ML032520791

Emergency Plan Implementing Procedure (EPIP) Revisions

ML032520791
Person / Time
Site:	Sequoyah
Issue date:	08/25/2003
From:	Salas P Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Security and Incident Response
References
EPIP-17, Rev 24, EPIP-6, Rev 36
Download: ML032520791 (58)

Text

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 August 25, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Docket Nos.50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT - UNITS 1 AND 2 - EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISIONS In accordance with the requirements of 10 CFR 50, Appendix E, Section V, the enclosure provides the following EPIP:

EPIP Revision Title EPIP-6 36 Activation and Operation of the Technical Support Center EPIP-17 24 Fire Emergency Procedure This letter is being sent in accordance with NRC RIS 2001-05.

If you have any questions concerning this matter, please telephone me at (423) 843-7170 or J. D. Smith at (423) 843-6672.

LicensX g and Industry Affairs Manager Enclosure cc (Enclosure):

Mr. Michael L. Marshall, Jr., Senior Project Manager U.S. Nuclear Regulatory Commission MS-0-8G9A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 4~cfA5 Pnnted o, ecyd

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 36 QUALITY RELATED PREPARED BY: D.A. Porter RESPONSIBLE ORGANIZATION: Emergencv Preparedness APPROVED BY: J. Randy Ford Date: 08/08/2003 EFFECTIVE DATE: 08/08/2003 Level of Use: Reference Page 1 of 51 REVISION 36

SEQUOYAH ACTIVATION AND OPERATION OF THE l

SEQUOYAH I TECHNICAL SUPPORT CENTER EPI C

I r 6 I Revision History Rev Date Revised Pages Reason for Revision 32 03/30/2001 Clarified Inter-relation of Apps U and B. Reformatted TSC minimum staffing to more clearly define necessary staff. Added TAT actions concerning Aux Air Dryers from DCN D20393A. Revised PAR chart in accordance with REP revision. Removed Iodine channels from 101, 106, and 112 rad monitors. Added Area monitor RM-90-61.

Corrected instrument IDs.

33 05/31/2001 Reformatted index and cover page. Added Revision history.

Revised header to smaller format. Added evaluation of Control Building Ventilation isolation as part of actions of PER 01-002674-000. Added Shift turnover verification EP Manager and added necessary forms as Apps BB and CC.

34 10/0112001 Revised App L to instruct the clerks to disable 'Memory Fax' option (PER 01-006615-000). Deleted App Y (PER 0108461-00).

Revised Title for App Z due to no longer having equipment listed in App. Minor formatting changes.

35 06118/2003 All Changed PHYSI-32 to SSI-1. Rolled all responsibilities into the checklists for clarity. Reordered and renumbered appendices for human factoring. Added TSC Relocation section. Changed position checklists in EPIP-6 to more closely match position responsibilities InApp. B of the REP. Changed the name of the App on PARs to match REP, Section 10, terminology, changed phone prefix in 3.2.1.B to '9' for consistency. Revised intial steps on all checklists. Added lines to SED checklist to record times when TSC and OSC were activated. Added checkoffs to Identify main types of onsite protective actions and item #4: 'Site Radiological Problems' to SED Turnover. Changed 4 PARs to 2 PARs to match current PAR Logic Diagram and added 'use 46 meters" behind the met data on SED Turnover App B. Added ERN to CR Coin. checklist Added security items to Sec. Mgr. for standardization. Moved NRCC checklist pg.2 into training materials. Removed '(A) Particulate cpm' from App K, on Aux Big Vent. Divided the Logkeeper and TSC Clerks responsibilities Into two sep. checklists. Removed note from Clerks chklst on Fax memory due to new fax machines. Added

'Directs onsite RADOON activities.' To RC Mgr checklist. Added and changed several items on Maint Mgrs. Checklist. Added ERN and eSOMS to Ops Coin., TSC Logkeepers, Maintenance Managers and RADOON Managers responsibilities. Renamed App entitled 'Control Building Battery Room Exhaust Fan Failure" to

'Ventilation Problems' and added procedural guidance for the condition of PER 00-4645, the containment penetration configuration. Removed the App Ye. Deleted TSC Roster from Procedure, will use EPIP-8 form. Human factored Emergency Responder Notification Form (now App M). Removed source notes (now found in rev file). Reformatted and edited procedure.

36 08/08/2003 5,6,26,28,40, Added information on containment sump blockage in response to 41 NRC Bulletin 2003-01.

Page 2 of 1 REVISION 36

ACTIVATION AND OPERATION OF THE ISEQUOYAHl TECHNICAL SUPPORT CENTER I EPIP 61 TABLE OF CONTENTS Section Title Paae Table of Contents..............................................................................................................3 1.0 PURPOSE .............. 5

2.0 REFERENCES

.............. 5 3.0 INSTRUCIONS ............................................. 5.......

3.1 Activation..................................................................................................................5 3.2 Activation Methods ............................. 5 3.3 Call Ust ............................ 6 3.4 Response Personnel ........................... 6 3.5 TSC Relocation ........................ 7 3.6 Deactivation .. 7...............

3.7 Procedure Adherence ........................ 7 4.0 RECORDS RETENTION .............................. 8 4.1 Records of Classified Emergencies ............................. 8 4.2 Drill and Exercise Records ............................. 8 5.0 ILLUSTRATIONS AND APPENDICES Appendix A.9 .................................. 9 Checklist A.01 Site Vice President ......................... 9 Checklist A.02 Site Emergency Director ......................... 10 Checklist A.04 Operations Manager ......................... 13 Checklist A.05 Technical Assessment Manager .......................... 15 Checklist A.06 Operations Advisor - TAT......................... 17 Checklist A.07 Operations Communicator ......................... 18 Checklist A.08 Site Security Manager ......................... 19 Checklist A.09 RADCON Manager ............................................................. 20 Checklist A10 Chemistry Manager ......................... 22 Checklist A1 1 NRC Coordinator ......................... 23 Checklist Al12 Control Room Communicator ...... ................... 24 Checklist A.13 Maintenance Manager ......................... 26 Checklist A.14 Technical Assessment Team Leader . ......................... 28 Checklist A.1 5 EP Manager ......................... 31 Checklist A. 16 TSC Logkeeper ......................... 32 Checklist A.17 TSC Clerical ......................... 33 (Continued)

Page 3 of 51 REVISION 36

SEQUOYAH ACTIVATION AND OPERATION OFTHE EPIP 6 TECHNICAL SUPPORT CENTER l I 6l TABLE OF CONTENTS Section Title Page 5.0 ILLUSTRATIONS AND APPENDICES (Continued)

Appendix B SED Turnover Data Sheet ..................................... 34 Appendix C TAT Recommendation Form .................................... 36 Appendix D TSC Accident Assessment Sheet .................................... 37 Appendix E Predictive Release Data Sheet .................................... 38 Appendix F Protective Action Recommendations .................................... 39 Appendix G Containment Sump Operation and Level Guidance ................... 40 Appendix H ERCW Concerns for Technical Assessment Team .................... 42 Appendix I Ventilation Problems .................................... 44 Appendix J Contingencies for Control and Processing Large Volumes of Secondary Side Contaminated Water ..................... 46 Appendix K Plant Parameter Data Sheets ................................... 47 Appendix L Reference Materials List ................................... 50 Appendix M Emergency Responder Notification ................................... 51 Page 4 of 51 REVISION 36

SEQUOYAH ACTiVATION AND OPERATION OF THE EDI TECHNICAL SUPPORT CENTER r E r 6 1.0 PURPOSE The purpose of this procedure is to describe activation of the Technical Support Center (TSC), describe the TSC organization, and provide for TSC operation once it has been staffed. The TSC is activated by EPIP-1 to respond to emergency conditions.

2.0 REFERENCES

EPIP-1, "Emergency plan Classification Matrix" EPIP-7, 'Activation and Operation of the Operations Support Center (OScr EPIP-8, "Personnel Accountability and Evacuation" EPIP-1 1, "Security and Access Control" EPIP-13, 'Dose Assessment' EPIP-14, 'Radiological Control Response" EPIP-15, OEmergency Exposure Guidelines" EPIP-16, OTermination and Recovery" O-SO-67-3, ERCW Strainers and Traveling Screenso Memorandum from J. B. Hosmer to R. J. Johnson dated 1/15/88, Implementing PRDCS and Operation Training (RIMS-B25880115028) 3.0 INSTRUCTIONS 3.1 Activation The TSC is activated by EPIP-1 to augment on shift personnel. When the TSC is activated by the on-shift Site Emergency Director (SED), the on-call SED will obtain a turnover from the on-shift SED using Appendix B and report to the TSC. The SED shall be responsible for implementing this procedure, coordinating TSC activities, and overseeing the operations of the Operations Support Center (OSC).

3.2 Activation Methods The SED will activate the TSC by announcing the emergency condition by one or more of the following methods:

A. Emergency Paging System (EPS).

B. Operations Duty Specialist (ODS) activate EPS from the Central Emergency Control Center (CECC).

C. Plant Public Address (PA) announcement.

D. The Shift Manager or operations clerk will contact the persons designated on the REP Duty Roster and/or Call List.

E. Assembly and accountability sirens Page of 1 REVISION 36

SEQUOYAH ACTIVATION AND OPERATION OF THE =D TECHNICAL SUPPORT CENTER EPI 3.3 Call List The Emergency Preparedness Manager (EPM) maintains a REP Duty Roster and Call List book listing key TSC personnel by name, plant and home telephone numbers. The REP Call Ust and Duty Roster book will be updated at least quarterly by the EPM or designee with input by the appropriate section/group supervisors.

