ML20072A125
| ML20072A125 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/07/1983 |
| From: | Murray T TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20072A116 | List: |
| References | |
| EI-1300.07.0, NUDOCS 8306090375 | |
| Download: ML20072A125 (12) | |
Text
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EI 1300.07.0 Davis-Besse Nuclear Power Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.07 Technical Support Center Activation
- Record of Approval and Changes Prepared by C. J. Reed '5/30/80 Date Submitted by C. E. Wells 6/13/80 Section Head Date Recommended by [Me# _ b/b
., SE Chairfan D'a te QA Approved /f./
Quality Assurance Manager Date ,
Approved.by D /O StationSuperintenden{ Date '
No. Recommendation Date Approved Date Approved Date
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1 EI 1300.07.2
- 1. PURPOSE To outline the personnel required for activation of the Technical Support Center (TSC) and their responsibilities and actions during an emergency at Davis-Besse Nuclear Power Station.
< 2. SCOPE Describe the actions of personnel assigned to the TSC when the the need for its activation has been determined.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Davis-Besse Nuclear Power Station Emergency Plan Telephone Directory 3.3 Station Response to Emergencies EI 1300.00 3.4 Unusual Event EI 1300.02 3.5 Alert EI 1300.03 3.6 Site Emergency EI 1300.04 1
3.7 General Emergency EI 1300.05 3.8 Administrative Controls EI 1300.12
- 4. DEFINITION 4.1 Technical Support Center (TSC) - An area onsite in close proximity to the Control Room which has the capability to display and
! transmit plant status information to the individuals who are 1- knowledgeable of and responsible for engineering and management support of reactor operations in the event of an emergency situation.
- 5. ACTIONS 2 5.1 The Technical Support Center is located at the Davis-Besse site, along Ohio State Route #2, in the Davis-Besse Administra-tion Building. The primary function of the TSC is to house and support an organization that provides management and technical assistance to the Station operations personnel during emergency conditions and to prevent or mitigate the consequences of abnormal plant conditions. The TSC provides direct voice and data communication with the Control Room and serves as a primary I
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2 EI 1300.07.2 i
2 communications contact with the offsite emergency organization of Toledo Edison. Visual observation of the Control Room will be available through closed-circuit television (CCTV). The TSC also contains the DADS to enable the TSC staff to acquire-i plant data and information necessary for technical evaluations needed to handle emergency conditions and recovery operations. l Two communication lines to the NRC are available for direct communication to the NRC Health Physics Network and Emergency j Notification System.
The TSC contains werk space for up to 25 people, including a main work area for 15 people and 3 conference areas, one of which will accommodate 8 people.
2 5.2 The TSC shall be activated at the Alert Emergency Classifi-cation level.
l 5.3 The first Station management individual to arrive at the TSC shall notify the Control Room that the TSC is manned.
5.4 Station Operations Manager 5.4.1 The primary Station Operations Manager is the Station Superintendent.
574.2 The alternate Station Operations Manager is the Assistant 2 Station Superintendent, Operations.
5.4.3 The Station Operations Manager is responsible for
. assuring the activation of the TSC.
5.4.4 The Station Operations Manager should proceed to the TSC and, if NOT previously performed, notify the Control Room that the TSC is maaned.
- 5.4.5 The Station Operations Manager should assure the following individuals arrive at the TSC
- a. Nuclear Engineering Manager
- b. Technical data communicator
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- c. Technical Engineer
- d. Plant Instrumentation and Control Systems Engineer
' e. Plant Nuclear Systems Engineer 5.4.6 The Station Operations Manager may establish the 4 9 I .
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3 EI 1300.07.3 following telephone communications loops as needed per the DBNPS Emergency Plan Telephone Directory:
- a. Technical Data Loop
- b. Technical Management Loop
- c. Policy Management Loop
- d. Public Relations Loop NOTE: If personnel are required as communicators, requests should be directed to the Operations Support Center.
5.4.7 The Station Operations Manager should assign an indi-vidual(s) to distribute applicable emergency equipment 3 listed in Attachment 1, (ie. log book, telephone books, and calculators).
5.4.8 Upon arrival, the Onsite Assessment Manager will assume control of the TSC from the Station Operations Manager.
5.5 Onsite Assessment Manager 5.5.1 The primary Onsite Assessment Manager is the Nuclear Engineering Manger.
5.5.2 The alternate Onsite Assessment Manager is the Plant Nuclear Systems Engineer.
5.5.3 The Onsite Assessment Manager, upon being informed that an Alert level emergency exist, shall proceed to the Technical Support Center (TSC).
