ML032660125
| ML032660125 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/11/2003 |
| From: | Salas P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EPIP-16, Rev 5, EPIP-6, Rev 37 | |
| Download: ML032660125 (63) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 September 11, 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) REVISION In accordance with the requirements of 10 CFR 50, Appendix E, Section V, the enclosure provides the following EPIP:
EPIP Revision Title EPIP-6 37 Activation and Operation of the Technical Support Center EPIP-16 5 Termination and Recovery This letter is being sent in accordance with NRC RIS 2001-05.
If you have any questions concerning this matter, please telephonye me at (423) 843-7170 or J. D. Smith at (423) 843-6672.
PedrX. as Licensing and Industry Affairs Manager Enclosure 4A045 PRinledon ecyded paper
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 6 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER Revision 37 QUALITY RELATED PREPARED BY: D. A. Porter RESPONSIBLE ORGANIZATION: Emergency Preparedness APPROVED BY: J. Randy Ford Date: 09/04/2003 EFFECTIVE DATE: 09/04/2003 Level of Use: Reference Page 1 of 51 REVISION 37
ISEQUOYAH l
l l
ACTIVATION AND OPERATION OF THE
~~~~~TECHNICAL SUPPORT CENTER E
EPI 6 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 10/01/2001 Revised App L to instruct the clerks to disable "Memory Fax" option (PER 01-006615-000). Deleted App Y (PER 01-008461-000).
Revised Title for App Z due to no longer having equipment listed in App. Minor formatting changes.
35 06/1812003 Alt Intent Change. 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 in App. 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 "v for consistency.
Revised initial 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 Clerk's chklst on Fax memory due to new fax machines. Added "Directs onsite RADCON activities.' To RC Mgr checklist. Added and changed several items on Maint Mgrs. Checklist. Added ERN and eSOMS to Ops Corn.,
TSC Logkeeper's, Maintenance Manager's and RADOON Manager's 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 08/0812003 5, 6, 26, 28, 40, Intent Change. Added information on containment sump blockage 41 in response to NRC Bulletin 2003-01.
37 09104/2003 36, 40 Intent Change. Revised containment sump level vortexing setpoint as a result of DCN E20591 A. Changed Feedback to TAT from TAM recommendations wording on App.C.
Page 2 of 1 REVISION 37
SEQUOYAH l
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER lP EPIP 6 l TABLE OF CONTENTS Section Title Page Table of Contents.............................................................................................................. 3 1.0 PURPOSE ...... 5
2.0 REFERENCES
............................................... ........................................................... 5 3.0 INSTRUCTIONS .......................... 5 3.1 Activation........................... 5 3.2 Activation Methods ........................... 5 3.3 Call List .......................... 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 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 A.10 Chemistry Manager ......................... 22 Checklist A.1 1 NRC Coordinator ......................... 23 Checklist A.12 Control Room Communicator ......................... 24 Checklist A. 13 Maintenance Manager ......................... 26 Checklist A. 14 Technical Assessment Team Leader . ......................... 28 Checklist A. 15 EP Manager ......................... 31 Checklist A. 16 TSC Logkeeper............. ............ 32 Checklist A. 17 TSC Clerical.............. ........... 33 (Continued)
Page 3 of 51 REVISION 37
SEaUOYAH I ACTIVATION AND OPERATION OF THE IEPIP 6 L SEQUOYAH I TECHNICAL SUPPORT CENTER l E 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 37
SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 61 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 (OSC)"
EPIP-8, "Personnel Accountability and Evacuation" EPIP-1 1, "Security and Access Control" EPIP-13, "Dose Assessment" EPIP-14, "Radiological Control Response" EPIP-15, *Emergency Exposure Guidelines' EPIP-16, Termination and Recovery' 0-SO-67-3, ERCW Strainers and Traveling Screens Memorandum from J. B. Hosmer to R. J. Johnson dated 1/1 5/88, 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 37
SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I
PIP 6 3.3 Call Ust 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 List 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 I. 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 6of 51 REVISION 37
SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP61 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 37
SEQUOYAH l ACTIVATION AND OPERATION OF THE 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 37
SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I DPI 61 APPENDIX A, CHECKLIST A.01 SITE VICE PRESIDENT Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST i___ ENTER badge into the TSC Accountability Card Reader.
SIGN IN on the OrganizationaVStaffing 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 Media Relations Specialist.
I____ 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 37
l SEQUOYAH ACTIVAION AND OPERATION OF THE I EPIP 61 l ~~TECHNICAL SUPPORT CENTERlI
}
APPENDIX A, CHECKLIST A.02 SITE EMERGENCY DIRECTOR Page 1 of 3 SUPPORT CENTER CHECKLIST INITIAL ACTIVATION OF THE TECHNICAL with Appendix B,
/_ OBTAIN turnover briefing from SM/SED in accordance (may be done concurrent with this Appendix).
, ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.............
Reader.