3.4 Response Personnel The following personnel normally report to the TSC or the assigned TSC support location upon activation of the TSC by the SED. Additional replacement personnel will be called as replacements to establish 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> operations while typically maintaining a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or shorter shift (excluding turnover). Appendix M may be used to facilitate establishing this rotation.

A. Site Emergency Director B. Site Vice President C. Operations Manager D. Operations Communicator E. Technical Assessment Manager F. Tech Assessment Team Leader G. Tech Assessment Team Members - Reactor, Mech, Elec Engineer(s)

H. Operations Advisor to the TAT

1. RADCON Manager J. Chemistry Manager K. Maintenance Manager L. Emergency Preparedness Manager M. Security Manager N. NRC Coordinator

0. Control Room Communicator P. TSC Logkeeper Q. Other plant staff the SED determines to be necessary to support OSC functions will be called:

1. Clerks

2. RADCON Boardwriter

3. RADCON ICS Operator Page 6 of 51 REVISION 36

I 1 p I

gSEQUOYAH SEQUQYAK l

I ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP 3.5 TSC Relocation It is highly unlikely that the TSC will be required to relocate due to the physical and radiological protection provided by its location. However, should the SED determine that relocation TSC is necessary, an alternate location will be selected based on the following guidance:

A. Location should have adequate access to the plant (preferably is within the Protected Area), have a current radiological survey, be upwind from plant, and have adequate ventilation control.

B. Location should have adequate communications capabilities (including at least three telephone circuits).

C. Location should have physical space for at least 15 persons (may be divided into two areas - one for TAT and one for Command & Control).

D. Locations for consideration include:

• Co-locating with the OSC

• O&PS 1 Floor

• Work Coordination Center

• Sequoyah Training Center 3.6 Deactivation The TSC will be deactivated when directed by the SED. All TSC personnel as a part of deactivation will:

A. Ensure all assigned tasks and assignments are completed.

B. Ensure all emergency response teams have been debriefed.

C. Ensure all emergency equipment and supplies have been returned to their specified storage locations.

D. Collect and review all records for completeness and forward all records to the Emergency Preparedness Manager.

3.7 Procedure Adherence Normal plant maintenance procedures will be followed whenever possible.

Should a situation arise where normal procedures would be inappropriate, maintenance will be performed as determined by the OSC Manager.

Page 7 of 51 REVISION 36

I ACTIVATION AND OPERATION OF THE I SEQUOYAH TECHNICAL SUPPORT CENTER I EPIP 61 4.0 RECORDS RETENTION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency classified as NOUE or higher are considered Lifetime retention Non-QA records.

Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.

4.2 Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.

Page 8 of 51 REVISION 36

SEQUJOYAH ACTIVATION AND OPERATION OF THE e

- TECHNICAL SUPPORT CENTER EPI C o APPENDIX A, CHECKLIST A.O1 SITE VICE PRESIDENT Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

SIGN IN on the Organizational/Staffing Chart and PUT ON position badge.

__/I SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

ESTABLISH log of communications/events.

ESTABLISH contact with the Media Relations Specialist.

CHECK the status of emergency actions already in effect such as accountability or site evacuation.

OPERATIONAL RESPONSIBILITIES LIST

• Provides TVA policy direction to the Site Emergency Director.

• Directs site resources to support and assist the SED in accident mitigation activities.

• Provides direct interface on overall site response activities with NRC, FEMA, Federal organizations, the CECC Director, and onsite media.

• Provides interface/briefings (as needed) at offsite locations on the overall site response activities with Federal, State and Local agencies.

• Serves as the primary site representative to function as a TVA Spokesperson in the Local News Center (LNC) at the Sequoyah Training Center (if activated) and the Joint Information Center (if necessary).

• Provides support to other emergency operation centers as necessary. As applicable, designates an alternate to provide direction and/or support for the overall site response and support to the SED.

• Serves as a corporate interface for SED relieving him from duties which could distract from the SED's primary purpose of plant operations and accident mitigating activities.

• Will assure that following all changes in emergency classification that the State has been notified in accordance with established procedures. Will appoint an alternate to complete this function if absent from the TSC.

Page 9 of 51 REVISION 36

I J TECHNICAL SUPPORT CENTER l l APPENDIX A, CHECKLIST A.02 SITE EMERGENCY DIRECTOR Page 1 of 3 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST OBTAIN turnover briefing from SM/SED in accordance with Appendix B, (may be done concurrent with this Appendix).

I ENTER badge into the TSC Accountability Card Reader.

I SIGN IN on the staffing chart and PUT ON position badge.

- SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

/___ ESTABUSH log of communications/events.

/___ ESTABUSH contact with the CECC Director and determine if the Director has assumed responsibility for primary contact with the site and state.

(NOTE: the ODS has this responsibility until the CECC Director assumes the function.)

IF the emergency classification is escalated and the CECC has not assumed responsibility for communications with the State, THEN ensure the State is notified within 15 minutes by implementing EPIP-3, EPIP-4 or EPIP-5, as appropriate.

I CHECK the status of emergency actions already in effect such as emergency notifications (NRC, State, etc.) accountability or site evacuation.

REVIEW checklist completion status for key positions (Operations, Technical Assessment Manager, RADCON, Maintenance Manager, etc.).

lI ENSURE minimum staffing is present for TSC operability and checklists are complete. The following individuals must be present:

E SED O RADCON Manager o Operations Manager or Operations Communicator 0 TAM or TATL or (Rx Engr and Mech Engr and Elec Engr)

Page IO of 51 REVISION 36

UOYAH l -ACTIVATION AND OPERATION OFTHE I 6 TECHNICAL SUPPORT CENTER EPI APPENDIX A, CHECKLIST A.02 SITE EMERGENCY DIRECTOR Page 2 of 3 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ASSUME role of SED from SMISED and O NOTIFY CECC that the TSC Isoperational.

O NOTIFY OSC that the TSC is operational.

_ ANNOUNCE, using x4900:

"This is . I have assumed the responsibility of the Site Emergency Director. I am declaring the TSC activated at and OSC activated at_ _ _

OPERATIONAL RESPONSIBILITIES LIST

• Directs onsite emergency organization accident mitigation activities.

• Establishes and maintains site priorities for accident mitigation.

• Responsible for determining the emergency classification and periodically reevaluates the classification. Changes to the classification will be reported to the CECC Director within about five minutes and the NRC. This responsibility cannot be delegated.

• Prior to the CECC being staffed, in accordance with Appendix F or EPIP-5 makes recommendations for protective actions to State and Local agencies through the Operations Duty Specialist within about five minutes of the determination. This responsibility cannot be delegated. except to the CECC Director.

• Initiates onsite protective actions.

• Performs CECC functions for the Alert emergency class, Site Area Emergency Class and General Emergency Class until the CECC is activated.

• Briefs the TSCIOSC staff on the current situation.

• Direct key TSC positions to provide status summary to TSC staff.

• Updates the plant staff on plant status and emergency conditions.

• Reviews operation of the OSC with the OSC Manager.

• Directs activities of onsite emergency organizations.

Page 11 of 51 REVISION 36

TECHNICAL SUPPORT CENTER APPENDIX A, CHECKLIST A.02 SITE EMERGENCY DIRECTOR Page 3 of 3 OPERATIONAL RESPONSIBILITIES LIST

• Consults with the CECC Director and Site VP on important decisions, significant events, and their related impacts.

• When necessary, establish a radiological checkpoint for she evacuation.

• Coordinates emergency actions with onsite NRC.

• Initiates long-term 24 Hour/day accident mitigation operations.

• Approves or authorizes, in accordance with EPIP-15, emergency doses that may exceed occupational dose limits. This responsibility cannot be delegated.

• May be relieved by the Operations Manager as needed.

• Evaluates conditions and determines if additional emergency procedures should be implemented.

A. CECC EPIP-9, "Emergency Environmental Radiological Monitoring Procedures" B. SON EPIP-10, uEmergency Medical Response" C. SON EPIP-1 1, "Security and Access Control" D. SON SSI-1, "Security Instructions to Members of the Security Force" E. SON EPIP-8, "Personnel Accountability and Evacuation" F. SON EPIP-13, "Dose Assessment" G. SON EPIP-14, 'Radiological Control Response"

• Assumes responsibility for Severe Accident Management when directed by the Main Control Room and the TSC is functional and the Severe Accident Management Guidelines (SAMG) evaluators are monitoring the Diagnostic Flow Chart. The TSC must have three evaluators monitoring SAMGs to assume the accident responsibility.

Page 12 of 51 REVISION 36

SEQUOYAH SEQUOYAH l ACTIVATION AND OPERATION OFTHE TECHNICAL SUPPORT CENTER I EPIP 6 I lPP6 APPENDIX A, CHECKLIST A04 OPERATIONS MANAGER Pagelof 2 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

ESTABUSH log of communications/events.

LOG ON to ICS.

ESTABLISH communications with SM and OSC Ops Advisor.

CHECK the status of emergency actions already in effect such as personnel dispatched for emergency response, Accountability or Site Evacuation.

K> / VERIFY notification of the NRC has been accomplished.

DESIGNATES an operationally competent person to establish and maintain communications with the NRC using the NRC ENS phones.

OPERATIONAL RESPONSIBILITIES LIST

• Directs operational activities, prevent congestion in the control room.

• Provide input to the SED for emergency classification.

• Informs the SED of plant status and operational problems.

• Provides status updates to the OSC Operations Advisor.

• Recommends solutions and mitigating action for operational problems.

• Reviews the emergency status with the control room. Reviews trended parameters, time history information, and status boards with the control room staff. Performs damage assessment as necessary.