5.5.4 The Onsite Assessment Manager's responsibilities and duties include, but are NOT limited to:
- a. Directing the engineering assessment activities of the TSC.
- b. Coordinating the engineering assessment activities of engineering support personnel from the NSSS vendor and the Architect Engineer.
- c. Ensuring that adequate mechanical, electrical, instrumentation and control, and technical engineers are available to perform engineering assessment, as required.
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- d. Ensuring that adequate support personnel are available to assist in records disposition, updating status board, and providing communica-tions to the Control Room and Nuclear Regulatory Commission, as necessary.
- e. Reporting to the Station Operations Manager and appraising him of engineering assessment activities, equipment operation problems and any alterations in the normal lineup or operation of plant systems.
5.6 Technical Engineer
, 5.6.1 The primary technical engineering individual is the i
Technical Engineer.
5.6.2 The alternate technical engineering indisidual is the Nuclear Performance Engineer.
5.6.3 The Technical Engineer shall assist in coordinat-ing and performing plant assessment activities.
5.6.4 The Technical Engineer shall, as necessary, assure that radiological controls are in place such as:
- a. TSC monitored for airborne activity by opera-tion of a portable air activity monitor.
- b. A high/ low survey instrument is utilized by personnel leaving the TSC for entry into the plant.
- c. Stepoff pads and contamination survey instru-ments are provided at the entrance to the TSC from the plant when required.
5.6.5 The Technical Engineer shall assure that personnel assembled in the TSC are briefed on conditions and monitoring methods in place while the TSC is activated.
+ 5.7 Radeon Operations Manager 5.7.1 The Radeon Operations Manager is the Chemist and Health Physicist.
4 5.7.2 The alternate Radeon Operations Manager is the Chemistry and Radiochemistry Supervisor or the Health Physics l
Supervisor.
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5 EI 1300.07.2 5.7.3 The Radeon Operations Manager directs and coordinates
~t he radioactive waste and radiological controls aspects of Emergency Operations and. keeps the Plant Operations Manager informed of radwaste and radcon activities pursuant to the emergency.
5.7.4 The Radeon Operations Manager is responsible for coordinating the activities of the Health Physics Monitoring Room portion of the Operations Support Center, however he may do this from his office located in the Technical Support Center. He is also responsible for relaying health physics information over the NRC Health Physics Network phone which is located there.
5.7.5 The Radeon Operations Manager shall supervise the onsite radiation surveys and survey results analysis.
5.8 Plant Staff 2 5.8.1 Plant Staff, such as the operations engineering staff, clerical support, etc., who are NOT assigned to other emergency functions, shall (if-in protected-area) report to the Operations Support Center and be directed to the TSC as needed.
5.8.2 The Technical Engineering staff who are not assigned other emergency functions, shall report directly to the TSC.
5.8.3 The Plant Staff shall assist in accident assessment, as required.
5.9 Technical Support Center Activity i 5.9.1 Communications with the Control Room, Emergency Support Center, Operations Support Center, Emerg-ency Control Center, and the NRC will be established as specified by the Onsite Assessment Manager or the Station Operations Manager.
2 a. The Data Acquisition and Display System (DADS) terminals in the TSC will provide sufficient I
station information and data communication for
! personnel to evaluate and diagnose station l conditions and activities so as to conduct emergency operations in an orderly manner. ,
- b. The DADS provide data communication between the ECC, TSC, Control Room and Emergency Support Center.
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6 EI 1300.07.4
- c. The DADS can monitor plant transients during and following most events expected to occur during the life of the station.
5.9.2 The condition of the reactor and essential safety-related systems shall be assessed and steps taken to assure protection of Station personnel and the public.
5.9.3 Analysis of plant conditions shall be performed to determine reactor core status. Containment Radiation Plots in Attachment 2 provide the relationship between containment radiation levels and the time after plant shutdown for various amounts of fuel inventory released '
4 into containment. This information can be used to declare the applicable emergency classification.
5.9.4 Directives issued to the Control Room shall be assessed for potential adverse consequences before issuance -
this includes all offsite directives from government or company management organizations.
- a. Directives to the Control Room should be done 4
verbally as long as there is mutual agreement to all parties that the correct action is being taken. .