I_ ENTER badge into the TSC Accountability Card badge.
___ SIGN IN on the staffing chart and PUT ON position EPIP-8, Appendix I)
/ SIGN roster upon arrival. (Ref.: use roster from J... ESTABLISH log of communications/events.
determine if the Director
/ ESTABLSH contact with the CEOC Director and the site and state.
with has assumed responsibility for primary contact CECC Director assumes (NOTE: the 005 has this responsibility until the the function.)
IF the
~ emergency
~ ~ ~ ~ ~ classification
~ ~ ~ ~ ~ ~is~escalated and the CEOC has not assumed
~ ~ ~ ........ . ..
, ~~ ~
~ ~~~ ~
~ ~ THEN ensure the State is responsibility for communications with the State, EPIP-4 or EPIP-5, as notified within 15 minutes by implementing EPIP-3, appropriate.
in effect such as
/_ CHECK the status of emergency actions already or site evacuation.
emergency notifications (NRC, State, etc.) accountability (Operations, I_~~1 REVIEW checklist completion status for key positions j
~~~~Technical Assessment Manager, RADOON, Maintenance Manager, etc.).
I operability and checklists are ENSURE minimum staffing is present for TSC
~~~~~complete. The following individuals must be present:
4 O SED 4 RADCON Manager O~~~~
El Operations Manager or Operations Communicator and Elec Engr)
El TAM or TATL or (Rx Engr and Mech Engr Page 10 of 1 REVISION 37
SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP 6 ffi 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 SM/SED and O NOTIFY CECC that the TSC is operational.
O NOTIFY OSC that the TSC is operational.
I___ 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 responsibilitv 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 responsibilitv 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 TSC/OSC staff on the current situation.
- Updates the plant staff on plant status and emergency conditions.
- Directs activities of onsite emergency organizations.
Page 11 of 51 REVISION 37
SEQUOYAH I l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER _
I EPIP6 l 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 site 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 responsibilitv 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, "Emergency 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-1 3, 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 37
SEQUOYAH ACTIVATION AND OPERATION OFTHE TECHNICAL SUPPORT CENTER EPIP 6]
APPENDIX A, CHECKLIST A.04 OPERATIONS 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)
_/ ESTABUSH log of communications/events.
LOG ON to ICS.
ESTABUSH 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.
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 13of 51 REVISION 37
EQUOYAH L
l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 6 APPENDIX A, CHECKLIST A.04 V> .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 37
rSEQUOYAH I ACTIVATION AND OPERATION OF THE EPIP 61 TECHNICAL SUPPORT CENTER E o 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)
ESTABUSH log of communications/events.
CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.
_/_ CHECK status of staff El TATL, l Reactor Engineer, 0 Mechanical Engineer, E Electrical Engineer, E TAT Ops Advisor E 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 37
SEQUOYAH l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 61 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 REVISION 37
SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP6 l APPENDIX A, CHECKLIST A.06 OPERATIONS ADVISOR, TAT Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST I__ 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)
I__ LOG on to ICS.
ESTABLISH contact with the Control Room. (Dial x101, keep on mute as much as possible.)
/__ 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.
- Completes portions of plant parameters data sheets (Appendix K) as needed.
Plots/trends as designated by TAM.
Page 17 of 51 REVISION 37 I1
l SEQUOYAH l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER l 6 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.
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).
- Monitors plant status boards and ICS.
- 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 Managers use (may use eSOMS, ERN Data).
Page 18 of 51 REVISION 37
SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER E 61 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.
/__ 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 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 needed.
- Controls access to the Site and Control Rooms.
- Reports on site accountability/evacuation as defined in SQN EPIP-8.
- Assures an officer is dispatched to areas outside the protected area such as the Sequoyah Training Center, Security Training Center, Livewell, 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. (SQN 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.
- Remain aware of Plant Radiological Conditions and report locations(s) of Security Personnel/Patrols (as needed) to the RADCON Manager and the SED.
Page 19 of 51 REVISION 37 JS
SEQUOYAH ACTIVATION AND OPERATION OF THE DI TECHNICAL SUPPORT CENTER E Pr P
APPENDIX A, CHECKLIST A.09 RADCON MANAGER Page 1 of 2 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST
/ ENTER badge into the TSC Accountability Card Reader.
SIGN INon 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.
ESTABLISH 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.
LOG on to ICS and the Emergency Response Network (must be activated from the CECC and OSC).
/ CHECK the status of emergency actions already in effect such as RADCON personnel in the field, and Accountability or Site Evacuation.
/ ESTABUSH communications with environs monitoring van (IF dispatched and not under the control of the CECC).
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 RAM/RAC informed of site radiological conditions.
Page 20 of 51 REVISION 37
OEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP 6 g 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 KI, by following SON EPIP-1 4, 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 SON 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.
- 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 37
I SEQUOYAH I
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 61 APPENDIX A, CHECKLIST A.10 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.
