previously evacuated when the projected dose is greater or equal to 2000 mrem TEDE from exposure or intake during the first year.
This projected dose includes doses from external radiation, and inhalation of resuspended materials.
- 5.
RETURN Return is allowed at levels below the secondary evacuation PAG (2000 mrem TEDE).
The decision to return segments of the public from previously evacuated areas will be determined by appropriate off-site agencies. Various cautions and dose reduction techniques will be assessed and, if necessary, communicated to the people upon their return.
- 6. DESIGNATION OF THE AFFECTED PROTECTIVE ACTION AREA The designation of the affected protective action area depends on the nature and extent of the incident and existing meteorological conditions. The area will be described by designating an affected keyhole shaped area and the affected geopolitical subareas within the EPZ.
a Affected Keyhole Area The affected keyhole area should resemble a keyhole consisting of a 3600 area surrounding the plant out to a distance of 2 or 5 miles and continuing in the downwind direction out to a distance determined by the PAGs. The affected downwind portion of the keyhole should include 1 sector on either side of the affected sector (i.e., total of 3 sectors). If the downwind direction is on a sector line then 2 sectors on each side of the affected sector should be included (i.e.,
total of 4 sectors).
b Affected Geopolitical Subareas Geopolitical subareas are subareas of the 10 mile EPZ defined by predetermine,-
geographic and/or political boundaries. The affected geopolitical subareas are defined by any and all subareas that intersect the affected keyhole area.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 21 of 33 FIGURE 7.2 Discussion of Protective Action Recommendations (Cont'd)
- 1.
(EXPOSURE PATHWAYS, Incident Phases, and Protective Actions POTENTIAL EXPOSURE PATHWAYS PROTECTIVE ACTIONS AND INCIDENT PHASES
- 1.
External radiation from facility Sheltering Evacuation Control of access
- 2.
External radiation from plume Sheltering Evacuation E. lLY Control of access,
- 3.
Inhalation of activity in plume Sheltering Administration of stable iodine Evacuation Control of access
- 4.
Contamination of skin and Sheltering clothes INTE MEDIATE Evacuation Decontamination of persons
- 5.
External radiation from ground Evacuation deposition of activity Relocation LTE Decontamination of land I_____
'E and property
- 6.
Ingestion of contaminated food Food and water controls and water
- 7.
Inhalation of resuspended Relocation activity Decontamination of land and property NOTE:
- 1. Based on EPA 400-R-92-001, May 1992
- 2. The use of stored animal feed and uncontaminated water to limit the uptake of radionuclides by domestic animals in food chain can be applicable to any of the phases.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 22 of 33 FIGURE 7.3 Protective Action Guidelines (PAGs)
PAG VALUES' RECOMMENDED COMMENTS PROTECTIVE ACTIONS Less than None required The State may choose
<1 REM (TEDE) to implement sheltering at their discretion. No recommendations are required from MNGP.
Greater than Recommend The State may chose WHOLE BODY2
>1 REM (TEDE) evacuation of the to implement sheltering P
CTED) general public, of the general public PROJECTED up to 5 REM (TEDE) or DOSE special population groups up to 10 REM (TEDE) if immediate evacuation is not practicable due to off-site constraints.
No sheltering recommendations are required from MNGP.
Less than None required The State may choose
<5 REM (CDE) to implement sheltering at their discretion. No recommendations are required from MNGP.
THYROID 3 Greater than Recommend The State may choose (CDE)
>5 REM (CDE) evacuation of the to implement sheltering PROJECTED general public, of the general public if DOSE immediate evacuation is not practicable due to off-site constraints.
No sheltering recommendations are required from MNGP.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 23 of 33 FIGURE 7.3 Protective Action Guidelines (PAGs) (Cont'd)
PAG VALUES' RECOMMENDED COMMENTS PROTECTIVE ACTIONS Less than None required The State may choose
<50 REM (CDE) to implement simple personal protective actions (washing). No recommendations are SKIN 4 required from MNGP.
(CDE)
Greater than Recommend The State may choose PROJECTED
>50 REM (CDE) evacuation of the to implement sheltering DOSE general public.
of the general public or simple personal protective actions if immediate evacuation is not practicable.
NOTE 1:
Protective Action Guides are based on EPA 400-R-92-001, May 1992.
NOTE 2:
TEDE = Total Effective Dose Equivalent; is the sum of the Effective Dose Equivalent from exposure to external source and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the Early Phase.
NOTE 3:
CDE = Committed Dose Equivalent to the Thyroid from radioiodine.
NOTE 4:
Committed Dose Equivalent to the skin from exposure to beta radiation from radioiodines and particulates.
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MONTICELLO NUCLEAR GENERATING PLANT A82-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 24 of 33 FIGURE 7.4 Emergency Worker Exposure Limits EXPOSURE LIMIT 1 EMERGENCY ACTIVITY1 COMMENTS 5 REM (TEDE)(2)(3)
All emergency activities This dose limit applies when a lower dose is not practicable through application of ALARA practices.
Protection of valuable This dose limit applies when property a lower dose is not practicable through application of ALARA practices.
Life saving or protection of Doses in excess of 25 REM large populations should be on a voluntary basis to persons fully aware of the risks involved.
NOTE 1:
Dose limits for emergency workers and activities are based on EPA 400-92-001, May 1992.
NOTE 2:
Sum of external effective dose equivalent and committed effective dose equivalent to non-pregnant adults from external exposure and intake during the duration of an emergency.
NOTE 3:
Exposure to the lens of the eye should be limited to 3 times the value listed and doses to the skin and/or extremities should be limited to 10 times the value listed.
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FIGURE 7.5 Transport Time and Monthly Average Flowrates 60 50 40 30 20 10 TIME (HRS) TO MINNEAPOLIS INTAKE (MULTIPLY BY.9 FOR Sr PAUL INTAKE)
MONTICELLO NUCLEAR GENERATING PLANT
,I A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 25 of 33 1000 I/mab
FIGURE Transport Time and Monthly Averaqe Flowrates (Cont'd)
MONTH JANUARY FEBRUARY MARCH APRIL MAY JUNE JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVG. RIVER FLOWRATE (CFS) 4663 4579 6336 10890 10157 7369 5352 3506 3334 5690 5438 4555 MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 26 of 33 I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 27 of 33 FIGURE 7.6 Liquid Release Protective Action Criteria
- 1.
PROTECTIVE ACTION BASED ON PROJECTED INTERNAL DOSE a
MPC Ratio in Raw River: < 1 MPC - No protective action required.
b MPC Ratio in Raw River: > 1 MPC - Recommend closure of water intakes.
c Projected Internal (Drinking) Dose:
< 250 mrem - No protective action required.
> 250 mrem - Implement preventive protective actions.
> 1000 mrem - Implement emergency protective actions.
- 2.