- b. If a disagreement occurs between the Control Room and the TSC, a written directive from the
- TSC should be forwarded to the Control Room signed by the Onsite Assessment Manager or Station Operations Manager.
5.9.5 Contact shall be made and support requested as required from the following organizations:
- a. Babcock and Wilcox
- b. Bechtel
- c. Nuclear Safety Analysis Center (NOTEPAD) 5.9.6 A record of activities of the TSC shall be maintained to the best ability of personnel present. Record i
disposition shall be in accordance with EI 1300.12,
' Administrative Controls.
5.9.7 The decision to deactivate the TSC shall be made by 3
joint concurrence of the Onsite Assessment Manager, Station Operations Manager, Shift Supervisor and other key plant personnel once accident recovery has reached a point where continuous technical assessment and advisory functions are no longer necessary to mitigate the consequences of plant conditions.
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7 EI 1300.07.3 5.10 Procedure for Activation of the Alternate TSC 5.10.1 The Onsite Assessment Manager will direct the activation of an alternate TSC if the normal TSC becomes uninhabitable for any reason.
5.10.2 No more than three (3) persons assigned to technical support will be dispatched to the Control Room. The 3 balance of the technical support staff (including vendor, TED and NRC personnel) will be located at a suitable position as close to the Control Room as
. possible. Communications will be established by telephone, messenger, telecopier, etc. between technical support personnel and the Control Room. Also, communica-tions will be established at least by telephone or messenger between the relocated TSC and the ECC.
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. o 8 EI 1300.07.3 Technical Support Center Equipment List Attachment 1 Location Item Quantity Log Book i ea.
E-Plan, Supporting & Implementing Proc. I ea.
State of Ohio Emergency Plan 1 ea.
FSAR 1 ea.
Admin. Manual (Vol 1, 2, 3) 1 ea.
Tech. Specs. 1 ea.
Rad. Prot. Manual 1 ea.
Drawing Change Notice (DCN) Log I ea.
TI-59 Calculator 2 ea.
Emergency Plan Telephone Directories 5 ea.
Telephone Headsets 4 ea.
TI-55 Calculator 7 ea.
Station Procedures (as Designated by the Tech. Engineer) i List of Drawings In TSC Library Electrical Mechanical ISIM ISID -
E-1 thru E-65B M-001 thru M-196 203A 233D 241B 12501-ISID-003 E-80 203B 233E 241C 006B E-81 M-580A - C 203F 233F 241D 007 E-82 M-581A - G 203H 233G 241E 010B E-101 M-589 203J 234A 241F 015 E-102 M-592 206F 234B 241G 017 019 (
E-103 206G 234C 241H E-104 M-101FW 207A 234D 241L 026A M-102FW 207B 235A 246A 027A M-103FW 207C 235B PS/PSU 027B M-104FW 210E 236A 028B M-105EW 210H 236B 029A M-106FW 220B 236C 029B M-107FW 229 236D 030 M-108FW 230A 236D 031 230A 236E 033
! 231A 236H 034 l 231B 240A 035 231D 240B 036
! 233A 240C 040A 233B 240D 040B 233C 241A 041
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l ISID - In Service Inspection Diagram ISIM - In Service Inspection Isometric
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5 h 9 I I I 20 25 30 O 2 t. 6 8 to 15 Based on a report by J. Stewart Bland, P.O. Box 4154, Annapolis, yD 21403 dated January, 1983.
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DAVIS-BESSE PIVISION COVER SHEET April 15. 1983 f*#h DATE TO: 'ALN_ & (LA 'LL u Wh)V n .
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FROM: EMERGENCY PLANNING & PREPAREDNESS SLTV.
SUBJECT:
Davis-Besse EMERGENCY PLAN IMPLEMENTING PROCEDURES Manual Changes This letter transmits additions and revisions to the Davis-Besse EMERGENCY PLAN IMPLEMENTING PROCEDURES Manual. Control Copy hC4, -
Instructions for the material are as follows: . .,
REMOVE AND RETURN INSERT Revision Index, Rev. 27 Revision Index, Rev. 28 EI 1300.07.3 EI 1300.07.4 ',
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Addressee Signature 7 l
RETURN TO THE OFFICE MANACER - STOP 43050 s
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THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES REVISION INDEX PAGE REVISION PROCEDURES REVISION TEMPORARY MODIFICATIONS 1 0 EI 1300.00 4 EI 1300.01 5
. EI 1300.02 3 T-6938 3- EI 1300.03 3
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