Page 13 of 51 REVISION 36

iSEQUOYAH l ACTIVAION AND OPERATION OF THEl TECHNICAL SUPPORT CENTER I P P 6 APPENDIX A, CHECKLIST A04 OPERATIONS MANAGER Page 2 of 2 OPERATIONAL RESPONSIBILITIES LIST

• Assures that the control room is aware of the TSC accident assessment and response.

• Discuss with the control room the OSC activities such as repair and response priorities and, status of damage control and repair teams.

• During long term accident operating conditions, evaluate routine activities which would be performed under normal plant operating conditions, e.g., AUO rounds, equipment inspections, surveillance instructions, compensatory measures, or other similar activities. Determine if any of these actions should be performed on a normal or reduced frequency.

• Assume SED responsibilities if the SED must leave the TSC.

Page 14 of 51 REVISION 36

l SEQUYAH l ACTIVATION AND OPERATIONOF THE f lE I TECHNICAL SUPPORT CENTER l 6 APPENDIX A, CHECKLIST A.05 TECHNICAL ASSESSMENT MANAGER Page 1 of 2 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

____ SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

ESTABLISH log of communications/events.

CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.

I__ CHECKstatusof staff EJ TATL, o Reactor Engineer, o Mechanical Engineer, O Electrical Engineer, K> 0 TAT Ops Advisor O Westinghouse Rep.

- OPERATIONAL RESPONSIBILITIES LIST

• Provide input to the SED for emergency classification declaration.

• Directs onsite effluent assessment.

• Directs activities of the Technical Assessment Team.

• Projects future plant status based on present plant conditions.

• Keeps assessment team informed of plant status.

• Provides information, evaluations, and projections to the SED.

• Communicates with the CECC Plant Assessment Manager.

• Coordinates assessment activities with the CECC plant assessment team.

• Establishes and maintains a status of significant plant problems.

- Page 15 of 51 REVISION 36

SEQUOYAH l ACTIVATION AND OPERATION OF THE l ID A I SEQIOYAH A TECHNICAL SUPPORT CENTER l lP APPENDIX A, CHECKLIST A.05 TECHNICAL ASSESSMENT MANAGER Page 2 of 2 OPERATIONAL RESPONSIBILITIES LIST

• Assures predictive release rate information (Appendix E) is sent to the CECC to be used in the predictive release rate model.

• If the need for post accident sampling is anticipated, alert TSC Chemistry Manager so that they can prepare RWP and support.

• Assures Post Accident sampling In accordance with 1/2-TI-CEM-043-066.1 is initiated as required.

• Designates personnel to maintain Plant Status and Trending Boards.

• Provides for trending of significant parameters.

• Assumes role as SAMG evaluator when required (if qualified).

Page 16 of 51 Pag 1REVISION 36

ACTIVATION AND OPERATION OF THE ISEQUOYAH I_ TECHNICAL SUPPORT CENTER I EPIP 61

- APPENDIX A, CHECKLIST A06 OPERATIONS ADVISOR, TAT Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST

-I ENTER badge into the TSC Accountability Card Reader.

-J SIGN IN on the staffing chart and PUT ON position badge.

I SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

I LOG on to ICS.

-J ESTABLISH contact with the Control Room. (Dial x1 01, keep on mute as much as possible.)

-I CHECK the status of emergency actions already in effect such as personnel dispatched into the field and Accountability or Site Evacuation.

OPERATIONAL RESPONSIBILITIES LIST

• Operates ICS to obtain plant status and parameters.

• Monitors procedure direction taken by the main control room operators and keeps Technical Assessment Team Leader informed of potential future problems and status of safety related equipment.

• Provides information from the Control Room to the Technical Assessment Manager and Technical Assessment Team.

• Obtains supplemental data as needed by the TSC, OSC, or CECC.

• Completes portions of plant parameters data sheets (Appendix K) as needed.

Plots/trends as designated by TAM.

Page 17 of 51 REVISION 36

SEQUOYAH ACTIVAT1ON AND OPERATION OF THEEDID TECHNICAL SUPPORT CENTER I E 61 APPENDIX A, CHECKLIST A.07 OPERATIONS COMMUNICATOR Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

I SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

OBTAIN headset and DIAL into the Control Room Operations Bridge (x 101).

PROVIDE the completed checklist to the TSC log keeper.

OPERATIONAL RESPONSIBILITIES LIST

• Monitors the Control Room Operations Bridge (xl 01).

• Provides information from the MCR and OSC to TSC personnel including information on AUO activities.

• Monitors plant status boards and ICS.

• Obtains supplemental data as needed by the TSC, OSC, or CECC.

• Makes inquiries to the Control Room Communicator to obtain specific information as necessary (includes emergency procedure status).

• Maintains a current log of major operational events for the Operations Manager's use (may use eSOMS, ERN Data).

Page 18 of 51 REVISION 36

SEQUOYAH ACnwVATON AND OPERATION OF THE TECHNICAL SUPPORT CENTER iE I APPENDIX A, CHECKLIST A.08 SITE SECURITY MANAGER Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST

__ ENTER badge into the TSC Accountability Card Reader.

-__I SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival.: (Ref.: use roster from EPIP-8, Appendix 1)

JL..... ESTABLISH log of communications/events.

ESTABLISH contact with the CAS and the SAS.

CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation and report status to the SED.

OPERATIONAL RESPONSIBILITIES LIST

• Directs activities of Site Security personnel and mobilizes additional personnel as K> needed.

• Controls access to the Site and Control Rooms.

• Reports on site accountability/evacuation as defined in SON EPIP-8.

• Assures an officer is dispatched to areas outside the protected area such as the Sequoyah Training Center, Security Training Center, Uvewell, and Design Services Complex during accountability / evacuation using EPIP-8 or EPIP-1 1.

• Advises incoming emergency response personnel at the gate house of any radiological, security, or environmental hazards in route to the TSC or OSC.

• Assists in establishing search teams, as required. (SON EPIP-8)

• Coordinates Security activities with emergency response organization.

• Provides status updates to Site Security personnel.:

• Reports status of Security related events to the SED.

K>

• Remain aware of Plant Radiological Conditions and report locations(s) of Security PersonnelPatrols (as needed) to the RADCON Manager and the SED.

Page 19 of 51 REVISION 36

SEQUOYAH lACTIVAlION AND OPERATION OF THE E I I SEQUOYAH I TECHNICAL SUPPORT CENTER I EPIP 6 APPENDIX A, CHECKLIST A.09 RADCON MANAGER Page1 of 2 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

/___ SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

ESTABLISH log of communications/events.

I ESTABUSH contact with the OSC RADCON Supervisor (x103), the radiological monitoring van (if dispatched), and the CECC Radiological Assessment Coordinator (RAC) or Radiological Assessment Manager (RAM) if the RAC is not available.

-I LOG on to ICS and the Emergency Response Network (must be activated from the CECC and OSC).

I_ CHECK the status of emergency actions already in effect such as RADCON personnel in the field, and Accountability or Site Evacuation.

ESTABLISH communications with environs monitoring van (IF dispatched and not under the control of the CECC).

I ENSURES the OSC RADCON Supervisor has designated a qualified/knowledgeable person to provide inplant radiological data to the NRC Health Physics Network (HPN) upon request.

OPERATIONAL RESPONSIBILITIES LIST

• Collects and provides plant radiological data to TSC as applicable.

• Directs onsite RADCON activities.

• Directs and/or performs assessments of inplant and onsite radiological conditions.

Uses the Integrated Computer System and the Emergency Response Network (ERN).

• Directs the OSC RADCON Supervisor in performing radiological assessments.

• Keeps the CECC RAMWRAC informed of site radiological conditions.

Page 20 of 51 REVISION 36

SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPI

=m APPENDIX A, CHECKLIST A.09 RADCON MANAGER Page 2 of 2 OPERATIONAL RESPONSIBILITIES LIST

• Coordinates additional RADCON support with the CECC RAM/RAC.

• Makes recommendations for protective actions for onsite personnel to the SED.

• Authorizes issue of Kl, by following SON EPIP-14, to onsite personnel, after informing the SED.

• Coordinates assessment of radiological conditions offsite with CECC RAM/RAC.

• Maintains status maps of offsite radiological conditions and inplant radiation status board.

• Provides RADCON surveillance through the OSC for off-site personnel assigned to the SQN Training Center, MET station, Communication Node Building, etc. if required by environmental releases. Ensure these off-site personnel are tracked through the Maintenance Manager on the Team Tracking Board on ERN.

• Obtains MET data as needed by using ICS or the CECC Computer.

• Provides periodic status reports to the SED on radiological conditions and input on the emergency classification and Protective Action Recommendations (PARs).

• Makes recommendations to the SED for personnel entry into radiological hazardous environments.

Page 21 of 51 REVISION 36

SEQUOYAH ACTIVATION AND OPERATION OF THE 1IDe TECHNICAL SUPPORT CENTER . 6 APPENDIX A, CHECKLIST A10 CHEMISTRY MANAGER Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

ESTABLISH log of communications/events.

ESTABLISH contact with the Chemistry Supervisor in the lab and the CECC Radiological Assessment Coordinator. Obtain assessment of any radiological release in progress and provide to the SED.

LOG ON to ICS.

CHECK the status of emergency actions already in effect such as Chemistry personnel in the field and Accountability or Site Evacuation.

OPERATIONAL RESPONSIBILITIES LIST

• Directs the Chem. Lab Supervisor to implement the applicable portions of EPIP-14.

• Coordinates the assessment of radioactive effluents with the CECC Radiological Assessment Coordinator.

• Directs Chemistry lab in performing Post Accident Sampling Activities.

• Determines impact of the incident on radwaste and various effluent treatment systems.

• Performs/directs release rate calculations, onsite/off-site dose assessments and dose projections in accordance with EPIP-13 when required.

• Completes Predictive Release Data sheet (Appendix E) and transmits it to CECC PAT.