PROTECTIVE ACTION BASED ON PROJECTED EXTERNAL DOSE a
Projected Total External Dose
< 250 mrem - No protective action required.
> 250 mrem - Preventive protection actions are necessary.
> 1000 mrem - Emergency protective actions are necessary.
NOTE:
Obtain total external projected dose by calculating the swimming, boating and standing projected doses using the following time assumptions for shoreline activities.
Swimming -3 hrs/day Boating
- 1 hrs/day Standing -6 hrs/day RECOMMENDED PREVENTIVE PROTECTIVE ACTIONS
- 1.
Close Raw Water Intakes
- 2.
Restrict Intake of Drinking Water, and Foodstuffs obtained from river.
- 3.
Restrict swimming and boating on river.
- 4.
Restrict access to river.
- 5.
Restrict use of river for irrigation and industry.
RECOMMENDED EMERGENCY PROTECTIVE ACTIONS
- 1.
Close raw water intakes.
- 2.
Condemn drinking water obtained from river.
- 3.
Condemn affected foodstuffs (milk or meat from animals consuming contaminated water or foodstuffs)
- 4.
Prevent access to river.
- 5.
Condemn use of river for irrigation and industry.
- 6.
Substitute uncontaminated water and foodstuffs for contaminated water and foodstuffs.
- 7.
Condemn water usage from river.
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FIGURE 7.7 Ground Deoosition Modelina 40W I 20W M1 11M1 TM1 4 Idl 2 S 1
I i
1 10 100 Projected Gcound Depoaiticn uCi/. 2 10O(C The ground deposition graph was calculated using relations in R.G. 1.109 & R.G.
1.111. The following assumptions pertain to the graph:
- 1. Unstable (A,B,C) Pasqill stability class. This results in the highest depositions for elevated releases. For ground level releases, the stability class has little effect on calculated deposition rates. For a stable stability class, actual ground deposition could be zero out of many miles from the plant.
- 2. Elevated (100 meter) release height. For ground level releases, deposition rates will be slightly higher out to 20 miles, and somewhat less beyond 20 miles.
I/mab MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 28 of 33 10" M3 1.OE+10 Activity Released (cci) 1.0E407 0.1
MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 29 of 33 FIGURE 7.7 Ground Deposition Modeling (Cont'd)
- 3. The plume is deposited uniformly within half-width of a sector arc (about 11 degrees), for constant wind directions. Actual plume widths for unstable stability classes are significantly wider than this. This assumption causes the projected area ground contamination to be at least as high as the highest (centerline) actual deposition that would occur under stable conditions for deposition in accordance with a normal distribution with distance from the centerline.
NOTE: If several wind shifts occurred during the release, determine the approximate number of sectors into which the plume deposited material for each release period of interest. Divide this value by 0.5 and divide the result into the ground depositions predicted by the graph, to obtain an estimate of the degree the deposition was "diluted". For example, if the plume was spread out over 2 sectors, the ground deposition values obtained from the graph should be divided by 4. Once ground contamination as a function of distance has been estimated, use MIDAS (plume model) to help predict footprint actual width.
- 4. Wind speeds and stability classes vary often. The Van der Hoven study concludes there is a 50/50 chance of a significant wind shift within 2-4 hours at any given location.
Therefore, the plume could be spread out more than the graph assumes and alter the resulting deposition. Rain showers could increase deposition greatly.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 30 of 33 FIGURE 7.8 Secondary Evacuation Dose Projection Relocation Proj Relocation Proj-ected Dose per Ground shine Inhalation Dose ected Dose Initial Exp. Rate Initial Exp. Rate Dose (mrem per (mrem per uCi/
(mrem per uCi/
(mr/hr per uCi/
(mrem per Isotope uCi/m 2)
M2)
M2)
M2) mr/hr)
S r-9 0 1 1 11 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ba-140 Ce-144 34 7.4 14 1.3 118 52 11 3.3 1.4 1.4 34 7.4 15 1.3 118 52 11 4.7 0.0162 0.0055 0.0023 0.0047 0.0183 0.0072 0.0279 0.0023 2100 1300 6700 280 6400 7200 390 2000 NOTES:
- 1. Ground shine is the whole body dose (1 meter above the ground) received after a 1-year exposure to unit ground contamination (uCi/m2) as measured at the beginning of the exposure period.
- 2.
Inhalation is the committed effective dose (i.e., corresponding whole body dose) received from the inhalation for 1 year of resuspended unit ground contamination (uCi/m 2) as measured at the beginning of the exposure period. A re-suspension rate of 1 E-6/meter is assumed.
- 3. The Relocation Projected Dose per Initial Exposure Rate column is the total committed effective dose that would be received after a 1 -year exposure to contamination that caused an initial unit exposure rate (mr/hr, i.e., gamma only) at 1 meter above the ground. (The effective mrem per mr/hr for a mixture would be equal to a weighted average of the values in this column, which is computed by multiplying the value in this column times the ratio of the individual isotope to the total.)
- 4. The projected doses pertain to adults. Infant projected doses are not more than two times higher than the adult doses (other than for iodine which does not contribute greatly to overall dose for infants or adults).
- 5.
Doses could be significantly lowered due to shielding from homes, decontamination, etc.
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MONTICELLO NUCLEAR GENERATING PLANT I -
A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 31 of 33 FIGURE 7.8 Secondary Evacuation Dose Projection (Cont'd)
- 6. Elimination of the source term due to weathering as well as radioactive decay is assumed.
- 7. The doses listed include the dose from radioactive daughters.
SECONDARY EVACUATION DOSE ASSESSMENT Direct Frisk Ground Contam Reloc Dose Initial Doses Isotope Smear (DPM)
(CPM)
(uCi/m 2)
(mrem)
Rate (mrem/hr)
Ru-106 130,000 29,000 67 1000 0.15 Cs-134 17,000 3,700 8.5 1000 0.16 1-131 1,500,000 330,000 770 1000 3.6 Rules of Thumb
- 1. The most restrictive nuclide in terms of projected relocation dose per measured initial dose rate is Cs-1 37 (about 7000 mrem per mrem/hr). Cesium-134 is the most restrictive nuclide in terms of projected relocation dose per unit contamination (about 120 mrem per
ýiCi/m 2).
- 2. Assuming a 10% smear collection efficiency, 10% counter efficiency, and 20 cm2 area "seen" by the probe for a direct risk, the following relationships were developed:
a Direct frisk tCi/m2 = net CPM 400 Where net CPM is frisker count rate about 1" from surface in question.
b Smear [tCi/m 2 = smear net CPM 200 Where smear net CPM is frisker count rate of 100 cm2 smear from a smooth surface.
- 3. Based on assumed radiological characteristics of releases from fuel melt accidents, gamma exposure rates in areas where the projected relocation dose is in the range of 1-5 Rems would be between about 2 and 10 mrem/hr during the first few days after shutdown following an SST-2 accident severity type. Ground deposition values in the range of 200-800 [tCi/m 2 could also be expected.