/_ ESTABUSH 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 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 37
t SEQUOYAH l
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 6 APPENDIX A, CHECKLIST A.1 1 NRC COORDINATOR Page 1 of 1 INITIAL ACTIVATION OF THE TECHNICAL SUPPORT CENTER CHECKLIST 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)
I_/_ ESTABLISH log of communications/events.
_I__ CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.
lI 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).
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Page 23 of REVISION 37
SEQUOYAH ACTIVATION AND OPERATION OF THE EPIP6 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 log of communications/events.
/___ ESTABUSH contact with the TSC Operations Communicator and OSC Operations Advisor. (x101).
/___ CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.
/____ LOCATE all Operations personnelteams currently or previously tasked and ensure each is tracked on the AUO OSC Team board.
OPERATIONAL RESPONSIBILITIES LIST
- 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.
Page 24 of 51 REVISION 37
SEQUOYAH Il ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP6 l APPENDIX A, CHECKLIST A.12 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 personnelteams dispatched by the Shift Manager.
OSC maintenance activities status are available through the Emergency Response Network.
- 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 37
SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 61 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 37
SEQUOYAH ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 1 APPENDIX A, CHECKLIST A.13 MAINTENANCE MANAGER Page 2 of 2 OPERATIONAL RESPONSIBILITIES LIST
- Communicates with the Assistant OSC Manager on matters concerning equipment and/or plant assessments.
Page 27 of 51 REVISION 37
SEQUOYAH l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP 6 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.
I SIGN IN on the staffing chart and PUT ON position badge.
SIGN roster upon arrival. (Ref.: use roster from EPIP-8, Appendix 1)
_I_ ESTABUSH a log of communications/activities.
ESTABUSH contact with the Technical Assessment Manager.
I____ ESTABUSH 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 performs 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.
Page 28 of 51 REVISION 37
SEQUOYAH l
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 6I 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.
- Provides Technical Assessment to TAM on Appendix D when requested.
- 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.
- In the 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 37
I SEQUOYAH ACTIVATION AND OPERATION OF THE I TECHNICAL SUPPORT CENTER APPENDIX A, CHECKUST 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, if 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, -Al 0, and -Al 1)
- 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.
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. .. ......................... .. .. ... . . : ,*n Page 30 of 51 REVISION 37
SEQUOYAH l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP6 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)
I/___ ESTABLISH log of communications/events.
CHECK the status of emergency actions already in effect such as Accountability or Site Evacuation.
/____ VERIFIES checklists are distributed and are being completed.
I/___ VERIFIES all essential positions are filled.
/___ VERIFIES all activation activities (TSC and OSC) are proceeding normally.
I/__ CALL IN Clerical Support and other personnel as necessary (actions may be delegated).
OPERATIONAL RESPONSIBILITIES LIST
- Advises the SED regarding overall REP, use of EPIPs, emergency equipment availability, and coordination with the CECC.
- 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.
Page 31 of 51 REVISION 37
SEQUOYAH l
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 6 APPENDIX A, CHECKLIST A.16 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.
I I_ 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 in classifications 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 0 Ops Communicator 0 TAT Operations Advisor 0 EP Manager O TAM 0 Maintenance Manager l NRC Coordinator Security Manager I] Control Room Communicator (on deactivation)
Page 32 of 51 REVISION 37
SEQUOYAH l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER I EPIP 6 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.
I____ 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.
- 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 37
I SEQUOYAH I ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER 1 EPIP 6 APPENDIX B SED TURNOVER DATA SHEET Page 1 of 2
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: ElYes EliNo Liquid E Yes No Gaseous l Yes El No
- 6. Dose Assessment Initiated: El Yes El No E Filtered E Unfiltered El Monitored E Unmonitored El Controlled E 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, or SAE E None General Emergency 1 OR 2 Page 34 of 51 REVISION 37
l SEQUOYAH I
l ACTIVATION AND OPERATION OF THE lEQUOYAHTECHNICAL SUPPORT CENTER I
I EPIP E 61 APPENDIX B SED TURNOVER DATASHEET Page 2 of 2
- 8. Onsite Protective Actions Taken:
l ACCOUNTABILITY E SITE EVAC O SPECIFIC AREA EVAC
- 9. Field Monitoring Vans Activated: l Yes 0 No
- 11. Status of personnel in the field dispatched by the SM/control room:
Names I Status/Locations 1.
SED responsibility was transferred at: Time: Date:_
From To SM SED in Control Room SED in the TSC Page 35 of 51 REVISION 37
l SEQUOYAH l ACTIVATION AND OPERATlON OF THE JEPIP-6 TECHNICAL SUPPORT CENTER APPENDIX C TAT RECOMMENDATION FORM Page 1 of 1 check one Recommendation I This is a dill. No.
O This is a real emergency.
To: Technical Assessment Manager From: Technical Assessment Team Leader Initals Date Tome 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 Accepted - Assigned to OSC 0 Rejection of Recommendation:
o Accepted - Assigned to Operations 0 Recommendation on hold":
o Other (If rejected, provide a copy of completed form back to the TAT.)