• Completes portions of plant parameter data sheets (Appendix K) as needed.

• Provides all plant chemistry data to the Technical Assessment Team.

• Provide input to the SED for emergency classification and PARs.

Page 22 of 51 REVISION 36

l SEQUYAH l ACTIV ATION AND OPERA llON OF THEl PIP61

! TECHNICAL SUPPORT CENTER l I APPENDIX A, CHECKLIST A.11 NRC COORDINATOR Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

ESTABLISH log of communications/events.

CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.

/___ CONTACT the Operations Manager to determine if the Emergency Notification System (ENS) line requires continuous communications.

OPERATIONAL RESPONSIBILITIES LIST

• Acts as primary liaison with onsite NRC personnel.

• Updates NRC personnel on plant status (use Appendix D as a guide when ICS is unavailable).

• Provides information requests from NRC to TSC personnel.

• Obtain copy of Appendix D from the TATL and report data to NRC in the event Emergency Response Data System (ERDS) fails.

• IF requested, maintain contact with the NRC on the NRC Emergency Notification System (ENS) phone line. Coordinate the transfer of responsibility for ENS continuous communications with the Main Control Room (Main Control Room).

Page 23 of 51 REVISION 36

l SEQUYAH l ACTIVATION AND OPERATION OF THE lE I TECHNICAL SUPPORT CENTER APPENDIX A, CHECKLIST A.12 CONTROL ROOM COMMUNICATOR Page 1 of 2 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

SIGN IN on the staffing chart and PUT ON position badge.

/___ SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

OBTAIN headset from the TSC and REPORT to the Control Room (portable phone is located at the Shift Manager's station).

/ESTABLISH

-zJ..... log of communications/events.

ESTABLISH contact with the TSC Operations Communicator and OSC Operations Advisor. (xl 01).

CHECK the status of emergency actions already in effect such as K." Accountability or Site Evacuation.

LOCATE all Operations personneiteams currently or previously tasked and ensure each is tracked on the AUO OSC Team board.

OPERATIONAL RESPONSIBILITIES LIST

• Serves as the control room - TSC and OSC communications link.

• Provides operational knowledge for status evaluation of plant systems.

• Provides advice regarding Technical Specifications, system response, safety limits, etc.

• Assists in development of recommended solutions to developing problems.

• May use ICS to trend parameters.

• Assures the control room staff is aware of the TSC accident assessments and OSC activities.

Page 24 of 51 REVISION 36

EPIP SEQUOYAH -l SE YH ITECHNICAL SUPPORT CENTER ACTIVATION AND OPERATION OF THE l E APPENDIX A CHECKLIST A12 CONTROL ROOM COMMUNICATOR Page 2 of 2 OPERATIONAL RESPONSIBILITIES LIST

• Ensures the OSC Operations Advisor and TSC Operations Communicator are informed of the status of all Operations personnel/teams dispatched by the Shift Manager.

OSC maintenance activities status are available through the Emergency Response Network.

X Communicate operational status of plant systems and major equipment, automatic and manual initiation of ESF equipment, important system parameters associated with EALs, and procedure transitions by the MCR.

• Communicate messages between the Shift Manager and the TSC.

Page 25 of 51 REVISION 36

X SEQUYAH l AcnIvATiON AND OPERATION OF THE TECHNICAL SUPPORT CENTER

,E IP APPENDIX A, CHECKLIST A.13 MAINTENANCE MANAGER Page 1 of 2 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

ESTABLISH contact with the OSC Manager, Assistant OSC Manager or Status Board Writer in the OSC. (x104)

ESTABUSH a log of communications/activities.

CHECK the status of emergency actions already In effect such as teams already dispatched by the Main Control Room, Accountability or Site Evacuation.

CHECK status of deployed emergency response teams (Operations, Maintenance, Medical Emergency Response Teams, etc.)".

OPERATIONAL RESPONSIBILITIES LIST

• Directs activities of the OSC.

• Directs repairs and corrective actions.

• Makes team task assignments to the OSC Assistant Manager.

• Performs damage assessment.

• Maintains cognizance of deployed OSC emergency response teams purpose and status. Provides updates to the SED on emergency teams status.

• Assists the SED and the OSC Manager in determining the priorities of activities.

• Monitors the emergency response team tracking (Projects team activities using the Emergency Response Network (ERN) Team Tracking" screen.

• Provides assistance to the SED as needed.

Page 26 of 51 REVISION 36

SEQUOYAH ACTIVATION AND OPE.RATION OF THE TECHNICAL SUPPORT CENTER I EPIP6 I APPENDIX A, CHECKLIST A.13 I MAINTENANCE MANAGER

- Page 2 of 2 OPERATIONAL RESPONSIBILITIES LIST

• Communicates with the Assistant OSC Manager on matters concerning equipment and/or plant assessments.

. Ensures OSC and TSC status boards are consistent.

• Provides TSC personnel with a debriefing summary for each returning OSC team.

Page 27 of 51 REVISION 36

rSEQUOYAH l ACTIVATION AND OPERArioN OF THE TECHNICAL SUPPORT CENTER lE l

I APPENDIX A, CHECKLIST A.14 TECHNICAL ASSESSMENT TEAM LEADER Page 1 of 3 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST

/___ ENTER badge into the TSC Accountability Card Reader.

J ___ SIGN IN on the staffing chart and PUT ON position badge.

/___ SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

ESTABLSH a log of communicationslactivities.

____ ESTABLISH contact with the Technical Assessment Manager.

ESTABLISH contact with the CECC Plant Assessment Team (9-751-1629).

ASSIGN team member to maintain equipment out of service and TAT assignments boards.

CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.

OPERATIONAL RESPONSIBILITIES LIST

• Team leader may designate a TSC log keeper and board writer(s).

• Monitors and performns trending of key plant parameters against EAL criteria and provides technical assessment.

• Determines the condition of the reactor and nuclear fuel.

• Project future status based on present plant conditions.

• Provide technical support to plant operations on mitigating actions.

• Prepares and provides current assessment on plant conditions and provides this information to the CECC Plant Assessment Team (on Appendix K when requested).

• Uses Appendix C, Tat Recommendation Form for communicating with the TAM.

• Evaluate containment sump level and actions to mitigate sump screen blockage per Appendix G.

Page 28 of 51 REVISION 36

E PI P 61 SEQUOYAH j I ACTIVATION AND OPERATION OF THE SEH TECHNICAL SUPPORT CENTER I APPENDIX A, CHECKLIST A.14 TECHNICAL ASSESSMENT TEAM LEADER Page 2 of 3 OPERATIONAL RESPONSIBILITIES LIST

• Provides direction for environmental qualification operating concerns for containment cooling following a non-LOCA event inside containment (i.e., loss of secondary side coolant) per Appendix H.

• Prepares TSC accident assessment sheet Appendix D and transmits to the CECC when requested.

• Provides Technical Assessment to TAM on Appendix D when requested.

• Verifies that all ABSCE doors are closed (call Fire Ops, x7447 or OSC Fire Ops Advisor, x6407).

• Identifies and tracks the status of current ABSCE breaches (call Fire Operations, x7447 or OSC Fire Ops Advisor, x6407).

• Verifies that all Control Room Emergency Ventilation Pressure Boundary (CREVS) doors are closed (call Fire Ops, x7447 or OSC Fire Ops Advisor x6407).

• Identifies and tracks the status of current CREVS breaches (call Fire Ops, x7447 or OSC Fire Ops Advisor, x6407).

• If all control building battery room exhaust fans are off, then refer to Appendix I.

• Monitor the temperature of the 6.9kv shutdown board rooms in accordance with Appendix I.

• Refer to Appendix J, for contingency plan for control and processing of large volumes of contaminated water in the plant secondary side.

• Interface with Nuclear Engineering onsite and in the CECC (9-751-1634) for specific technical assistance and support as needed.

• Inthe event of a high energy line break (HELB) in the Auxiliary Building, evaluate the need to restore the environmental condition of the Auxiliary Building back to a normal condition within 6 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If environmental conditions are adverse, make recommendations to the Technical Assessment Manager to mitigate the condition.

Page 29 of 51 REVISION 36

ACTIVATION AND OPERATION OF THE EI I l EQUYAH I TECHNICAL SUPPORT CENTER I w APPENDIX A, CHECKLIST A.14 TECHNICAL ASSESSMENT TEAM LEADER Page 3 of 3 OPERATIONAL RESPONSIBILITIES LIST Auxiliary Air Dryers should be turned on within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after an accident and, one or more trains of dryers are inoperable and the outside ambient air temperature is at or below freezing, then monitor the rooms listed below for freezing temperatures at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If necessary, actions such as turning off ventilation fans and instituting freeze protection shall be taken until both trains are operable.

• (DCN D20393A)

• 480V Transformer Rooms (Rooms 749-A6, -A7, -Al0, and -Al1)

• Mechanical Equipment Rooms (Rooms 763-A3, and -A4)

• In the event of a radiological, chemical, or smoke release that may impact the air intake at the north or south end of the Control Building, evaluate stopping the Control Bldg Emergency Pressurization Fan from the affected intake.

Page 30 of 51 REVISION 36

[SEOUOYAH ACIAION AND OPERATION OF THE lEI TECHNICAL SUPPORT CENTER I l APPENDIX A, CHECKLIST A.15 EP MANAGER Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

ESTABLISH log of communicationslevents.

_/ CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.

VERIFIES checklists are distributed and are being completed.

VERIFIES all essential positions are filled.

K>

....I VERIFIES all activation activities (TSC and OSC) are proceeding normally.

CALL INClerical Support and other personnel as necessary (actions may be delegated).

OPERATIONAL RESPONSIBILITIES LIST

• Advises the SED regarding overall REP, use of EPIPs, emergency equipment availabilty, and coordination with the CECC.