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FIGURE 7.9 Relocation Protective Action Guidelines Relocation Projected Dose (TEDE) 2000 mrem Recommended Actions Relocate General Public COMMENTS:
- 1. To avoid social and family disruption and the complexity of implementing separate PAGs for individual members of the population, the relocation PAG may be applied for all members of the population. While the relocation PAG is based on projected doses to adults, infant relocation projected doses are not more than two times higher than adult projected doses.
- 2.
Return is allowed at levels below the PAG.
I/mab MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 32 of 33 I
FIGURE 7.10 Forms Utilized in Procedure NUMBER
- 1. 5790-102-2
- 2. 5790-102-3
- 3.
5790-204-1
- 4. 5790-202-1
- 5. 5790-410-3 TITLE MONTICELLO EMERGENCY NOTIFICATION REPORT FORM EMERGENCY NOTIFICATION FOLLOW-UP MESSAGE MONTICELLO OFF-SITE PROTECTIVE ACTION RECOMMENDATION CHECKLIST OFF-SITE SURVEY RESULTS DATA LOG GROUND DEPOSITION SAMPLE RESULTS LOG MONTICELLO NUCLEAR GENERATING PLANT A.2-807 TITLE:
OFF-SITE DOSE ASSESSMENT AND Revision 8 PROTECTIVE ACTION RECOMMENDATIONS Page 33 of 33 I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
EOF SECURITY Revision 3 Pag I
f1 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION P) 1.0 PU R PO SE........................................................
2.0 APPLICABILITY...................................................
3.0 ORGANIZATION AND RESPONSIBILITIES...........................
4.0 DISC USSIO N......................................................
5.0 PRECAUTIONS....................................................
6.0 INSTRUCTIO NS...................................................
6.1 Initial Activation Instructions...................................
6.2 Activation of the Front Access Point............................
6.3 Activation of the EOF Receiving Area Access Point...............
6.4 General Instructions..........................................
6.5 Security Safeguards Contingency Event Instructions..............
7.0 FIG U R ES.........................................................
7.1 EO F Floor Plan..............................................
7.2 Monticello Training Center Floor Plan...........................
7.3 EO F Signs..................................................
This revision incorporates Volume F Memos:
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:,.i--
36-.Z4ý Resp Supv:
N IFrew" 1/yrsI ARMS:
A.2-809
-Doc Type: 1060 Admin Initials: k 1 Date:,)-.4 I/mab
.GE 2
2 2
2 2
2 2
3 4
5 6
8 8
9 10 Prepared By:
Reviewed By:
OC Review Req'd: YES
".C Meeting Number: 2-*3 /--/
Date:/z z
Approved By:
/ze Date:/
7~~#~ :j~):2~K~
OR ADMINISTRATIVE USE^0NLY~-~%r
MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
EOF SECURITY Revision 3 Page 2 of 10 1.0 PURPOSE This procedure provides instructions and guidance for the EOF Security Coordinator and Security Force Members during activation and operation of the Emergency Operations Facility (EOF) at the Monticello Nuclear Generating Plant (MNGP). Steps in this procedure satisfy commitment M85029A. Procedure steps satisfying this commitment is identified with a $.
2.0 APPLICABILITY An Alert or higher emergency has been declared at the MNGP and/or the EOF has been activated.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The EOF Security Coordinator is responsible for:
3.1.1 Implementation of this procedure.
3.1.2 Overall direction and coordination of the EOF security activities.
3.2 The EOF Security Force is responsible for assisting the EOF Security Coordinator with the completion of assigned duties.
4.0 DISCUSSION The EOF Security Coordinator position is staffed by MNGP personnel that are qualified as Security Group Leaders/ EOF Security Coordinators. Personnel qualified to fill these positions are identified in the Security Group section of Form 5790-001 -01 (EMERGENCY RESPONSE ORGANIZATION).
Necessary Security Force support will be provided by personnel from the site contract security force or other available personnel as appropriate.
5.0 PRECAUTIONS Once activated, only authorized emergency response personnel should be allowed into controlled areas of the EOF. Unauthorized personnel (i.e. media, general public, etc.) should be directed to the designated off-site facilities established for their use.
6.0 INSTRUCTIONS 6.1 Initial Activation Instructions 6.1.1 Upon arrival at the EOF refer to the EOF Tag Board and determine the initial Security Coordinator staffing. Assume the Security Coordinator position or determine if the designated Security Coordinator is in need of assistance.
6.1.2 Initiate Form 5790-809-01 (EOF SECURITY COORDINATOR ACTIVATION CHECKLIST).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
EOF SECURITY Revision 3 Page 3 of 10 6.2 Activation of the Front Access Point 6.2.1 Move the Security Desk (normally stored in the office across from the EOF copy/fax room) to the front EOF access point. The front access point is in the hallway outside of the EOF area by telephone extension 1203. Refer to FIGURE 7.1 for the front access point location.
6.2.2 Obtain a supply of TLDs, Dosimeters, the EOF Sign-In/Out Forms, any needed administrative supplies and the dosimeter charger from the EOF Administrative supply locker.
6.2.3 Staff the access point desk and issue dosimetry/log personnel into and out of the EOF in accordance with instruction provided in Form 5790-809-01.
6.2.4 The south patio entrance in the front of the building (door #2 on FIGURE 7.2) is the preferred entrance to the EOF. Ensure that this door is unlocked and post sign A (see FIGURE 7.3) on the outside of this door.
6.2.5 Secure (lock if possible) and post sign B (see FIGURE 7.3) on the following Training Center entrance/exit points:
NOTE: Sign B should be posted on the outside of these doors.
A.
Door 1 on FIGURE 7.2, the main training center entrance.
B.
Door 3 on FIGURE 7.2, the training center entrance near the multi-purpose room.
C.
Door 6 on FIGURE 7.2, the Simulator Staff entrance.
6.2.6 Verify that doors 4, 5, 7, and 9 are locked. These doors are normally locked and should remain locked through out the EOF activation.
6.2.7 Unlock door 8, the back EOF entrance door, and post sign E on both sides of this door.
6.2.8 Secure (lock if possible) and post sign E (see FIGURE 7.3) on the following EOF entrance/exit points as follows:
NOTE: Sign E should be posted on both sides of these doors.
A.
Door 10, the back hallway door between the EOF area and the reminder of the training center.
B.
Door 12, the door between the Simulator Computer Room and the Simulator Staff Offices.
C.
Door 13, the door between the Simulator and the EOF.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
EOF SECURITY Revision 3 I
Page 4 of 10 D.
Door 14, the Simulator security door.
NOTE: Door 15, the EOF hallway door to the MTC front entrance, should remain open and is not required to have a sign post on it at this time.
