ML20129F116
| ML20129F116 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/21/1985 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20129F108 | List: |
| References | |
| 0502D, 502D, PROC-850621-01, NUDOCS 8507170234 | |
| Download: ML20129F116 (100) | |
Text
{{#Wiki_filter:. - . . ._. . . . ___ _ - - _ . . - i PGandE Letter No.: DCL-85-222 ENCLOSURE 1 Updates Included In This Submittal . DIABLO CANYON EMERGENCY PLAN IMPLEMENTING PROCEDURES i Volume 3A Updated Table of Contents EP G-2, Revision 7 EP G-2S1 , Revision 2 Volume 38 Updated Table of Contents EP RB-14, Revision 2 e e e 1 0502d/0005K 8507170234 850621 PDR ADOCK 05000275 F , PM
PGandE Letter No.: DCL-85-222 ENCLOSURE 2 Location of Proprietary Information Procedure: EP G-2S1 -- Attadment, Emergency Organization Call List (Form 69-10297), p. 32 of 32 0502d/0005K
l *
- PGandE Letter No.: DCL-85-222 1
1 .
- ENCLOSURE 3 I i
Updates to Diablo Canyon 1 Emergency Plan Implementing Procedures b l l 0502d/0005K
. . PGandE Letter No.: DCL-85-222 i l
CURRENT EMERGENCY PLAN IMPLEMENTING PROCEDURES , TABLE OF CONTENTS ! Volume 3A TITLE REV E-0 Reactor Trip or Safety Injection 0 E-0.1 Reactor Trip Response 0 E-0.2 Natural Circulation Cooldown 0 E-0.3 Natural Circulation Cooldown with Steam Void in Vessel 0 (with RVLIS) E-0-4 Natural Circulation Cooldown with Steam Void in Vessel 0 (Without RVLIS) E-1 Loss of Reactor or Secondary Coolant 0 E-1.1 SI Termination - 0 E-1.2 Post LOCA Cooldown and Depressurization 0 E-1.3 Transfer to Cold Leg Recirculation 0 E-1.4 Transfer to Hot Leg Recirculation 0 E-2 . Faul ted Steam Generator Isolation 0 E-2.1 Alternate Auxiliary Feedwater Supplies 0 E-3 Steam Generator Tube Rupture 0 ECA-0.0 Loss of All AC Power .0 ECA-0.1 Loss of All AC Power Recovery W1thout SI Required 0 ECA-0.2 Loss of All AC Power Recovery with SI Required 0 E CA-0. 3 Restore Vital Bus 0 ECA-1.1 Loss of Emergency Coolant Recirculation 0 ECA-1.2 LOCA Outside Containment 0 ECA-2.1 Uhcontrolled Depressurization of All Steam Generators 0 ECA-3.1 SGTR With Loss of Reactor Coolant-Subcooled Recovery Desire 0 ECA-3.2 SGTR with Loss of Reactor Coolant - Saturated Recovery Desired 0 ECA-3.3 SGTR Without Pressurizer Pressure Control 0 F-0 Critical Safety Function Status Trees 0 FR-S.1 Response to Nuclear Power Generation /ATWS 0 FR-S.2 Response to Loss of Core Shutdown 0 FR-C.1 Response to Inadequate Core Cooling 0 FR-C. 2 Response to Degraded Core Cooling 0 FR-C.3 Response to Saturated Core Conditions 0 FR-H.1 Response to Loss of Secondary Heat Sink 0 FR-H.2 Response to Steam Generator Overpressure 0 FR-H.3 Response to Steam Generator High Level 0 FR-H.4 Response to Loss of Normal Steam Release Capabilities 0 0502d/0005K 06/21/85
!N75 CF
TABLE OF CONTENTS (Con tinued) FR-H.S Response to Steam Generator Low Level 0 FR-P.1 Response to Imminent Pressurized Thermal Shock Condition 0 FR-P.2 Response to Anticipated Pressurized Thermal Shock Condition 0 FR -Z.1 Response to High Containment Pressure 0 FR-Z.2 Response to Containment Flooding 0 FR-Z. 3 Response to High Containment Radiation Level 0 FR-I.1 Response to High Pressurizer Level 0 FR-I. 2 Response to Low Pressurizer Level 0 Fr-I.3 Response to Voids in Reactor Vessel 0 R-1 Personnel Injury or Illness (Radiologically Related) 15 and/or Overexposure R-2 Release of Airborne Radioactive Materials 5 R-3 Release of Radioactive Liquids 4 R-4 High Radiation (In Plant) 3 R-5 Radioactive Liquid Spill 3 R-6 Radiological Fire 8 R-7 Offsite Transportation Accidents 5 M-1 Employee Injury or Illness (Nonradiological) . 13 M-2 Nonemployee Injury or Illness (Third Party) 11 M-3 Chlorine Release 5 M-4 Earthquake 8 M-5 Tsunami Warning 5 M-6 Nonradiological Fire 10 M-7 Oil Spil1 Isolation and C1ean Up Procedure 7 M-8 Containment Emergency Personnel Hatch 0, M-9 Hazardous Waste Management Contingency P1an 2 M-10 Fire Protection of Safe Shutdown Equipment, Unit 1 3 M-10 Fire Protection of Safe Shutdown Equipment, Unit 2 3 G-1 Accident C1assification and Emergency P1an Activation 5 G-2 Establishment of the On-Site Emergency Organization 7 G-2 S1 Emergency Organization Call List Form 69-10297 2 G-3 Notification of Off-Site Organizations 5 G-4 Personnel Accountability and Asseirbly 6 G-5 Evacuation of Nonessential Site Personnel 2 06/21/E 0502d/0005K