• Confirms TSC and OSC are operating properly.

• Provides assistance to the SED and OSC Manager as requested.

• Makes P/A announcements to update plant personnel of the emergency status of current plant conditions as directed by the SED.

• Ensures that a Shift Turnover using Appendix M is prepared. Clerks may be assigned this task.

• Assists SED in listing overall mitigation priorities and filling out EPIPs.

• Tracks entry into EAL's and PAR's.

Page 31 of 51 REVISION 36

SEQUOYAHACTIVATION AND OPERATION OF THE -i TECHNICAL SUPPORT CENTER EI APPENDIX A, CHECKLIST A16 TSC LOGKEEPER Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST ENTER badge into the TSC Accountability Card Reader.

SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. {Ref.: use roster from EPIP-8, Appendix I)

_/ ESTABLISH a log of activities.

OPERATIONAL RESPONSIBILITIES LIST

• Uses REP Call List to obtain staff for unfilled positions or replacement staff for shift turnover. (Use Appendix M).

• Logkeeper maintains a chronological log of the SED and TSC activities to include time of classification changes and PARs and the level of each, changes in plant conditions, times of briefings, team status, content of discussions, and decisions made by the SED and any other entry as directed by the SED.

• Projects Emergency Response Network (ERN) screens. (Sequence Of Events, Plant Status, etc.)

• Regularly prints eSOMS (electronic Shift Operating Management System) control room logs and provides copies to the Operations Manager and the Operations Advisor to the TAT.

• Verifies the SED priorities by calling the-CECC Plant Assessment Team Engineer (9-751-1634) initially and when SED priorities change.

• Logkeeper assists the SED in preparing briefing notes. The notes should include activiities since the last briefing and include team status, changes Inclassifications and PARs and current plant conditions.

• Collect initial TSC checklists if requested from:

0 Site Emergency Director 0 Operations Manager 0 RADCON Manager O Site Vice President 0 Chemistry Manager 0 TAT Leader O Ops Communicator - 0 TAT Operations Advisor 0 EP Manager o TAM E Maintenance Manager 0 NRC Coordinator o Security Manager 0 Control Room Communicator (on deactivation)

Page 32 of 51 REVISION 36

EPI 6 SEQUOYAH l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER l E APPENDIX A, CHECKLIST A.17 TSC CLERICAL Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST

/_ ENTER badge into the TSC Accountability Card Reader.

SIGN IN on the staffing chart and PUT ON position badge.

SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix I)

/ ESTABLISH a log of activities.

OPERATIONAL RESPONSIBILITIES LIST

• Assists in setup and activation of the TSC.

• Provides pager reports to the Site Emergency Director and EP Manager.

• Maintains ongoing accountability of TSC personnel.

• Answers telephones.

• Distributes plant parameter data sheets when ICS is not functional.

• Distributes faxes to the appropriate personnel in the TSC.

• Uses REP Call List to obtain staff for unfilled positions or replacement staff for shift turnover (Appendix M).

• Operates fax machines and keeps a fax log.

• Verifies that faxes have been received in the CECC and OSC

• Provides faxes of AUO status from the OSC to the Operations Manager and Operations Advisor to the TAT.

• Changes classifications on the TSC classification clock.

Page 33 of 51 REVISION 36

X SEQUOYAH l SEQUOlAH I I ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I E IP 6 APPENDIX B SED TURNOVER DATA SHEET

-Page 1 of 2

1. Current Emergency Classification: 0 NOUE 0 ALERT 0 SAE 0 GE EAL(s)

Time Declared Time ODS Notified .

State Notified Time NRC Notified _

2. Event

Description:

3. Equipment Problems:

4. Site Radiological Problems:

5 Rad Release > Tech Specs: OYes No Liquid 0 Yes No Gaseous 0 Yes No

6. Dose Assessment Initiated: 0 Yes 0 No o Filtered Unfiltered o Monitored E Unmonitored El Controlled 0 Uncontrolled Projected Duration (Hours/Minutes)

Wind Speed - mi/hr Wind Dir From Deg (use 46 meters)

Projected TEDE mrem @ ___miles Projected Thyroid CDE  : mrem @ miles

7. Protective Action Recommendations to Offsite Officials NOUE, Alert, orSA O-None General Emergency0 1 OR 02 Page 34 of 51 REVISION 36

SEQUOYAH ACTIVATION AND OPERATION OFTHE TECHNICAL SUPPORT CENTER j

I EE P 6 61 APPENDIX B SED TURNOVER DATASHEET Page 2 of 2

8. Onsite Protective Actions Taken:

O ACCOUNTABILITY 0 SITE EVAC 0 SPECIFIC AREA EVAC

9. Field Monitoring Vans Activated: 0 Yes 0 No

10. Emergency Facilities Activated: 0 TSC 0 OSC 0 CECC

11. Status of personnel in the field dispatched by the SM/control room:

Names Status/Locations

.9

.4 I-,

SED responsibility was transferred at: Time: Date:_

From To SM SED in Control Room SED in the TSC Page 35 of 51 REVISION 36

SEQUOYAH ~ ACTIVATION AND OPERATION OF THE IJEPIP -6 TECHNICAL SUPPORT CENTER E APPENDIX C TAT RECOMMENDATION FORM Page 1 of 1 Chekone(*

El This is a drill. Recommendation No.

0 This is a real emergency.

To: Technical Assessment Manager From: Technical Assessment Team Leader kftals Data Time Prepared by TAT Member Recommendation:

Is there another parallel or related path that should be considered?

Reviewed by Technical Assessment Manager.

Initials Date/Time Feedback to TAT from TAM:

o Acceptance of Recommendation: 0 Assigned to OSC Team Letter o Rejection of Recommendation: l Assigned to Operations O Recommendation 'on hold": 0 Other (If rejected, provide a copy of completed form back to the TAT.)

-Page 36 of 51 REVISION 36

AC7lVATION AND OPERATION OF THE SEUOYAH TECHNICAL SUPPORT CENTER EPIP -6 APPENDIX D TSC ACCIDENT ASSESSMENT SHEET Page of 1 To: Technical Assessment Manager (cc: CECC PAT & NRC Coordinator)

From: SQN Technical Assessment Team (To be filled out when CS Isnot operable or as requested)

1. HEAT REMOVAL CAPABILITY (FR-H and FR-C; S/G Level, RCP Flow, ECCS Flow, Subcooling RCS):

-2. FUEL INTEGRITY: (Rad Monitors, Core Exit TICs, RCS Chemistry, RVLIS, H2 Concentration):

3. RADIOACTIVITY IN CONTAINMENT: (Rad Monitors, Rad Surveys, Fuel Integrity):

4. CONTAINMENT INTEGRITY: (FR-Z; CNTMT Pressure, CNTMT Breeches, Releases Outside CNTMT):

5. SUBCRITICALITY: (FR-S; Rods all inserted, NIS SR + IR Decreasing):

6. RCS INVENTORY: (FR-1; PZR Level, RVLIS, RCS Subcooling, Core Exit TICs):

7. OVERALL ASSESSMENT:

8. RECOMMENDATIONS:

TAT Leader: ime:_ Date:

Page 37 of 51 REVISION 36

[ I ~~ACTIVATION AND OPERATION OF THE lEI SEQUOYAH TECHNICAL SUPPORT CENTER l =

APPENDIX E PREDICTIVE RELEASE DATA SHEET Page 1 of 1 TO: CECC PAT DATE: TIME:_ UNIT:

DATA NEEDED FOR CECC TO PERFORM PREDICTIVE RELEASE METHODOLOGY

1. PRIMARY COOLANT CONCENTRATION Isotope Gas yCi/cc Liq yCl/m- SAMPLE DATA 1-131 DATE TIME 1-132 1-133 LOCATION 1-134 1-135 TEMPERATURE: DEG F CS-137 CS-138 PRESSURE PSIA KR-85m KR-85 GAS VOLUME: CC KR-87 KR-88 WATER MASS: GRAMS XE-133 XE-135 WATER LEVEL:____

2. CONCENTRATION OF HYDROGEN INCONTAINMENT ATMOSPHERE H CONC (MOLE  :%):_ DEGREESFF DATE:

CNTMT TEMP: - PSID TIME:

CNTMT PRESS_ _ LOCATION __

3. OPERATING POWER HISTORY (IF ICS DATA LINK INOPERABLE)

Date/Time of Shutdown:

Start End Avg Power Start End Avg Power Period Period in MWt Period Period in MWt

4. EXO-SENSOR CORE EXIT THERMOCOUPLE READINGS (IF ICS DATA LINK INOPERABLE)

Thermocouple Date Time Reading F Notes:

5. Rx WATER LEVEL HISTORY (IF 105DATA LINK INOP) see Ti-2s, Apperdx BPages5 C olC Date Time RVLIS% RCS Efev (ft) RCS Vol Gabs RSVlC~

DATA COLLECTED BY: _ _ _ _ _

- Page 38 of 51 REVISION 36

SEQUOYAH ACTIVAllON AND OPERATION OF THE I -

I I TECHNICAL SUPPORT CENTER E P -6 APPENDIX F I , PROTECTIVE ACTION RECOMMENDATIONS Page 1 of 1 Note: If conditions are unknown utilizing the flowchart, then answer NO.

general Emerge I CONTINUE ASSESSMENT v D ec ar e d

• Modify protective actions based on available plant and field monitoring information.