6.3 Activation of the EOF Receiving Area Access Point NOTE: The Receiving Area Access Point is in the hallway immediately across from the EOF Countroom. Refer to Form 5790-802-07 (EOF RECEIVING AREA FLOOR PLAN).
6.3.1 If the Front Access Point was used, secure the front access point and move the Security Desk and other needed equipment to the Receiving Area Access Point. Proceed to Step 6.3.5.
6.3.2 If the Front Access Point has not been established, move the Security Desk (normally stored in the office across from the EOF copy/fax room) to the Receiving Area Access Point.
6.3.3 Obtain a supply of TLDs, Dosimeters, the EOF Sign-In/Out Forms, any needed administrative supplies and the dosimeter charger from the EOF Administrative supply locker.
6.3.4 Staff the access point desk and issue dosimetry/log personnel into and out of the EOF in accordance with instruction provided in the EOF Security Coordinator Activation Checklist (Form 5790-809-01).
6.3.5 The back EOF entrance door (door #8 on FIGURE 7.2) is the preferred entrance to the EOF. Ensure that this door is unlocked and post sign D (see FIGURE 7.3) on the outside of this door.
6.3.6 Secure (lock if possible) and post sign C (see FIGURE 7.3) on the following Training Center entrance/exit points:
A.
Door 1 on FIGURE 7.2 the main training center entrance.
B.
Door 2 on FIGURE 7.2 the main training center entrance.
C.
Door 3 on FIGURE 7.2 the training center entrance near the multi-purpose room.
D.
Door 6 on FIGURE 7.2 the Simulator Staff entrance.
E.
Verify that doors 4, 5, 7, and 9 are locked. These doors are normally locked and should remain locked through out the EOF activation.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
EOF SECURITY Revision 3 Page 5 of 10 6.3.7 Secure (lock if possible) and post signs E and F (see FIGURE 7.3) on the following EOF entrance/exit points as follows:
NOTE: Signs E and F should be posted on both sides of these doors.
A.
Door 10, the back hallway door between the EOF area and the reminder of the training center.
B.
Door 12, the door between the Simulator Computer Room and the Simulator Staff Offices.
C.
Door 13, the door between the Simulator and the EOF.
D.
Door 14, the Simulator security door.
E.
Door 15, the EOF hallway door to the MTC front entrance.
6.3.8 Assist the Radiation Protection Specialist with the setup of the EOF Receiving Area as necessary.
6.3.9 As personnel arrive at the EOF ensure that they are monitored for contamination prior to entering the EOF or as directed by the EOF Radiation Protection Staff.
6.3.10 If personnel are found to be contaminated, immediately notify the EOF Radiation Protection Staff.
6.4 General Instructions 6.4.1 Maintain strict access control of the EOF throughout the event.
$ 6.4.2 Ensure Fitness for Duty (FFD) verification is conducted for all persons reporting to the EOF.
6.4.3 Ensure that the designated Access Point is continuously staffed.
6.4.4, Throughout the event provide periodic briefings to the EOF Coordinator on the status of EOF security.
6.4.5 Provide requested information to the EOF Coordinator in preparation of status updates in the EOF Command Center. Attend the updates and participate as necessary.
6.4.6 Maintain periodic contact with the Security Group Leader in the TSC.
6.4.7 Serve as the interface with the NRC Security/Safeguards personnel present in the EOF or by telephone with the NRC Regional or Headquarters personnel. Coordinate NRC interface with the Security Group Leader and/or Corporate Security as needed.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
EOF SECURITY Revision 3 Page 6 of 10 I
6.4.8 Serve as the liaison with the Local, State, and/or Federal law enforcement agencies as necessary.
6.4.9 If media personnel arrive at the EOF, immediately notify the EOF Coordinator and the Emergency Manager. Do not allow media personnel to access the EOF without the Emergency Manager's authorization.
6.4.10 Assist with off-site contractor/vendor access screening to the site as necessary.
6.4.11 In cooperation with the Security Group Leader and Emergency Manager determine if EOF Security should establish positive control over the Owner Controlled Area and/or the designated Off-site Assembly Point. If so, coordinate obtaining additional security personnel for those functions.
6.4.12 If NRC personnel arrive at the EOF, notify the EOF Coordinator immediately.
6.5 Security Safeguards Contingency Event Instructions NOTE: If the emergency involves a security/safeguards event, the EOF Security Coordinator role becomes more significant to EOF operation. In these cases the EOF Security Coordinator should advise the Emergency Manager and EOF Staff directly.
6.5.1 If the event involves a security/safeguards event, consider establishing a Security Command Post in the EOF.
NOTE: If a NRC Site Team is not present in the EOF, classroom 9 may be used for the security command post. If the NRC is present, classroom 10 may be used.
6.5.2 Serve as the liaison with Local, State, and/or Federal law enforcement agencies.
6.5.3 Continuously update the Emergency Manager on the status of plant/site security, contingency plan implementation and other matters related to the event.
6.5.4 Monitor the event and evaluate the need to re-classify the emergency in accordance with A.2-1 01 (CLASSIFICATION OF EMERGENCIES).
Make recommendations to the Emergency Manager as appropriate.
6.5.5 Maintain contact with Corporate Security. Assist with relocating Corporate Security personnel to the EOF as necessary.
6.5.6 Monitor Site Security staffing and augment as necessary.
6.5.7 Consider the use of armed security in the EOF if necessary.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
EOF SECURITY Revision 3 Page 7 of 10 6.5.8 Ensure that all safeguards materials used during the event are properly controlled. Contact the EOF Coordinator for assistance with needed equipment.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
EOF SECURITY Revision 3 Page 8 of 10 7.0 FIGURES FIGURE 7.1 EOF Floor Plan I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
PEOF SECURITY Revision 3 P ag 9If1 FIGURE 7.2 Monticello Training Center Floor Plan 5
4 I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-809 TITLE:
EOF SECURITY Revision 3 Page 10 of 10 FIGURE 7.3 EOF Signs SIGN A SIGN B SIGN C EOF IS ACTIVATED DO NOT USE THIS DOOR USE RECEIVING AREA ENTRANCE ON NORTH SIDE OF BUILDING SIGN D SIGN E SIGN F EOF VENTILATION BOUNDARY EMERGENCY VENTILATION SYSTEM IN OPERATION CLOSE DOOR AFTER USE I/mab FOR EMERGENCY ENTRANCE AUTHORIZED PERSONNEL ONLY ENTER AND TURN RIGHT FOR EOF ACCESS EOF IS ACTIVATED DO NOT USE THIS DOOR USE SOUTH PATIO ENTRANCE IN FRONT OF BUILDING EOF EMERGENCY ENTRANCE AUTHORIZED PERSONNEL ONLY EOF IS ACTIVATED DO NOT USE THIS DOOR UNLESS AUTHORIZED BY THE EOF COORDINATOR
MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY IN Revision 3 THE EOF Page 1 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION PAGE 1.0 PU R PO SE........................................................