Page 36 of 51 REVISION 37
lEQUOYH l ACTIVATION AND OPERATION OF THE JEPIP-6 I SEQUOYAHI TECHNICAL SUPPORT CENTER APPENDIX D TSC ACCIDENT ASSESSMENT SHEET Page 1 of 1 To: Technical Assessment Manager (cc: CECC PAT & NRC Coordinator)
From: SON Technical Assessment Team (To be filled out when ICS is not operable or as requested)
- 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):
- 7. OVERALL ASSESSMENT:
- 8. RECOMMENDATIONS:
TAT Leader:_ Time: Date:_-
Page 37 of 51 REVISION 37
ACTIVATION AND OPERATION OF THE IEQUOYH ITECHNICAL SUPPORT CENTER 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 pCVcc Liq pCuml 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 IN CONTAINMENT ATMOSPHERE H CONC (MOLE %): DEGREES F 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 ICS DATA LINK INOP)
- See Tl-28, Appendix B,Page 5 Date Time RVLIS% RCS Elev (ft) RCS Vol Gals RCS Vol CuFt DATA COLLECTED BY:
Page 38 of 51 REVISION 37
I l
ISEQUOYAH I ACTIVATON AND OPERATION OF THE TECHNICAL SUPPORT CENTER 1 EPIP-6 APPENDIX F PROTECTIVE ACTION RECOMMENDATIONS Page 1 of 1 Note: If conditions are unknown utilizing the flowchart, then answer NO.
MMMMN%-
neral Emergenc3 CONTINUE ASSESSMENT Ee D ecIar ed
- Modify protective actions based
. _ ~1_ MEEWp on available plant and field monitoring information.
- Locate and evaluate localized 1
hot spots.
L miles is the Projected NO or Measured Dose Greater than PAG Table 1 Limits YES RECOMMENDATION 1 RECOMMENDATION 2 EVACUATE 2 miles radius EVACUATE 2 mile radius and 10 miles downwind and 5 miles downwind AND AND SHELTER remainder of II SHELTER remainder of 10 mile EPZ 10 mile EPZ I
p P -
Table I Radioactivity Release Dose Note: Unknown conditions are assumed less than listed conditions TYPE Protective Action Guide (PAG) Limits 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 37
lEOUOYAH
§ SEQOY HI ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP -6 I APPENDIX G CONTAINMENT SUMP OPERATION AND LEVEL GUIDANCE Page 1 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 22 percent, the sump will operate as designed with full ECCS flow.
- 7. The limiting set point for sump operation at full flow (22 percent level) is based upon vortex prevention requirements.
- 8. If recirculation from the sump is required with a low sump level (less than 22 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 "External Leakage Rates" notebook, in the affected unit Control Room, to anticipate areas of potentially high dose rates when sump recirculation is initiated.
Page 40of 51 REVISION 37
SEQUOYAH l ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER IEPIP I - 6 1 APPENDIX G 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).
- 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).
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 cooldown/depressurization, 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 37
SEOUOY" l ACTIVATION AND OPERATION OF THE I l -6 SEQUOYH 1TECHNICAL SUPPORT CENTER I APPENDIX H ERCW CONCERNS FOR TECHNICAL ASSESSMENT TEAM Page 1 of 2 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.
>,,.. ........ N ...... . . . ... . I . ...'t. ii0fytw
.. -hammer,must I becnsidered-.-Parametrs to c.Bonsider are cotainmet
- 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-67-1 04, FCV-67-1 12, 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 EROW 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-67-1 07, 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 (TCV's) 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 1 REVISION 37
ACTIVATION AND OPERATION OF THE IlEQUOYAH I TECHNICAL SUPPORT CENTER lP -6 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 tornado 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 37
SEQUOYAH 1 I l
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER lEPIP I _6 6 1 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 80 0F 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 37
SEQUOYAH SEQQYA I ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP -6 IrEr 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 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 shutdown 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-VLV-67-577B*