• Locate and evaluate localized hot spots. _

/ At 4k or beyond 5 miles is the Projected NO or Measured Dose

\ Greater than PAG

\Table I Liits U

4L RECOMMENDATION 1 RECOMMENDATION2 EVACUATE 2 miles radius- EVACUATE 2 mile radius and 10 miles downwind and 5 miles downwind AND AND SHELTER remainder of - SHELTER remainder of 10 mile EPZ 10 mile EPZ I - 4 Jable 1 Radioactivity Release Dose Note: Unknown conditions are assumed less than listed conditions TYPE Protective Action Guide (PAG) Umits Measured 3.9E-6 micro Curie/cc Iodine 131

__________ 1 Rem/hr External Dose Projected 1 Rem TEDE

____________ 5 Rem Thyroid CDE Page 39 of 51 REVISION 36

iSEQUOYAH l ACTIVATION AND OPERATION OF THElI I l TECHNICAL SUPPORTCENTER EPIP - 6 APPENDIX G CONTAINMENT SUMP OPERATION AND LEVEL GUIDANCE Page of 2 Part I Containment Level Information

1. The 11 percent containment level set point for switch over was specified to prevent an inappropriate automatic switch over to the containment sump for steam line breaks in the yard that could damage the RWST. Switch over, as required for a LOCA, is based on change in RWST level (i.e., volume of water injected). Based upon RWST Technical Specification limits and switch over setpoints, the actual sump level will be at least 63.5 percent (el. 693) at the time of switch over.

2. During the injection phase following a LOCA, the only function of the containment sump level instrumentation is to provide a permissive input for the switch over.

3. Until the inflow into the containment sump and the leakage out of it through the crane wall reaches equilibrium, the actual transient sump level could approach 90 percent. When instrumentation errors are considered, the sump level indication could go high off scale for a short period of time.

4. Actual equilibrium level in the containment sump is expected to be 63.5 percent (i.e., crane wall penetrations are sealed up to 63.5 percent, and more than enough water will be injected to reach this level; surplus water will flow into the area outside the crane wall). However, due to instrument inaccuracies, the indicated level could vary between 50 percent and 78 percent.

5. After the sump has reached equilibrium and temperature effects on instrumentation have stabilized, the indicated sump level should remain constant. Because the sump volume is large and will tend to mask small leaks, any significant trend showing an increase or decrease In level, however slow, should be investigated.

6. The containment sump is subject to vortexing, which could damage the pumps if the sump is operated at too low level. As long as the indicated level stays above 37 percent, the sump will operate as designed with full ECCS flow.

7. The limiting set point for sump operation at full flow (37 percent level) is based upon vortex prevention requirements.

8. If recirculation from the sump is required with a low sump level (less than 37 percent) following a large break LOCA, then the operator should be aware that vortex-free sump operation is no longer assured. If operation under these conditions is required, the probability of effective ECCS operation will improve if flow from the sump is reduced. Also, other system indicators (e.g., pump amps, pressure, and flow) should be monitored for signs of vortexing.

9. For near normal conditions (i.e., containment spray is no longer required and total flow from the sump is less than 11,000 galmin) the instrument inaccuracies are less than +/- 8 percent and a minimum indicated level of 18 percent will ensure vortex free sump operation.

10. Utilize the uExtemal Leakage Rates" notebook, in the affected unit Control Room, to anticipate areas of potentially high dose rates when sump recirculation is initiated.

Page 40 of 51 REVISION 36

SEQUOYAH ~~~ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP 6 1 APPENDIXG CONTAINMENT SUMP OPERATION AND LEVEL GUIDANCE Page 2 of 2 Part II Information on Blockage of Containment Sump Screens after establishing sump recirculation

1. MONITOR for indications of sump blockage. Transport of debris to the containment sump screens during sump recirculation could result in a flow restriction on the RHR and CS pump suction. Although significant sump clogging is not expected, the potential exists for loss of adequate NPSH resulting in loss of ECCS and CS flow.

EA-63-8, Monitoring for Containment Sump Blockage," provides guidance for the MCR staff on monitoring ECCS and CS Indications to detect the onset of sump clogging. The following may Indicate sump screen blockage:

ECCS flow, discharge pressure; and motor amps gradually dropping (unexplained) or erratic/dropping to zero (if adequate NPSH has been lost).

Note that RCS pressure rising will cause flow and motor amps to decrease.

• CS pump flow and motor amps gradually dropping or erratic/dropping to zero (if adequate NPSH has been lost).

K> 2. IF indications of sump clogging are observed, THEN the following actions should be evaluated:

a. Evaluate reducing containment spray flow and/or ECCS flow by stopping one train. This is expected to slow the rate of debris buildup and will reduce the differential pressure across the sump screens. If containment pressure is not excessive, reducing CS flow to single train is preferred over reducing ECCS flow. Caution should be exercised since deliberately stopping one train of ECCS or CS may violate accident analysis assumptions (a subsequent single failure will result in complete loss of flow).

b. Evaluate the need for RWST refill to allow realigning pump suction to RWST.

Caution should be exercised prior to pumping an additional large water volume into containment due to the potential for containment flooding resulting in loss of instrumentation and eventual loss of containment integrity.

c. If sump clogging results in severely degraded flow, then evaluate the need for entry into ECA-1 .1, "Loss of RHR Sump Recirculation." This ECA initiates actions to refill the RWST, allows reducing or stopping CS flow, initiates RCS cooldownfdepressurization, and Initiates RCS makeup from alternate source (normal charging).

d. Briefly stopping and then restarting all flow across sump screens (by stopping all ECCS and CS) may allow debris to fall off. (Screens are sloped to allow gravity to assist in debris removal). This action should NOT be recommended without carefully considering the impact on core temperatures and containment pressure.

Page 41 of 51 REVISION 36

TECHNICAL SUPPORT CENTER APPENDIX H ERCW CONCERNS FOR TECHNICAL ASSESSMENT TEAM Page 1 of 2

1. Provide direction for environmental qualification operating concerns for containment cooling following a non-LOCA event (e.g. loss of secondary coolant) inside containment. Items which should be addressed are listed below:

a. Cooldown the RCS to less than 3500 F within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and continue as conditions allow.

b. In case of failure of the normal RHR suction valve FCV-74-1 to open, continue cooldown using the steam generators.

c. Within one to four hours after event initiation, place at least two lower containment coolers in service. Ensure ERCW is aligned before placing coolers in service. This action will require entry into the annulus to manually open the ERCW valve if one train of power is lost. Preferably, all lower containment coolers should be placed in service.

(1) If A-train power is lost, A-train valves FCV-67-104, FCV-67-112, FCV-67-83 and FCV-67-91, located in the annulus (approx. el. 690) will have to be manually operated in order to place the B-train ERCW header to the B-train lower compartment coolers in service. See Appendix W, page 3, for the specific location of these valves.

(2) If B-train power is lost, B-train valves FCV-67-88, and FCV-67-96, FCV-67-99 and FCV-67-107, located in the annulus (approx. el. 690) will have to be manually operated In order to place the A-train ERCW header to the A-train lower compartment coolers in service. See Appendix W, page 3, for the specific location of these valves.

(3) The Temperature Control Valves (TOVs) for each Lower Compartment Cooler must be opened to obtain ERCW flow. The TCV's are operated from panel M-9 for Units 1 & 2 or can also be failed open from the Auxiliary Control Room via transfer switches.

d. Evaluate containment heat loads. If a reactor coolant pump is running, then at least three lower containment coolers should be in service.

Page 42 of 51 REVISION 36

- ~~ACTIVATION AND OPERATION OF WIE IEI TECHNICAL SUPPORT CENTER APPENDIX H ERCW CONCERNS FOR TECHNICAL ASSESSMENT TEAM Page 2 of 2

e. ERCW gages are located in the 669 Penetration Room. Expect that each string of ERCW entering containment would require >400 gpm if all coolers in that string are receiving flow. Evaluate the ERCW flow to the lower compartment coolers and consider reducing flow to other equipment such as the containment spray heat exchangers if the required flow is not available.

(The system flow balance assumes that containment spray flow will be removed if the lower compartment coolers are used.)

f. In case of failure of both the CVCS letdown and excess letdown flow paths, then evaluate use of the reactor vessel head vent system or pressurizer PORV.

2. Monitor ERCW screens and strainers. Within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after an operating basis earthquake (1/2 SSE), a loss of downstream dam, a stage I flood, a tomado warning or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following a LOCA, then perform the following actions

a. Isolate chlorination to ERCW.

b. Inspect ERCW traveling screens and place screens Into continuous backwash.

c. Inspect ERCW strainers differential pressure and place into continuous backwash.

3. For events other than those listed in previous step, then maintain the normal monitoring and cleaning frequency of the ERCW screens and strainers per O-SO-67-3.

Page 43 of 51 REVISION 36

jSEQUOYAH I ACTIVATION AND OPERATION OF THE lEPIP -6 APPENDIX I VENTILATION PROBLEMS Page 1 of 2 A. CONTROL BUILDING BATTERY ROOM EXHAUST FAN FAILURE AND 6.9KV SHUTDOWN BOARD ROOMS TEMPERATURE MONITOR With all control building battery room exhaust fans off there is a potential for Hydrogen buildup in the battery rooms. Calculations (EEB 800723 901 and EEB 800723 902) show that it will take approximately 11 days to reach potentially explosive limits of hydrogen in the room. The TSC staff shall monitor the time frame that the battery room exhaust fans are off. The TSC staff shall determine how and when the fans are to be returned to service prior to the explosive limits being reached.

Monitor the temperature of the 6900V shutdown board rooms within the first hour and then every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> In accordance with O-PI-OPS-000-606.0 to ensure that the temperature remains below 800F. If the temperature of a Board Room exceeds 800F, actions must be taken (as determined by the TSC) to reduce the temperature below 800F and the temperature of the affected Board Room(s) must be monitored at an increased frequency as determined by the TSC.