2 2.0 APPLICABILITY...................................................
2 3.0 ORGANIZATION AND RESPONSIBILITIES...........................
2 4.0 DISCUSSIO N......................................................
3 5.0 PRECAUTIONS....................................................
3 6.0 INSTRUCTIONS...................................................
4 6.1 Termination of an Alert or Site Area Emergency..................
4 6.2 Transition to the Recovery Phase..............................
5 6.3 Recovery Manager Instructions................................
8 Prepared By:
,/__Reviewed By:,ý ALARA Coord Revi'9w By:
OC Review Req'd: YES OC Meeting Number:
Date:
Approved By:
Date:,
ýFOR ADMIISRATIVE USEPNYV 2Z~
This revision incorporates Volume F Memos:____
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:
Resp Supv:
EP '
lAssoc Ref. A2 11SR N Freq: 1 /vrs/
ARMS: A 2-811 Doc Type: 1060 Admin Initials:
Date:
I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY IN Revision 3 THE EOF Page 2 of 10 1.0 PURPOSE 1.1 The purpose of this procedure is to provide instructions for the termination of an Alert or Site Area Emergency or the transition to the Recovery Phase from a Site Area or General Emergency. The procedure specifies the criteria for termination of the Emergency Phase and guidance for the Emergency Manager and Recovery Manager on on-site Recovery planning.
2.0 APPLICABILITY 2.1 An Alert or Site Area Emergency has been declared and conditions indicate the immediate Emergency Phase may be terminated, or 2.2 A Site Area or General Emergency has been declared and conditions indicate the immediate Emergency Phase is over and the transition to the Recovery Phase may be made.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Manager is responsible for:
3.1.1 Implementation of Section 6.1 or 6.2 of this procedure.
3.1.2 The decision to terminate the event or enter Recovery.
3.1.3 Assisting the Recovery Manager with the establishment of the dissolution of the Emergency Response Organization back into the normal Site (Recovery) Organization.
3.2 The Emergency Director is responsible for:
3.2.1 The decision to terminate an Alert (when the Emergency Manager position is not yet staffed).
3.2.2 Assisting the Emergency Manager in the decision to terminate the event or enter the Recovery Phase.
3.2.3 Participation in the turnover of overall management from the Emergency Response Organization to the Site (Recovery)
Organization.
3.3 The Recovery Manager is responsible for:
3.3.1 Implementation of Section 6.3 of this procedure.
3.3.2 Overall direction and coordination of on-site recovery activities.
3.3.3 Coordination of site recovery activities with other utility departments and off-site agencies and organizations.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY IN Revision 3 THE EOF Page 3 of 10 3.4 The EOF Group Leaders are responsible for:
3.4.1 The development of short and long term recovery action item lists which identify corrective and/or recovery actions necessary to return the plant and site to a normal operation or shutdown status.
3.5 The Site Managers are responsible for:
3.5.1 Coordination of on-site recovery activities under the direction of the Recovery Manager and NMC Generation Management.
3.6 The Plant Scheduling Department is responsible for:
3.6.1 Development of outage and maintenance schedules which support the Recovery action item lists.
4.0 DISCUSSION 4.1 This procedure provides guidance and instructions for the termination of an emergency classification (Alert or Site Area Emergency) or the transition from a Site Area or General Emergency classification to Recovery.
For an Alert classification the close-out of the event will usually involve the termination of the emergency class and dissolution of the Emergency Response Organization (both site and corporate). Any necessary follow-up activities would be limited to in-plant or on-site areas and coordinated and managed by the site organization. In some cases, Recovery may be appropriate for the close-out of an Alert classification if substantial damage has occurred to plant structures or equipment. Conversely, in some cases, a Site Area Emergency may be terminated if no significant damage has occurred to the plant systems or structures. The Emergency Manager and Emergency Director should make this determination based on the extent of damage and other considerations.
Generally, for the Site Area and General Emergency classifications the proper close-out of the event involves the establishment of a Recovery organization (under the direction of a Recovery Manager) and the transition to the Recovery Phase. During Recovery, overall management of recovery activities is the responsibility of the Recovery Manager.
5.0 PRECAUTIONS 5.1 The termination 6f an emergency classification or the transition to Recovery should be closely coordinated with the State and local authorities and federal agencies.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY IN Revision 3 THE EOF Page 4 of 10 6.0 INSTRUCTIONS 6.1 Termination of an Alert or Site Area Emergency NOTE: If substantial damage has occurred to plant systems, equipment or if significant radiological releases or contamination have occurred on-site, recovery may be appropriate verses termination.
6.1.1 Assess plant and environmental conditions. When all of the following criteria are met consider termination of the emergency classification.
A.
The plant is in a stable condition with at least one fission product barrier intact, and B.
No radioactive releases are being made to the environment in excess of plant Offsite Dose Calculation Manual (ODCM) limits.
C.
The potential for future degradation of plant conditions is small.
6.1.2 When the criteria for termination are met, consult with the Emergency Director to obtain their concurrence on event termination (based on in-plant conditions and activities in-progress.
6.1.3 When the Emergency Director concurs consult the the NRC regarding the termination of the emergency as follows:
A.
If the NRC Site Incident Response Team has not been activated or is not present on-site, confer with the Sr. NRC Resident Inspector and/or NRC Headquarters.
B.
If the NRC Site Incident Response Team is present consult the NRC Director of Site Operations or Senior NRC official present.
6.1.4 When the Emergency Director and NRC concur, contact the State Operations Chief (in the State EOC). Determine if off-site protective actions are in effect or if other circumstances exist which make on-site termination of the event inadvisable (at this time).
6.1.5 When the Emergency Director, NRC and State concur that the emergency classification may be terminated, terminate the emergency.
6.1.6 Upon termination of the emergency make an announcement in the EOF to that effect. Note the time the emergency is terminated.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY IN Revision 3 THE EOF Page 5 of 10 6.1.7 Direct the Radiation Protection Support Supervisor to compose a new Form 5790-102-02 (EMERGENCY NOTIFICATION REPORT FORM) for the change in classification (termination).
A.
Submit the form for EM approval, and B.
Direct the EOF Off-site Communicators to transmit the notification.
6.1.8 Direct the Technical Support Supervisor to ensure Form 3195 is completed reflecting the termination of the emergency.
A.
Review and approve the completed form.
B.
Direct the ENS Technical Communicator to transmit the information on the form to NRC Headquarters via the ENS within one hour of event termination.
6.1.9 Ensure all individuals, who were notified of the event, are notified of the termination.
6.1.10 If significant damage has occurred to plant systems or equipment, and the plant will remain shutdown for an extended period of time, initiate outage planning in accordance with applicable site procedures.
6.1.11 Direct the EOF Coordinator to collect all emergency related forms, checklists and documentation generated at the EOF during the event and forward to Plant Emergency Preparedness for review and analysis.