J
~, m NUMBER EP G-2 y #,US Pacific Gas and Electric Company REVISION 7 -
DEPARTMENT OF NUCLEAR PLANT OPERATIONS DATE 2/26/85 DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 PAGE 1 0F 22-EMERGENCY PROCEDURE ESTABLISHMENT OF THE ON-SITE EMERGENCY TITLE ORGANIZATION ik.;'OT~'A;;7 APPROVED Yd M3"b IO
' PLANT U NAGER ,)
DATE SAFETY SCOPE This procedure describes the responsibilities of the positions in the On-site Emergency Organization and the actions required by plant personnel for establishing the On-site Emergency Organization. This procedure and changes thereto require PSRC review. GENERAL
- 1. The transition from a nomal operating organization to an On-site Emergency Organization involves the following three basic steps:
- a. Filling appropriate On-site Emergency Organization positions on an interim basis with personnel who are immediately available on-site at the time of the emergency. See Figure 1 for the description of the " Suggested Interim Emergency Organization."
- b. Notifying plant personnel off-site and on-site that their assistance is required (refer to EP G-2 Supplement I for instructions).
I c. Filling positions in the long-tem emergency organization, l as described in Figure 2 "Long-Tem Emergency Organization," with appropriate plant personnel as they arrive at the Control Room, Operational Support Center, Technical Support Center, or the Emergency Operations Facility.
- 2. Plant personnel are assigned to the long-tem emergency organization positions on an interim or long-term basis and are ranked in order of preference in Supplement 1. " Emergency Organization Call List." All position-holders are responsible -
for performing the duties of their position as described in Table
- 1. "On-site Emergency Organizations' Respcnsibilities," or as specified by the Site Emergency Coordinator.
DC0075 1Y!II
DIA8LO CANYON POWER Pt. ANT UNIT NCHS) 1 AND 2 h0N DATE 2/26/85 PAGE 2 0F 22 TITLE. ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION All position holders are responsible for performing the duties of their position until 1) duly relieved with permission received from the Site Emergency Coordinator, or 2) the Site Emergency Coordinator determines that the emergency organization position
- is no longer required. Fom 69-9370, " Site Emergency Organization Assignments" may be used to record emergency assignments and shift rotations.
t
- 3. The Shift Foreman shall remain in the Control room where he is responsible for overall comand and control of the emergency. He shall assume the position of the interim Site Emergency Coordinator. He shall not become totally involved in any single operation but shall maintain a broad perspective of operational conditions affecting the safety of the plant, in compliance with Nuclear Plant Administrative Procedure, NPAP A-102.
4 When an emergency is declared and notification of plant staff and offsite response organizations is in process, incoming phone calls on the plant emergency number shall be answered, and the plant emergency number shall be provided to offsite personnel needing to contact the plant. Calls on the nomal plant number s. ' will be answered to the extent possible without interfering with the emergency response. ~
- 5. All notifications shall be recorded. A hard copy of all transactions will be generated by the Rapid Alert Notification System data terminal. Manual notifications are nomally recorded on Form 69-10297 " Emergency Organization Call List." Fom 69-9221, " Emergency Notification Record" or a log is used to record incoming calls or calls to persons not on Fom 69-10297.