B. ISOLATION OF A LEAKING AIR OR WATER LINE WITHIN 2 HOURS FOLLOWING A LOCA or HELB The containment penetration configuration consisting of an outboard active valve and an inboard check valve could result in air or water leakage Into containment should:

• the outboard valve fail to close and

• the associated air or water line be ruptured as the result of a LOCA or HELB (Main Steam or Main Feedwater line break).

Air leakage results in an uncontrolled increase in containment pressure following a LOCA. Water leakage results in sump boron concentration dilution and a water level in containment above the design limit.

A HELB induced failure of an ERCW line In containment could result in loss of the LCCs which are needed to maintain acceptable long-term containment

-temperatures post-HELB. An alternate method of cooling containment under this scenario is to use the containment sprays to cool the air in the upper compartment and the air return fans (ARFs) to circulate this air from the upper compartment to the lower compartment. The fans/ductwork from the LCCs should be used to circulate this air throughout the lower compartment.

Page 44 of 51 REVISION 36

lISEOUJOYAH I TECHNICAL SUPPORT CENTER lEPIP -6 APPENDIX I VENTILATION PROBLEMS Page 2 of 2 The leaking air or water line needs to be isolated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of a LOCA or HELB. The following Table identifies the outboard isolation valve which needs to be confirmed to be closed and the action to take should positive indication that the listed valve is closed is not available.

Valve UNID Action 1-FSV-32-110 see EA-32-3 2-FSV-32-1 11 see EA-32-3 1-FSV-32-80 close 1-VLV-32-1830 or isolate ACA from SCSA and shutdown the ACA Compressor-A (0-CMP-32-60-A) 1-FSV-32-102 close 1-VLV-32-1920 or isolate ACA from SCSA and Xshutdown

________________ the ACA Compressor-B (0-CMP-32-86-B) 2-FSV-32-81 close 2-VLV-32-1834 or isolate ACA from SCSA and shutdown the ACA Compressor-A (0-CMP-32-60-A) 2-FSV-32-103 close 2-VLV-32-1919 or isolate ACA from SCSA and shutdown the ACA Compressor-B (0-CMP-32-86-B) 1,2-FCV-70-90 close 1,2-VLV-70-690 1,2-FCV-70-92 close 1,2-VLV-70-700 1,2-FCV-67-99 or close 1,2-VLV-67-523A*

1,2-FCV-67-107 1,2-FCV-67-83 or close 1,2-VLV-67-523B*.

1,2-FCV-67-91 1,2-FCV-67-88 or close 1,2-VLV-67-577A*

1,2-FCV-67-96 1,2-FCV-67-104 or close 1,2-YLV-67-577B*

1,2-FCV-67-112 Page 45 of 51 REVISION 36

TECHNICAL SUPPORT CENTER EPI -6 APPENDIX J CONTINGENCIES FOR CONTROL AND PROCESSING LARGE VOLUMES OF SECONDARY SIDE CONTAMINATED WATER Page 1 of 1 The method of processing large amounts of contaminated water in the secondary side of the plant due to a steam generator tube rupture will be determined by the Chemistry Lab, based on condensate samples for activity.

The preferred method is to process the water through the condensate D.I. Waste Regeneration System to the High Crud Tanks (HCT). The water can then be released to the release header using O-SI-CEM-077-400.1 or O-SI-CEM-077-400.2. Reference flow diagrams 1,2-47W838-1 and 4.

If the contamination levels of the condensate are almost within limits for release, consideration should be given to using one of the condensate D.. beds to reduce the activity level to a point that release using method one is possible. This will depend on the age and condition of the resins. Contact the WWPG manager or Technical Support Engineer for guidance.

If the contamination levels are high enough to prevent release, consider processing the water through a Demineralizer System sirnilar to the Rad Waste D.l. being supplied by Chem Nuclear, under agreement contract #93N7B-79294A-000.

Two methods of D.l. operation are discussed here. The first being the best method.

METHOD 1 (PREFERRED)

Process the water through the condensate D.l. Waste Regeneration System. This will provide a flow path from the condensate system through a vendor supplied demineralizer system back to the unit hotwell through an open manway (vacuum will have to be broken).

This will allow recirculation of water from the condensate system of up to 200 gpm back to the hotwell until the activity levels are at a point that the water can be released to the HCTs, or after Chem Lab analysis indicates that it can be saved as condensate.

METHOD 2 (ALTERNATE)

Process water through a vendor supplied D.l. System to the HCT's and then release the HCT's to the release header, using O-SI-CEM-077-400.1 or O-SI-CEM-077-400.2, as clean D.I. water. As this water is being removed additional make-up water will be required to maintain inventory in the unit hotwell.

Page 46 of 51 REVISION 36

.E SEQUOYAH-I IOYAH ACTIVATION A TECHNICAL AND OPERATION SUPPORT CENTER OFTHE EPIP 6 APPENDIX K PLANT PARAMETER DATA SHEETS Page 1 of 3 GENERAL INFORMATION Date: Time: - Unit:

1. CST level: Gallons (L1-2-230A) (L-2-233A)

2. SG Heat Sink: OCONDENSER :ATMOSPHERE 1

3. AFW Pump Running: 0 MD-A  : 0 MDB OTD SG Levels: NR: percent J

4 (u-3-39)  :(U-3-52) - (L-3-94) (U-3-107 5 SG Levels: WR: percent (1-13-43) (U-3-43) 1(U-S-99) (1398) 6 SG Pressures: WR: psig (PI-1-2A) (PI-"A)  : (PF1-2A) (PI-1-27A) 7 RVLIS: percent LOWER RANGE (U68--37) (Ll-68-370)

WIDE RANGE (L-368) (U-8-372)

PLENUM (11-369) (1--371) 8 PZR Level: percent (11-68-3) 1(-M68-320) 9 PZR Pressure: psig (P468 . (PI-68-340A) 10 RCS Pressure: psig WR: LOOP I HOT LEG (P-669) 11 RCS HL Temp: °F (rR1) j (TR68-24) (M-6"3) .(R68 65) 12 RCS CL Temp: F (TR) (TR-68-24) (jR-68j43) j (68-65) 13 RCS Flow: O RCPs Runrfng: 1 2 3 4 O Natural Ciclalon 14 ECCS Status: 0 Swxby 0 Ijedlng 0 Recosuaton 0 Spray 15 RWST Level: percent (LU-63-60) (16-1 16 CNTMT Sump Level: WR (1-63-176) 17 Charging SI Flow: gpm (FI-62-93) (FI-63-170) 18 CNTMT Press: NR - psid (P-30-44) (PI-30-45)

QUAD I QUAD3 19 Incore Thermocouples: OF (1of #41,28,24,56,5,29.6) (1of #54.12.8,40,4.3,7)

QUAD 2 QUAD 4

_________________________ (1 of #44,22,58,21,16,63,64) (1 of #60,9,45,6,46,42,36) 20 NIS Source Range: cps (N31) (N32)

DATA COLLECTED BY:-

Page 47 of 51 REVISION 36

SEQUOYAH ACTIVATION AND OPERAION OFTHE I EiP 6 1 TECHNICAL SUPPORT CENTER APPENDIX K PLANT PARAMETER DATA SHEETS Page 2 of 3:

RADIATION MONITORS Date: Time: Unit:

1 Lower Containment 0 Isolated 0 Blocked (M-12)

RM-90-106Acprn RM-904106B cpm (M-12) Parttclate (M-12) Total Gas RM-90-273 R1Hr RM-90-274 RnHr

. (M-30) #2 & 3 (M-30) 1 & #4 2 Upper Containment 0 Isolated 0 Blocked 0 To Lower (M-12)

RM-90-1 12A cpm RM-90-12B cpm (M-12) Paliculate (M-12) Total Gas RM9O-271 RfHr RM-90-272 R/Hr

_________________ (M-30) 2 & #3 (M-30) 1 & #4 3 Shield Bldg: Unit 1 RM-9040 uCvseo RM-90-260 mdhr (M-30) Release Rate (M-30) Low Range 1-FE-90-400 cfn RM-90-261 mr/hr (M-28) Flow (M-30) Hgh Range 4 Shield Bldg: Unit 2 - RM90-400D uCifsec RM-90-260 mrhr (M-30) Release Rate (M-30) Low Range 2-FE-90-400D cfm RM-90-261 mr/hr (M-28) Fbw (M-30) High Range 5 Aux Bldg Vent 0 Isolated 0 Bloded RM-90-101B cpm (M-12) (M-12) Toal Gas 6 SG Blowdown: RM90120A cpm RM90-121A cpm

%&U12) (M-12) 7 Condenser Exhaust RM-90-99cpm RM-90-1 19 cpm (M-12) (M-12)

RM-90-255 mr/hr RM-90-26 mr/hr (M-30) Mid Range (30) High Range 8 ERCW Header A RM-9013SAcpn- RM-90-14Acpm

. ~~~~~12) ~~(M (1ff412)

B RM-90-134A cpm RM-90141A cpm ffi _ ~~~~~ ~~(M-12)  :: M-12) 9 RHR Pump Rm: A RM-90-290 mr/hr RM-90-291 mr/hr (M-30) Low Range (M-30) High Range B RM-90-292 mr/hr RM-90-293 mrlhr (M-30) Low Range (M-30) High Pange 10 RCDT Pump Disch RM-90-277 mr/hr RM-90-278 mr/hr (M-30) ' ' SO) 1 Rx Floor/Eqpt Drain Disch RM-90-275 mrthr RM-90-276 mrthr M -30) (M-30) 12 Main Steam Lines RM-90-421 IC cW RM-90-423 tCvcc (M-30) (M-30)

RM-90-422 FCVo RM-90.424 pCVcc (M-30) (IJ40 13 Area Monitors RM90-59 mr/hr lRM-90-60 mr/hr RM-90-61 mrthr (M-12) (M-12)- (M-12)

DATA COLLECTED BY: -

Page 48 of 51 REVISIO)N 36

SEQUOYAH TECHNICAL ACTVAON AND TECHNICALSUPPORTCENTERSUPPORT OPERAIN CENTER OF E EPIP 6

- APPENDIX K PLANT PARAMETER DATA SHEETS Page 3 of 3 RADIATION RELEASES Date: ime: Unit:

Release Point:

Release Information:

Release Began at and expected to end at___ (for duration of hours).