6.1.12 The development and submittal of follow-up reports to the NRC should be coordinated through the plant Operations Committee in accordance with existing site administrative procedures.
6.2 Transition to the Recovery Phase 6.2.1 When plant conditions are stable, significant radioactive releases are terminated, and the immediate emergency has been mitigated, direct the Emergency Director (TSC Group Leaders) and the EOF Technical Support Supervisor to assess conditions in their respective areas and identify short and long term recover items. Use Form 5790-602-01 (RECOVERY ACTION ITEM FORM).
6.2.2 Direct the Emergency Director (Support Group Leader) to collect the Forms 5790-602-01.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY IN Revision 3 THE EOF Page6of10 6.2.3 Continue to assess plant and environmental conditions. When all of the following criteria are met, transition to the recovery phase should be considered.
A.
The plant is in a stable condition with at least one fission product barrier intact, and B.
No radioactive releases are being made to the environment in excess of plant ODCM limits.
C.
The potential for future degradation of plant conditions is small.
D.
NRC Headquarters (or the Director of Site Operations of the on-site response team) concurs with the transition to Recovery.
6.2.4 When the criteria for Recovery is met, contact the Emergency Director to obtain the concurrence on-going to Recovery (based on in-plant and on-site conditions and activities in-progress).
NOTE: If the Emergency Director does not concur with making the transition to Recovery (at this time) determine when the Emergency Director estimates in-plant and/or on-site conditions will permit making the transition to Recovery, and what resources or support the EOF can provide to assist in resolving the issues preventing the transition to Recovery from proceeding.
6.2.5 When the Emergency Director concurs with making the transition to Recovery direct the Emergency Director (Support Group Leader) to deliver the Forms 5790-602-01.
6.2.6 In cooperation with plant and corporate management, select and notify a designated Recovery Manager. Refer to A.2-001 (EMERGENCY ORGANIZATION) to identify qualified candidates). Request the Recovery Manager report to the EOF.
6.2.7 Upon arrival at the EOF the Recovery Manager should be briefed by the Emergency Manager and Emergency Director and implement Section 6.3 of this procedure.
6.2.8 Assist the Recovery Manager in compiling one comprehensive Recovery Action Item list from the Recovery Action Item Forms 5790-602-01 developed by the TSC, OSC and EOF. The Emergency Manager, Emergency Director; and key EOF and TSC Group Leaders (as necessary) should assist in this effort.
NOTE: A meeting with key EOF, TSC (and NRC personnel if present) is recommended to compile the integrated recovery action list prior to making the transition to Recovery.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY IN Revision 3 THE EOF Page 7 of 10 6.2.9 When the initial comprehensive recovery action item list is complete, the Emergency Manager (Recovery Manager and other key utility personnel) should consult the NRC regarding the transition to Recovery as follows:
NOTE: If the NRC Incident Response team has not been mobilized or has not arrived, the proposal to enter the Recovery Phase should be discussed with the NRC Headquarters. If the NRC Incident Response Team is on-site, the EM and ED should meet with the Director of Site Operations to discuss the transition to Recovery.
A.
If the NRC Site Incident Response Team has not been activated or is not present on-site, confer with the Sr. NRC Resident Inspector, NRC Headquarters and NRC Region Ill.
B.
If the NRC Site Incident Response Team is present consult the NRC Director of Site Operations or Senior NRC official present.
6.2.10 When the NRC concurs that transition to Recovery is appropriate (on-site) contact the State Operations Chief (in the State EOC).
Determine if off-site protection actions are in effect or if other circumstances exist which make the transition to Recovery inadvisable (at this time).
6.2.11 When the Emergency Director, NRC and State concur that the transition to Recovery may be made direct the Radiation Protection Support Supervisor to complete Form 5790-102-02 reflecting the transition to Recovery and:
A.
Review and approve the completed form.
B.
Direct the EOF Off-Site Communicator to transmit the information on the form to the appropriate off-site agencies.
6.2.12 Direct the Technical Support Supervisor to complete Form 3195 (EVENT NOTIFICATION WORKSHEET) reflecting the transition to Recovery and:
A.
Review the completed form for completeness and sign the approval space.
B.
Direct the ENS Technical Communicator to transmit the information on the form to NRC Headquarters via the ENS within one hour of event termination.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY IN Revision 3 THE EOF Page 8 of 10 6.2.13 Make an announcement in the EOF informing the EOF staff of the transition to Recovery:
"ATTENTION EOF PERSONNEL. THE (SPECIFY THE EMERGENCY CLASS) IS TERMINATED. THE PLANT IS IN RECOVERY. THE EMERGENCY RESPONSE ORGANIZATION IS DISSOLVED AND A RECOVERY ORGANIZATION IS BEING ESTABLISHED. SECURE (SPECIFY FUNCTIONAL AREA) IN THE EOF."
6.2.14 Inform the NMC Executive Spokesperson (at the JPIC) that the transition to Recovery is being made and the name of the Recovery Manager.
6.2.15 Direct the EOF Coordinator to collect all emergency checklists, documentation and records generated during the event and forward them to Plant Emergency preparedness for analysis and retention.
6.2.16 The development and submittal of follow-up reports to the NRC should be coordinated through the plant Operations Committee in accordance with existing plant administrative procedures.
6.2.17 Assist the Recovery Manager with the formation of the Recovery Organization and other administrative recovery details.
6.3 Recovery Manager Instructions 6.3.1 Upon arrival at the EOF, obtain a briefing from the Emergency Manager (and Emergency Director if present) on the status of making the transition to Recovery.
6.3.2 Review the completed Recovery Action Item Lists (with the Emergency Manager, Emergency Director and other key EOF/TSC Group Leaders) to determine the extent of recovery activities required.
6.3.3 Upon completion of the Recovery Action Items list reviews, and when the NRC and State concur, coordinate the transition to Recovery.
Ensure the Emergency Manager directs the conduct of required notifications to the State, County and Federal agencies.
6.3.4 Coordinate the dissolution of select portions of the Emergency Response Organization back into the normal site organization and if necessary:
A.
Direct the Plant organization be modified to support outage activities including:
- 1. Plant outage scheduling.
- 2.
Augmentation of plant maintenance staff with maintenance supervisors and traveling maintenance personnel.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY, IN Revision 3 THE EOF Page 9 of 10
- 3.
Augmentation of the plant Radiation Protection staff with contract HP support.
B.
Direct the Site organization to assume outage support roles including:
- 1. Administrative support (logistics, purchasing, budgeting, etc.)
- 2.
QNQC support.
- 3.
Security support.
6.3.5 If significant damage has occurred to plant systems or equipment, and the plant will remain shutdown for an extended period of time, ensure outage planning is initiated in accordance with plant scheduling department procedures.
6.3.6 Consider assigning a Task Force (consisting of site and corporate personnel from various functional areas) to evaluate the event and:
A.