- 6. All records generated by the utilization of this procedure for an exercise or emergency shall be forwarded the next working day to the Assistant Plant Manager, Support Services, for review and retention,
- a. Records generated from exercises will be categorized as non permanent and retained for a minimum of five years.
- b. Records generated from actual emergency events will be categorized as lifetime and placed into lifetime storage in accordance with procedure " Requirements for Retention and Extended Storage of Operation Phase Activity Records (AP E-151)."
DC0075 2VIII
DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/26/85 PAGE 3 0F. 22 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION INITIATING CONDITIONS Notification and establishment of the On-site Emergency Organization shall be initiated by the Shift Foreman when he declares an Unusual Event, Alert, Site Area or General Emergency in accordance with , Emergency Procedure G-1, " Accident Classification and Emergency Plan Activation." IMMEDIATE ACTIONS
- 1. The Shift Foreman shall assume the position of the interim Site Emergency Coordinator, assess the situation, and appoint members of the on-site operating staff to assume the positions shown in Figure 1 " Interim Site Emergency Organization," as .he deems necessary to terminate or mitigate the emergency.
NOTIFICATIONS The Rapid Alert Notification is the preferred notification method during of f-nomal hours, except for the Unusual Event Classification. It is programed with the same positions, names, and numbers included in Form 69-10297. " Emergency Organization Call List." It can be activated on site by push button control or remotely by telephone. Once the system dials the programed number and the call is answered,' a synthesized human-like voice delivers the appropriate message. The call recipient acknowledges the call by using a response number on the telephone keypad or a device provided for that purpose. If no acknowledgement occurs, the machine continues to call other emergency personnel on the list. A hard copy of all transactions is generated by the Rapid Alert Notification data terminal. Form 69-10297, " Emergency Organization Call List" can be used if sounding the Site Emergency Signal is not desirable, for paging key people and individuals designated "On Call," encoding UHF radio equipped cars, for Unusual Events, or if the Rapid Alert Notification System is inoperable. NOTIFICATION OF AN UNUSUAL EVENT
- 1. The interim Site Emergency Coordinator shall contact, as a minimum, position holders for the long-term emergency organization positions indicated by the Unusual Event Stop Callout Point on the " Emergency Organization Call List" in Supplement 1. Personnel contacted should inform the caller as to whether they will proceed to their emergency response location or remain on standby status.
K)TE: Notify personnel contacted of event termination. DC0075 3VIII
i l oiAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 [0N DATE 2/26/85 PAGE 4 0F 22 Ting ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION l f_ 2. Additional plant personnel may be called out as deemed necessary
. by any of the above personnel.
NOTIFICATION OF AN ALERT, SITE AREA EMERGENCY, OR GENERAL EMERGENCY l 1. The interim Site Emergency Coordinator shall contact l position-holders to fill positions in the long-tenn emergency ! organization using the Rapid Alert Notification System or if unable, per Fonn 69-10297, " Emergency Organization Call List." NOTE: During normal working hours, sounding of the Site Emergency Signal may be used as a means of establishing the emergency organization. During off-nonnal hours or if sounding the Site Emergency Signal is not desirable, the interim Site Emergency Coordinator should appoint a _ Liaison Assistant who assists the Liaison Coordinator.and notifies plant personnel per Supplement 1 to this procedure. The Liaison Assistant may perform the callout from the Control Room area or may be dispatched to the Technical Support Center (TSC) to activate the TSC telephone switchboard to receive incoming emergency calls and complete plant staff notification.
- 2. If long-tenn emergency position holders and support staff are already on station, notify them of the escalation or reduction of the emergency classification. Particular care should be given to notifying personnel at the following locations:
- a. TSC or Control Room (depending on location of the Site Emergency Coordinator)
- b. EOF, and monitoring teams under the control of EOF.
- c. OSC
- d. Security Building
- e. Personnel who may be performing emergency actions in various areas of the plant site (other than at emergency facilities).
- 3. Additional Liaison Assistants may be assigned to assist in notifications or coordinate message dissemination between the Site Emergency Coordinator and the Emergency Liaison Coordinator.
DC0075 4VIII
DIA8LO CANYON POWEQ PLANT UNIT NO(S) 1 AND 2 h0N DATE 2/26/85 . l PAGE 5 0F 22 l TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION
- 4. Support staff called on-site (who are not given a predesignated response location) should be directed to report to the Security Building lunchroom (Readyroom). Upon arrival, they will call the TSC or Control Room to receive further direction.