1,2-FCV-67-112 Page 45 of 51 REVISION 37
SEQUOYAH ACTIVATION AND OPERATION OF THE I e TECHNICAL SUPPORT CENTER I 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.l. Waste Regeneration System to the High Crud Tanks (HCT). The water can then be released to the release header using 0-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.l. 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 similar to the Rad Waste D.I. 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 HCrs, 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 HCTs and then release the HCT's to the release header, using O-SI-CEM-077-400.1 or 0-SI-CEM-077-400.2, as clean D.l. 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 37
SEQUOYAH I ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER JEPIP E -6 APPENDIX K PLANT PARAMETER DATA SHEETS Page 1 of 3 GENERAL INFORMATION Date: Time: Unit:
- 1. CST level: Gallons (UL-2-230A) (U-2-233A)
- 2. SG Heat Sink 0 CONDENSER 0 ATMOSPHERE
- 3. AFW Pump Running: 0 MD-A 0 MD-B 0 TD 4 SG Levels: NR: percent (U-3-39) (U-3-52) (U-3-94) (U-3-107) 5 SG Levels: WR: percent (U-3-43) (U-3-43) (U-3-99) (LI-3-98) 6 SG Pressures: WR: psig (PI-1-2A) (PI-1-9A) (PI-1-20A) (PI-1-27A) 7 RVLIS: percent LOWER RANGE (U-68-367) (U.68-370)
WIDE RANGE (U-68-368) (U-68-372)
PLENUM (U-68-369) (U-68-371) 8 PZR Level: percent (U-68-335) (U-68-320) 9 PZR Pressure: psig (PI-68-342A) (PI-68-340A) 10 RCS Pressure: psig WR: LOOP 1 HOT LEG (Pl-68-69) 11 RCS HL Temp: F (TR-68-1) (TR-68-24) (TR-68-43) 7TR-68-65) 12 RCS CL Temp: F (TR-68-1) (TR-68-24) (TR-68-43) (TR-68-65) 13 RCS Flow: 0 RCPs Running: 1 2 3 4 0 Natural Circulation 14 ECCS Status: 0 Stancby 0 Injecng 0 Recirculation 0 Spray 15 RWST Level: percent (LU-63-50) (U-651) 16 CNTMT Sump Level: WR (LI-63-176) 17 Charging Si Flow: gpm (FI-62-93) (FI-63-170) 18 CNTMT Press: NR - psid (P3-30-44) (P3-30-45)
QUADI1 QUAD 3 19 Incore Thermocouples: °F (1of #41,28,24,56,55,29,6) (1 of #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 37
SEUA ACTIVATION AND OPERATION OF THE JEIP TECHNICAL SUPPORT CENTER APPENDIX K N PLANT PARAMETER DATA SHEETS Page 2 of 3 RADIATION MONITORS Date: Time: Unit:
1 Lower Containment 0 Isolated 0 Blocked (M -1 2) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
RM-90-106A cpm RM-90-106B cpm (M-12) Parliculate (M-12) Total Gas RM90-273 R/Hr RM-90-274 R/Hr (M-30) 2& 3 (M-30) 1 & #4 2 Upper Containment 0 Isolated 0 Blocked 0 To Lower (M-12)
RM-90-112A cpm RM-90-112B cpm (M-12) Particulate (M-12) Total Gas RM-90-271 RJHr RM-90-272 R/Hr (M-30) #2 & #3 (M-30) #1 & #4 3 Shield Bldg: Unit 1 RM-90-400 uCVsec RM-90-260 mrhr (M-30) Release Rate (M-30) Low Range 1-FE-90-400 cfm RM-90-261 mr/hr (M-28) Flow (M-30) High Range 4 Shield Bldg: Unit 2 RM-90-400D uCsec RM-90-260 mr/hr (M-30) Release Rate (M-30) Low Range 2-FE-90-400D cim RM-90-261 mr/hr (M-28) Flow (M-30) High Range 6 Aux Bldg Vent 0 Isolated 0 Blocked RM-90-101B cpm (M-12) (M-12) Total Gas 6 SG Blowdown: RM90-120A cpm RM-90-121A cpm (M-12) (M-12) 7 Condenser Exhaust RM-90-99 cpm RM-90-119 cpm (M-12) (M-12)
RM-90-255 mr/hr RM-90-256 mr/hr (M-30) Mid Range (M-30) High Range 8 ERCW Header A RM-90-133Acpm RM-90-140Acpm (M-12) (M-12)
B RM-90-134Acpm RM-90-141Acpm (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 mr/hr (M-30) Low Range (M-30) High Range 10 RCDT Pump Disch RM-90-277 mr/hr RM-90-278 mr/hr (M-30) (M-30) 11 Rx Floor/Eqpt Drain Disch RM-90-275 mr/hr RM-90-276 mr/hr (M-30) (M-30) 12 Main Steam Lines RM-90-421 pCl/cc RM-90-423 VCi/cc (M-30) (M-30)
RM-90-422 VC/cc RM-90-424 pCilcc (M-30) (M-30) 13 Area Monitors RM-90-59 mr/hr RM-90-60 mr/hr RM-90-61 mr/hr I (M-12) (M-12) (M-12)
DATA COLLECTED BY:
Page 48 of 51 REVISION 37
ACTIVATION AND OPERATION OF THE IEQUOYH ITECHNICAL SUPPORT CENTER EPIP-6 APPENDIX K PLANT PARAMETER DATA SHEETS Page 3 of 3 RADIATION RELEASES Date: Time: Unit: -
Release Point:
Release Information:
Release Began at _ _ and expected to end at_ _ (for duration of _ hours).