Develop required reports (e.g., LER, etc.) for the event.
B.
Provide follow-up information to outside organizations (e.g.,
INPO Network, etc.).
C.
Evaluate the Emergency Plan activation and generate the required reports (for NMC and NRC review).
D.
Serve as the primary interface with the NRC Advanced Inspection Team (if dispatched).
6.3.7 If the NRC dispatches an Advanced Inspection Team (AIT) ensure a liaison (or group) is assigned to prepare for and assist the NRC team when they arrive including:
A.
Lodging and workspace for the NRC team members.
B.
Coordination of quarantine list (developed by the NRC) with plant scheduling.
C.
Scheduling and coordination of personnel interviews (as requested by the NRC).
D.
Submittal or required reports to the NRC.
6.3.8 Coordinate the assignment of personnel to initiate post-event follow-up activities with the following organizations:
A.
The State of Minnesota including the Division of Emergency Management, Health Department, MPCA.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-811 TITLE:
EVENT TERMINATION OR RECOVERY IN Revision 3 THE EOF Page 10 of 10 B.
County and local authorities including Civil Defense, law enforcement, social services, etc.
C.
Industry organizations including INPO, NEI, etc.
6.3.9 Ensure the required reports are generated (in accordance with existing site and corporate directives) and submitted to the following organizations as necessary:
A.
Plant Operations Committee.
B.
Monticello Safety Audit Committee.
C.
Environmental Regulatory Affairs Department.
D.
Utility Executive Management.
E.
NRC and other Federal agencies.
6.3.10 Serve as the management liaison between the site organizations and corporate organizations on matters related to the event including:
A.
Outage planning and scheduling (if required).
B.
Budgeting and procurement authorizations.
C.
Regulatory affairs (licensing issues, etc.).
D.
Post-event issues including insurance claims, plant startup schedules, public affairs, etc.
6.3.11 Ensure post-event environmental radiological monitoring program (REMP) is coordinated (as necessary) by the REMP Administrator.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 1 of 12 EMERGENCY PLAN IMPLEMENTING PROCEDURE - TABLE OF CONTENTS SECTION Pi 1.0 PU R PO SE........................................................
2.0 APPLICABILITY...................................................
3.0 ORGANIZATION AND RESPONSIBILITIES...........................
4.0 D ISCUSSIO N......................................................
5.0 PRECAUTIO NS....................................................
6.0 INSTRUCTIONS...................................................
6.1 Initial Agency Liaison Activation and Staffing.....................
6.2 Expanded EOF Set-up and Activation...........................
6.3 General Liaison Instructions...................................
6.4 News Media Instructions......................................
7.0 FIG U R ES.........................................................
7.1 Emergency Operations Facility Floor Plan.......................
7.2 EOF Training Rooms 8 and 9 Floor Plan........................
7.3 EOF Training Rooms 11 and 12 Floor Plan......................
7.4 EOF Security Office and Training Room 14 Floor Plan............
7.5 Expanded EOF Activation for NRC Co-Location..................
AGE 2
2 2
2 3
3 3
4 5
5 7
7 8
9 10 11 C>
PrpreCy Reviewed By:*)
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Approved By:
Date:
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This revision incorporates Volume F Memos:__
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:-
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EP lAssoc Ref A.2
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ISR: N Freq:, /yrs/.
ARMS:
A.2-812 Doc Type: 1060 Admin Initials.
Date:
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MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 2 of 12 1.0 PURPOSE This procedure provides instructions and guidance for liaison activities between MNGP emergency response personnel and off-site agencies responding to the EOF 2.0 APPLICABILITY 2.1 An Alert has been declared at the Monticello Plant and the EOF has been activated and staffed, and 2.2 Off-site emergency response organizations (e.g., NRC, State, Counties, etc.)
or news media are responding to the Monticello EOF.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Emergency Manager is responsible for:
3.1.1 Overall direction and coordination of NMC's emergency response activities including operation of the EOF.
3.2 The EOF Coordinator is responsible for:
3.2.1 Coordination of the activation and operation of the EOF including setup"-.)
of the EOF for expanded activation.
3.3 The Agency Liaison is responsible for:
3.3.1 Implementation of this procedure.
3.3.2 Serving as the initial off-site agency contact including reception, briefing and facilitating co-location with their MNGP counterpart(s).
4.0 DISCUSSION This procedure provides instructions for the Off-site Agency Liaison activities during an emergency at the MNGP. It includes guidance for initial staffing of the Agency Liaison position and other emergency response activities for which the Agency Liaison is responsible.
Two stages of EOF activation are defined in this procedure. Normal (full) EOF activation occurs anytime the EOF is activated (at the Alert classification or higher).
Expanded EOF activation occurs when off-site federal agencies are mobilized and respond to the EOF (usually at a Site Area Emergency or higher classification).
In the expanded activation mode the designated classrooms (immediately adjacent to the EOF Command Center) are arranged and additional telecommunications installed to accommodate the off-site agency response. The EOF Coordinator is responsible to monitor the progress of off-site agency response and setup for expanded activation of the EOF prior to the arrival of agency personnel (initial NRC Site Team).
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MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 3 of 12 The expanded NRC activation site team is an organization the NRC employs in the event of an extended incident. The regional office will initially respond to a significant on-site emergency with a team of 12-18 individuals that would arrive at the site in about 6-12 hours. A full complement of NRC staff may be on-site within 24-36 hours of the onset of an event.
Normally, the State of Minnesota, Wright and Sherburne Counties will activate their Emergency Operations Centers at an Alert or higher. When these centers are activated, they will send representatives to the EOF to serve as communication links to their respective EOC.
5.0 PRECAUTIONS 5.1 Media personnel that respond to the EOF should not be allowed access to the EOF unless specifically authorized by the Emergency Manager. Prior to allowing the media access to the EOF all efforts to direct the media to the Joint Public Information Center (JPIC) should be exhausted.
5.2 All communications from the news media or general public should be directed to the JPIC. Emergency Response Organization personnel SHALL NOT release information to the news media or general public without prior approval.
6.0 INSTRUCTIONS 6.1 Initial Agency Liaison Activation and Staffing 6.1.1 Upon notification of an emergency, all qualified Agency Liaison personnel should report directly to the EOF.
6.1.2 Upon arrival at the EOF, refer to the EOF Tagboard to determine Agency Liaison assignment as follows:
A.
If no one has assumed the Agency Liaison position, turn the appropriate tag and sign in as the Agency Liaison.
B.
If another Agency Liaison has already assumed the duties, report to the EOF Coordinator for duty assignment.