Release Potential of - Ci in volume of ft3/gal Release Rates: f renrasinn i Stabl- 11 Introasina n Unknown Airborne Releases l_= _X _- Liquid Releases Gross Release Rates (uCsec) Concentration Flow Total Release Noble Gas l_______l Value Units Value Units Value Units lodines__

Particulate .

Isotopic Release Rates (uClsec)

Isotope Release Rate Met Data_

Date Time Sensor Elevation (in) Wind Speed (molsed) Wind Direction (from) Temnp Differential RemarkslComments:

DATA COLLECTED BY:

Page 49 of 51 REVISION 36

- ACTIVATION AND OPERATION OF THE IEQUOY -TECHNICAL SUPPORT CENTER :EPIP-6 I-APPENDIX-L -

REFERENCE MATERIALS LIST I Page of 1 The following reference materials are provided in the TSC:

1. Sequoyah Nuclear Plant FSAR.

2. Sequoyah Nuclear Plant Technical Specifications (Unit 1).

3. Sequoyah Nuclear Plant Technical Specifications (Unit 2).

4. Surveillance Instructions (Selected).7

5. Technical Instructions (Selected).1

6. Radiological Control Instructions.

7. Site Health and Safety Manual.

8. System Operating Instructions.:

Yk.I 9. General Operating Instructions.

10. REP and SQN and CECC Emergency Plan Implementing Procedures

11. Plant Functional Drawings.:

12. Abnormal Operating Procedures.

13. Emergency Operating Instructions.

1 Selection to be made by Technical Support Manager.

Page 50 of 51 REVISION 36

W SEQUOYAH l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER l EPIP - 6 1 Appendix M EMERGENCY RESPONDER NOlFICATION Page 1 of 1

_ _ __ __ ___ __ __ ___ _ _ _ _ _ _ _.___ _ _ _f _ _ _ _ _ :D a te :

ERO POSITION _ Replacement - Notifications SED NOTIFIED AT E AND FFD 0 Operations Manager NOTIFIED AT Q AND FFD Control Room Communicator NOTIFIED AT QAND FFD E RADCON Manager NOTIFIED AT 0 AND FFD O TAM NOTIFIED AT 3 AND FFD 3 TAT Leader NOTIFIED AT O AND FFD Q TAT Electrical Engineer NOTIFIED AT . AND FFD E TAT Mechanical Engineer NOTIFIED AT E AND FFD n TAT I&C Engineer NOTIFIED AT 0 AND FFD 0 TAT NOTIFIED AT E AND FFD 0 TAT NOTIFIED AT Q AND FFD0 Reactor Engineer NOTIFIED AT 0 AND FFD0 Operations Communicator NOTIFIED AT 0 AND FFD0 Chemistry Manager NOTIFIED AT Q AND FFDQ Maintenance Manager . NOTFE AT - AND FFDE Operations Advisor to TAT NOTIFIED AT AND FFD E]

EP Manager NOTIFIED AT a AND FFD 0 VP NOTIFIED AT a AND FFD 0 NRC Coordinator NOTIRED AT O AND FFD O TSC Logkeeper NOTIFIED AT QAND FFD Security Manager NOTIFIED AT C AND FFD0 TSC Clerk NOTIFIED AT E] AND FFD0 RADCON ICS Operator NOTIFIED AT 0 AND FFD 0 NOTIFIED AT 0 AND FFD 0 NOTIFIED AT 0 AND FFD0 NOTIFIED AT El AND FFDO NOTIFIED AT 0 AND FFD 0 NOTIFIED AT 0 AND FFD0 NOTIFIED AT 0 AND FFD NOTIFIED AT E AND FFD E Page 51 of 51 REVISION 36

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EMERGENCY PREPAREDNESS IMPLEMENTING PROCEDURE EPIP-1 7 FIRE EMERGENCY PROCEDURE REVISION 24 PREPARED BY: BILL PEGGRAM PHONE: 8360 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: RANDY FORD DATE: July 29,2003 EFFECTIVE DATE: August 12, 2003 LEVEL OF USE:: REFERENCE USE QUALITY-RELATED

HISTORY OF REVISION/REViEW

• Previously EPIP-17 had been Emergency Equipment and Supplies Procedure and had been canceled on 8/30/2002 when contents moved to EPIP-12. This is a new procedure issued for standardization as EPIP-17 to address Fire Response.

PAGE2 OF 4 REVISION 24

SQN FIRE EMERGENCY PROCEDURE l EPIP-17 TABLE OF CONTENTS 1.0 INTRODUCTON .................................................................................................................. 4 1.1 Purpose .................................................................... 4

2.0 REFERENCES

. ................................................................... 4 2.1 INDUSTRY DOCUMENTS .................................................................... 4 A. NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants ....... 4.......4 B. 10 CFR 50.47, Code of Federal Regulations .............................................................. 4 2.2 Plant Instructions .................................................................... 4 A. TVA Radiological Emergency Plan .................................................................... 4 B. VAN Fire Protection Report.......................................................................................4 C. EPIP-1, Emergency Plan Classification Matrix ............................................................ 4 D. AOP-N.01, Plant Fires .................................................................... 4 E. AOP-N.08, Appendix R Fire Safe Shutdown ............................................................... 4 3.0 INSTRUCTIONS .................................................................... 4 3.1 Initial Notification .................................................................... 4 3.2 Fire Response Team Responsibilities .................................................................... 4 3.3 Shift Manager Responsibilities . ................................................................... 5 3.4 Incident Commander Responsibilities .................................................................... 5 3.5 RADCON Representative Responsibilities .................................................................... 5 4.0 DOCUMENTATION .................................................................... 5 4.1 Records of Classified Emergencies .................................................................... 5 4.2 Drill and Exercise Records .................................................................... 6 5.0 ILLUSTRATIONSIAPPENDICES-NONE .................................................................... 6 PAGE 3 OF 6 REVISION 24

I SQN l FIRE EMERGENCY PROCEDURE EPIP-17

1.0 INTRODUCTION

1.1 Purpose To provide timely response to fire emergencies at Sequoyah and a mechanism to notify additional emergency personnel or resources as needed.

1.2 Scope This procedure applies to all fire emergencies at Sequoyah.

2.0 REFERENCES

2.1 Industry Documents A. NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants B. 10 CFR 50.47, Code of Federal Regulations 2.2 Plant Instructions A. TVA Radiological Emergency Plan B. TVAN Fire Protection Report C. EPIP-1, Emergency Plan Classification Matrix D. AOP-N.01, Plant Fires E. AOP-N.08, Appendix R Fire Safe Shutdown 3.0 INSTRUCTIONS 3.1 Initial Notification 3.1.1 Upon receiving a fire emergency call, OBTAIN:

• name of caller.

• location of fire.

• nature of fire.

3.1.2 NOTIFY the Shift Manager of the fire.

3.1.3 IN1ITATE the "Fire Alarm" if not already actuated.

PAGE 4 OF 6 REVISION 24

I SQN FIRE EMERGENCY PROCEDURE EPIP-17 3.2 Shift Manager Responsibilities 3.2.1 The Shift Manager will:

• DISPATCH Incident Commander to scene if fire is in plant operating areas.

• ESTABLISH and maintain communications with the Incident Commander.

• REFER to AOP-N.01, Plant Fires or AOP-N.08, Appendix R Fire Safe Shutdown for applicability based on the severity of the fire.

• EVALUATE EPIP-1, Emergency Plan Classification Matrix.

3.2.2 WHEN requested by the Fire Brigade Leader, NOTIFY the off-duty SQN fire protection personnel using the REP Call List.

3.3 Incident Commander Responsibilities 3.3.1 The Incident Commander will:

• ESTABLISH radio communication with the Shift Manager.

• INFORM Shift Manager of ongoing situation(s).

• EVALUATE potential impact on plant equipment and safe shutdown capability.

3.4 RADCON Representative Responsibilities 3.4.1 If the fire is in an area containing Radioactive Materials, the RADCON Representative will:

• ADVISE the Incident Commander of radiological hazards.

• ENSURE the Incident Commander is aware of areas of significant radiation exposure and airborne radioactivity that may affect stay time for team members.

• NOTIFY the Incident Commander of any team members limitations in regards to stay time.

4.0 DOCUMENTATION 4.1 Records of Classified Emergencies The materials generated in support of key actions during an actual emergency classified as NOUE or higher are considered Lifetime retention Non-QA records.

Materials shall be forwarded to the EP Manager who shall submit any records deemed necessary to demonstrate performance to the Corporate EP Manager for storage.

PAGE 5 OF 6 REVISION 24

SQN FIRE EMERGENCY PROCEDURE EPIP-17 4.2 EP Drill and Exercise Records The materials deemed necessary to demonstrate performance of key actions during EP drills are considered Non-QA records. These records shall be forwarded to the EP Manager who shall retain records deemed necessary to demonstrate six-year plan performance for six years. The EP Manager shall retain other records in this category for three years.

4.3 Routine Fire Response Records The records and retention requirements for routine fire response and drills are specified in the Fire Protection Report 5.0 ILLUSTRATIONSIAPPENDICES NONE PAGE 6 OF 6 REVISION 24