RAlasA Potential nf ri in volume nf fta/nal Release Rates: 0 Decreasing 0 Stable 0 Increasing Unknown Airborne Releases l Liquid Releases Gross Release ates uC/sec l Concentration Flow l Total Release Noble Gas Isotope Value Units Value Units Value Units lodines Particulate Isotopic Release Rates (uCi/sec) _
Isotope Release Rate l X Met Data Date lime Sensor Elevation (m) Wind Speed (m/sec) Wind Direction (from) Temp Differential RemarkslComments:
DATA COLLECTED BY:
Page 49 of 51 REVISION 37
§ SEQUOYAH l ACTIVATION AND OPERAllON OF THE JEPIP-6 TECHNICAL SUPPORT CENTER APPENDIX L REFERENCE MATERIALS LIST Page 1 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). 1
- 5. Technical Instructions (Selected). 1
- 6. Radiological Control Instructions.
- 7. Site Health and Safety Manual.
- 8. System Operating Instructions.
- 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 37
ACTIVATION AND OPERATION OF THE EPI -
TECHNICAL SUPPORT CENTER Appendix M EMERGENCY RESPONDER NOTIFICATION Page 1 of 1 Date:
ERO POSITION l Replacement [ Notifications SED NOTIFIED AT _ AND FFD, Operations Manager NOTIFIED AT OAND FFD Control Room Communicator NOiFIED AT - ANDFFD RADCON Manager NOTIFIED AT __ AND FF TAM NOTIREDAT O ANDFFDO TAT Leader NOIFIED AT 0ANDFFD O TAT Electrical Engineer NOlIFIED AT O AND FFD Q TAT Mechanical Engineer NOTIFIED AT 0 AND FFD0 TAT I&C Engineer NOTIFIED AT 0 AND FFD [
TAT NOTIFIED AT E AND FFD TAT NOTIFIED AT 0 AND FFD Reactor Engineer NOTIFIED AT _ ANDFFD Operations Communicator NOTIFIED AT [ ANDFFD O Chemistry Manager .NoTIFED AT _ ANDFFD O Maintenance Manager NOTIFIED AT. AND FFD O Operations Advisor to TAT NOTIFIED AT [ ANDFFD 0 EP Manager NOTIFIED AT 0 AND FFD 0 VP NOTIFIED AT [ AND FFD NRC Coordinator NOTIFIED AT O AND FFD TSC Logkeeper NOTIFIED AT Q AND FFD 0 Security Manager NOTIFIED AT [ AND FFD 0 TSC Clerk NOTIFIED AT Q AND FFD 0 RADCON ICS Operator NOTIFIED AT Q AND FFD NOTIFIED AT 0 AND FF00 N07IFIED AT Q AND FF 0 NOTIFIED AT { AND FFD NOTIFIED AT O AND FFD0 NOTIFIED AT 0 AND FFD0 NOTIFIED AT Q AND FFD NOTIFIED AT a AND FFD 0 Page 51 of 51 REVISION 37
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-1 6 TERMINATION AND RECOVERY Revision 5 QUALITY RELATED PREPARED/I PROOFREAD BY- Bill Peonram RESPONSIBLE ORGANIZATION: Emerger mv Prenaredness APPROVED BY Randy Ford EFFECTIVE DATE: August 29, 2003 LEVEL OF USE: REFERENCE
REVISION HISTORY REV EFFECTIVE PAGES
SUMMARY
OF CHANGES DATE EFFECTED 5 08/29/2003 2, 7, 8, 9 Intent Revision. Added a revision history. Changed records section. Added step to contact CECC to ensure they can perform their functions. Moved SED sign off to end of Appendix A and B. Removed source notes section.
_ __________ _________ Reformatted Checklists.
PAGE 2 OF 11 REVISION 5
TABLE OF CONTENTS Section Title........... Page Table of Contents............ 3 1.0 PURPOSE .4
2.0 REFERENCES
.4 2.1 Interface Documents .4 2.2 Development Documents .4 3.0 INSTRUCTIONS .4 3.1 Termination .4 3.2 Recovery .5 3.3 Local Recovery Center (LRC) .6 3.4 Radiation Dose Management .6 4.0 RECORDS RETENTION .7 4.1. Records of Classified Emergencies .7 4.2. Drill and Exercise Records .7 APPENDIXES Appendix A, Termination Guidelines .8 Appendix B, Recovery Guidelines .10 Appendix C, TVA Recovery Organization .11 PAGE 3 OF 11 REVISION 5
1.0 PURPOSE This procedure gives guidance on terminating an emergency classification by the Site Emergency Director (SED) following staffing of the Emergency Response Facilities (ERFs), and the development of recovery procedures to efficiently utilize resources and keep radiation doses ALARA.
This procedure also provides a minimum list, in the form of a checklist, of the plant system parameters to be considered prior to termination of an emergency. A checklist of guidelines for development of a recovery strategy are also included.
These checklist should not be considered as all inclusive. They should be used only as a minimum basis, excluding the specifics of the event, for termination and recovery.