6.1.3 Upon assuming the Agency Liaison position, proceed to the EOF Command Center.
6.1.4 Obtain any necessary administrative supplies from the administrative supplies locker in the EOF Fax Room.
6.1.5 Establish residence near the EOF Coordinator station in the EOF Command Center.
6.1.6 When directed, set-up the EOF Training Rooms for expanded EOF activation in accordance with Section 6.2.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 4 of 12 6.2 Expanded EOF Set-up and Activation 6.2.1 The Agency Liaison should prepare EOF Classrooms 8, 9, 11 and 12 for expanded EOF activation if any of the following conditions are met:
NOTE: The EOF may be setup for expanded activation at the Alert classification at the discretion of the Emergency Manager (based on recommendations from the EOF Coordinator) depending on time and personnel resources available.
A.
If a Site Area Emergency (or higher) emergency classification is declared (off-site agency response to the EOF is very likely).
B.
If off-site agencies (e.g., State, Counties, NRC, FEMA, etc.) are responding to the EOF.
C.
If the event is security related and Security (and law enforcement agencies) are using the EOF as a base of operations.
6.2.2 Set-up EOF Classrooms 8, 9, 11 and 12 expanded EOF activation as follows:
A.
Arrange the existing tables and chairs in each room (refer to FIGURES 7.2, 7.3, and 7.4 for suggested arrangement).
B.
Obtain designated telephones from storage cabinet (in each room) and plug-in the telephone(s) into their respective telephone wall jack(s) and operationally test each telephone.
C.
Classrooms are designated for EOF use as follows:
- 1. Classroom 8 (NRC Administrative support including typists, messengers, facsimile operator, etc.)
- 2.
Classroom 9 (NRC Emergency Response and NRC Director Site Operations Conference Room including ENS and HPN monitors, Emergency Response Coordinator, etc.).
- 3.
Classroom 11 (NRC Public Affairs Coordinator and Xcel communications representatives).
- 4.
Classroom 12 (NRC Government Liaison, EOF Liaison and State and/or County government representatives).
6.2.3 If the event involves NRC site team response to the EOF, obtain the NRC title placards (from the EOF administrative supplies cabinet) and position them in the respective classrooms and the EOF Command Center (adjacent to their counterparts) in accordance with FIGURE 7.5.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 5 of 12 6.3 General Liaison Instructions 6.3.1 Inform EOF Security of the expected arrival time and identity of the individuals arriving at the EOF (if known).
6.3.2 Provide arriving off-site personnel (NRC, etc) with EOF floor plans showing their room assignment, location of the command center and location of key emergency response stations.
6.3.3 Provide arriving off-site personnel with copy of the current EOF staffing organization chart for assisting in their identification of key ERO positions.
6.3.4 Ensure the assigned room has Monticello and Prairie Island Nuclear Emergency Telephone Directories available.
6.3.5 When the NRC team arrives complete the following:
A.
Conduct an initial briefing in Training Room 9.
B.
Assist the NRC in setting up their equipment in Training Rooms 8 and 9.
C.
Introduce the NRC team to their ERO counterpart.
6.3.6 If representatives from the State, Counties or Law enforcement agencies arrive complete the following:
A.
Conduct an initial briefing in Training Room 12 and ensure they are briefed on the response efforts to the emergency.
B.
Ensure they have sufficient administrative supplies.
C.
Familiarize them with the available information concerning the emergency by reviewing all status boards, telefaxes, and press releases.
D.
Update them as changes in the emergency event occur.
6.3.7 Throughout the event assist the off-site agencies present in the EOF with facility and communications needs.
6.3.8 If off-site vendors or contract support arrives, ensure they get connected up to their ERO counterpart.
6.4 News Media Instructions 6.4.1 If informed that local or national news media personnel have arrived at the EOF or Site, immediately notify the EOF Coordinator and Emergency Manager.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 6 of 12 6.4.2 Ensure that the Emergency Manager or EOF Coordinator notifies Communications or the NMC Executive Spokesperson at the MN State I EOC that news media personnel have arrived on-site or at the EOF.
6.4.3 If the Emergency Manager approves the news media access to the EOF, then inform EOF Security that they will be allowed access.
6.4.4 Escort the news media to the Training Center Multi-purpose Room (or other designated waiting area) and have them wait for NMC/MNGP management or a Communications Representatives.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 I
I E
Page 7 of 12 7.0 FIGURES FIGURE 7.1 Emergency Operations Facility Floor Plan
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MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 8 of 12 FIGURE 7.2 EOF Training Rooms 8 and 9 Floor Plan LAN A 2-812-2 I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 9 of 12 FIGURE 7.3 EOF Training Rooms 11 and 12 Floor Plan A 2-812-3 I/mab
MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 1Page 10 of 12 FIGURE 7.4 EOF Security Office and Trainina Room 14 Floor Plan 1556 TRAINING
(
ROOM 14 EM)
OFFICE (EOF
( 0.,1 Iý2 "
Co1.*
(LO SECURITY)
SIM SUPV I/mab A.2-812-4
MONTICELLO NUCLEAR GENERATING PLANT A.2 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 11 of 12 FIGURE 7.5 Expanded EOF Activation for NRC Co-Location CLASSROOM DESIGNATIONS Classroom 8 NRC administrative support including fax and typists Classroom 9 NRC conference room for Director Site Operations Classroom 10 - Technical Support Room (NMC and NRC)
Classroom 11 Communications/Media Room (NMC and NRC)
Classroom 12 -
Government Liaison Room (NMC, NRC, State and Local)
Classroom 14 -
Emergency Manager Conference Room NRC PLACARD LOCATIONS EOF Command Center (adjacent to MNGP counterpart)
NRC Director Site Operations (Emergency Manager)
NRC Protective Measures Coordinator (RPSS)
NRC Protective Measures Assistant (Assistant RPSS)
NRC Reactor Safety Coordinator (Technical Support Supervisor)
NRC Reactor Safety Assistant (Technical Support Supervisor)
NRC Emergency Response Coordinator (EOF Coordinator)
Classroom 8 (NRC Administrative Support)
NRC Resource Coordinator NRC LAN Jack FAX Jack I/mab
-812
MONTICELLO NUCLEAR GENERATING PLANT A.2-812 TITLE:
OFF-SITE AGENCY LIAISON AT THE EOF Revision 3 Page 12 of 12 FIGURE 7.5 Expanded EOF Activation for NRC Co-Location (Cont'd)
NRC PLACARD LOCATIONS (Cont'd)
Classroom 9 (NRC DSO Conference Room)
NRC Emergency Response Assistant NRC Reactor Safety Liaison Communicator NRC Protective Measures Liaison Communicator NRC ENS Monitor NRC HPN Monitor EOF Security Office (office immediately outside EOF Fax Room)
NRC Safeguards Coordinator NRC Security Coordinator EOF Dose Assessment Room NRC Environmental Measurements Coordinator Environmental Dose Assessment Coordinator Classroom 11 (EOF Media/Communications Room)
NRC Public Affairs Coordinator Agency/Media Liaison Coordinator Classroom 12 (Government Liaison Room)
NRC Government Liaison Coordinator NRC Government Liaison Communicator I/mab