2.0 REFERENCES
2.1 Interface Documents A. NP Radiological Emergency Plan B. EPIP-1 5, Emergency Exposure Guidelines 2.2 Development Documents A. None.
3.0 INSTRUCTIONS 3.1 Termination A. The decision to terminate an event where the ERFs are not staffed is the responsibility of the SM /SED.
B. The decision to terminate an event following staffing of the ERFs will be made by the SED after consultation with the plant technical and operations staffs and coordinated with the CECC Director. This decision will be based upon a comprehensive review of plant system parameters and completion of Appendix A, Termination Guidelines.
C. Should an emergency situation occur following the termination, the SED shall reactivate the Emergency Response Organization.
PAGE 4 OF 11 REVISION 5
3.2 Recovery A. The overall goal of the recovery effort is to assess the plant condition resulting from the emergency, perform clean-up and repair operations to restore the plant to a predetermined status.
B. The decision to enter the recovery phase will be made by the SED with concurrence from the CECC Director and the Senior Vice President, Nuclear Operations. Following the decision to enter into the recovery phase, the Senior Vice President, Nuclear Operations or his designee will direct the overall recovery effort.
C. If the recovery phase is expected to be a long-term process, he may form a team to be responsible for continuous control of the recovery operation. The organizational structure of such a team would be contingent upon the emergency situation and procedures required for recovery. The Local Recovery Center (LRC) is available to provide additional office space near the site for the recovery team at the discretion of the Senior Vice President, Nuclear Operations. See section 3.3 for information concerning the Local Recovery Center.
D. All major post accident onsite recovery measures shall be performed in accordance with written procedures.
E. Personnel protective measures shall be taken on initial entries and throughout the assessment and recovery operation to limit exposures As Low As Reasonable Achievable (ALARA) in accordance to SQN EPIP-1 5, Emergency Exposure Guidelines.
F. The State of Tennessee has the authority for actions taken offsite however, TVA will serve as an important source of technical and analytical assistance for the State in offsite monitoring and sampling. The Senior Vice President, Nuclear Operations, or his designee will serve as the State's contact for coordination of TVA's efforts in offsite monitoring, sampling and recovery.
PAGE 5 OF 11 REVISION 5
SEQUOYAH TERMINATION AND RECOVERY EPIP-1 6 3.3 Local Recovery Center (LRC)
A. The purpose of the LRC, located at the Sequoyah Training Center (STC), is to provide a nearsite facility for TVA recovery management as well as NRC emergency response personnel and other emergency and/or recovery personnel.
B. The LRC provides adequate space for TVA and others who may locate there to support the site should additional office space near the site become necessary during the recovery phase.
C. The LRC will provide dedicated space for NRC personnel containing adequate supplies, communication, and data necessary for them to carry out appropriate functions.
See NP-REP, Appendix B for description.
3.4 Radiation Dose Management A. Radiological Control (RADCON) personnel will provide monitoring services and dosimetry and prescribe the protective equipment to be used during the recovery of personnel or equipment.
B. Before entry to the affected area is attempted, RADCON will estimate airborne and direct radiation levels in the recovery area. From the information obtained, respiratory protection and occupancy times will be established.
C. RADCON personnel will accompany the recovery personnel on the initial entry to confirm that the airborne radioactivity and radiation levels are as expected.
D. Dose for recovery personnel will be kept within the limits described in EPIP-15, and NP-REP. Respiratory protection factors given in EPIP-15 may be used in determining appropriate respiratory protection for the entry team.
E. TLD badges worn by recovery personnel will be processed by TVA. Process time for a badge would be approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
F. Although an emergency situation transcends the normal requirements of limiting exposure, there are suggested levels in NP-REP and EPIP-1 5 for exposure to be accepted in emergencies. However, every reasonable effort to minimize exposure to ALARA would be made, even in emergencies.
PAGE 6 OF 11 REVISION 5
SEQUOYAH TERMINATION AND RECOVERY EPIP-16 4.0 RECORD 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 7 OF 11 REVISION 5
APPENDIX A Page 1 of 2 TERMINATION GUIDELINES
- 1. ENSURE THE STABILITY OF THE REACTOR SHUTDOWN CONDITION, I.E. D YES SUCCESSFUL PROGRESS TOWARD A COLD SHUTDOWN CONDITION. NO COMMENTS:
- 2. ENSURE THE INTEGRITY OF THE REACTOR CONTAINMENT BUILDING. D YES ONO COMMENTS: aN/A
- 3. ENSURE THE OPERABILITY OF THE ENGINEERED SAFETY SYSTEMS AND D YES DECONTAMINATION FACILITIES. N/OA COMMENTS:
- 4. ENSURE THE AVAILABILITY AND OPERABILITY OF A HEAT SINK. NO Y
COMMENTS: NA
- 5. ENSURE THE INTEGRITY OF POWER SUPPLIES AND ELECTRICAL EQUIPMENT. D YES ONO COMMENTS: ON/A
- 6. ENSURE THE OPERABILITY AND INTEGRITY OF INSTRUMENTATION INCLUDING E YES RADIATION MONITORING EQUIPMENT AND ANY PORTABLE EQUIPMENT THAT D NO MAY HAVE BEEN ASSIGNED DURING THE EMERGENCY. NIA COMMENTS:
- 7. ENSURE THE AVAILABILITY OF TRAINED PERSONNEL AND SUPPORT D YES SERVICES. N/OA COMMENTS:
Continued on next page.
PAGE 8 OF 11 REVISION 5
APPENDIX A Page 2 of 2 TERMINATION GUIDELINES
- 8. ENSURE THAT ANY RADIOLOGICAL EFFLUENT RELEASES ARE UNDER ED YES CONTROL. NO COMMENTS:
- 9. COORDINATE THE TERMINATION OF THE EVENT WITH THE CECC DIRECTOR, a YES TECHNICAL SUPPORT AND OPERATIONS. NO COMMENTS:
- 10. COORDINATE WITH SON RADIOLOGICAL CONTROL OR CHEMISTRY MANAGER D YES SPECIFICS REGARDING THE USE OR NEED FOR POST ACCIDENT SAMPLING. NO COMMENTS:
- 11. CONTACT CECC DIRECTOR AND MAKE SURE STATE IS ABLE TO PERFORM a YES THEIR FUNCTIONS. aNO OlN/A COMMENTS:
- 12. ENSURE THAT THE CECC DIRECTOR HAS INFORMED THE NRC AND THE 0 YES AFECTED STATE AGENCIES THE DECISION TO TERMINATE THE EMERGENCY. NO AND THAT HE/SHE HAS ANNOUNCED THAT THE EMERGENCY HAS NA TERMINATED AND THE RECOVERY PHRASE IS TO BE INITIATED.
COMMENTS:
TIME_
Site Emergency Director (Signature) DateI I FORWARD TO EMERGENCY PREPAREDNESS MANAGER, OPS 41-SON PAGE 9 OF 11 REVISION 5
SEQUOYAH TERMINATION AND RECOVERY EPIP-1 6 APPENDIX B Page 1 of 1 RECOVERY GUIDELINES
- 1. ENSURE THAT A DETAILED SEQUENCE OF EVENTS IS RECONSTRUCTED El YNEOS COMMENTS: Q NIA
- 2. ENSURE THAT THERE IS A RECONSTRUCTION OF OPERATION'S ACTIVITIES El YES DURING THE EVENT (I.E., SYSTEM ALIGNMENTS AND EQUIPMENT NO CONFIGURATIONS). a WA COMMENTS:
- 3. ENSURE THAT A RECOVERY ORGANIZATION IS ESTABLISHED AND THAT El YES DIRECTION AND CONTROL ARE PROVIDED. SEE APPENDIX C FOR NO ORGANIZATION STRUCTURE. NA COMMENTS:
- 4. COORDINATE ASSESSMENT OF CURRENT CONDITIONS AND PLANNED El YES RECOVERY ACTIVITIES FOR TECHNICAL SPECIFICATION IMPACT. El N/A COMMENTS:
- 5. ENSURE A RECOVERY PLAN INCLUDES WRITTEN PROCEDURES FOR ALL El YES MAJOR POST INCIDENT RECOVERY MEASURES. THESE PROCEDURES MAY El NO INCLUDE BUT ARE NOT LIMITED TO THE FOLLOWING: ONIA
- FIRST REACTOR BUILDING ENTRY
- FIRST CONTAINMENT BUILDING ENTRY
- DAMAGE EVALUATION
- DECONTAMINATION
- DISASSEMBLY
- REPAIR
- DISPOSAL
- TEST AND STARTUP OF RESTORED FACILITIES COMMENTS:
- 4. ENSURE THAT STATION RECOVERY ACTIVITIES ARE CONDUCTED IN D YES ACCORDANCE THE RADIATION EXPOSURE LIMITS OF 10 CFR 20 AND SQN o N/A EPIP-1 5.
COMMENTS:
TIME Siee Emergency Director (Signature) Date I /
FORWARD TO EMERGENCY PREPAREDNESS MANAGER, OPS 41-SQN PAGE 10 OF 11 REVISION 5
SEQUOYAH TERMINATION AND RECOVERY EPIP-16 d~ ~~~~PP1 APPENDIX C Page 1 of 1 TVA RECOVERY ORGANIZATION Senior Vice President, Nuclear Operations Site CECC Public Vice President, Manager Manager Vic President Information Engineering and Nuclear Nuclear Manager Technical Services Assurance Security Aiant Administrative Manager Support Group I
Manager Chief Manager, Radiological and Engineer Nuclear Chemistry Services Fuels Manager Manager, Emergency Preparedness Nuclear Licensing For position responsibilities refer to the Radiological Emergency Plan, Section 13.2.
PAGE 11 OF R O 5 REVISION