SUPPORTING PROCEDURES , EP G-1, " Accident Classification and Emergency Plant Activation" EP G-2, Supplement 1 EP G-3, " Notification of Off-site Organizations" EP G-4, " Personnel Assembly and Accountability" AP E-15', " Requirements for Retention And Extended Storage Of Operation Phase Activity Records" APA3, Supplement 1,"OnCallSystemandPersobnelAvailability" NPAP A-102, " General Authorities And Responsibilities Of The Shift Foreman" TABLES
- 1. On-site Emergency Operating Organization - Responsibilities FIGURES
- 1. Typical On-Shift Emergency Organization And Assignments
- 2. Long-term Emergency Organization
- 3. Interim EOF Organization ATTACHMENTS
- 1. Form 69-9370, " Site Emergency Organization Assignments."
- 2. Fonn 69-9221. " Emergency Notification Record."
DC0075 5VIII
o . ciAaLO CANYON POWER PLANT UNIT NO{S) 1 AND 2 ON DATE 2/26/85 PAGE 6 0F 22 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION TABLE 1 ON-SITE EMERGENCY ORGANIZATION RESPONSIBILITIES A. Site Emergency Coordinator
- 1. Prior to being relieved by the Site Emergency Coordinator, the Interim Site Emergency Coordinator is responsible for the following in addition to the duties and responsibilities of the Shift Foreman:
*a. Make the initial evaluation and classification of the situation.
*b. Assign plant staff personnel to positions in the Site Emergency Organization.
- c. Notify, or direct the notification of:
- 1) Plant staff personnel
- 2) Company off-site emergency organizations
- 3) Local noncompany emergency support groups s;
- 4) San Luis Obispo County, California Office of Emergency Services and the Nuclear Regulatory Comission
*d. Authorize the sounding of the site emergency signal.
*e. Authorize the evacuation of the plant site and specify the appropriate evacuation route.
*f. Authorize overtime and other expenses associated with establishing and maintaining an appropriate site emergency organization.
*g. Provide direction for all emergency response operations ,
performed by Company personnel in the San Luis Obispo 1 County Area. <
*h. Maintain liaison with off-site emergency support groups.
*i. Make protective action recomendations regarding evacuation, sheltering, confiscation of food, or other emergency measures to local government agencies. )
- Responsibility that may not be delegated.
DC0075 6VIII
DIABLO CANYON POWEQ PLANT UNIT NO(S) ' 1 AND 2 h ON
- DATE 2/26/85 I PAGE 7 0F 22 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION
*j. Authorize any extraordinary emergency measures, such as the use of company emergency personnel exposure limits.
- 2. The Site Emergency Coordinator will establish the emergency response organization in the TSC and then relieve the interim ,
Site Emergency Coordinator (normally the Shift Foreman). He will ' assume the following duties.
- a. Prior to the time that the corporate Recovery Manager assumes his position at the Emergency Operation Facility, the Site Emergency Coordinator is responsible to:
*1) Provide direction for all emergency response operations performed by Company personnel in the San Luis Obispo County Area.
*2) Authorize any recomendations of the Company regardi,ng evacuation, confiscation of food, or other emergency measures, to noncompany emergency support groups.
*3) Authorize changes in the Emergency Action Level
. classification to off-site authorities.
*4) Authorize any extraordinary emergency measures, such as the use of company emergency personnel exposure limits.
- 5) Request assistance as necessary for on-site or off-site radiation monitoring from federal agencies, either through the county / state emergency response organization once established, or directly,
- b. Coordinate and direct all on-site activities.
- c. Maintain liaison with off-site emergency support groups providing on-site assistance and support the corporate Recovery Manager in the development of a coordinated recovery action plan for on-site.
- d. Recomend changes in Emergency Action Level Classification to the Recovery Manager.
- Responsibility that may not be delegated. i DC0075 7VIII
o ,- oue.O CANYON POWER PLANT UNIT NO 5) 1 AND 2 ON DATE 2/26/85 PAGE 8 0F 22 m LE. ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION
- e. Manage TSC Operations. This includes collecting and l-analyzing the technical information necessary for assessment of plant operational aspects, providing technical counsel in support of the Control Room (CR), assessment of radiological release potential, determination of actual or potential release rates,on-site exposure monitoring and contamination control, repair of plant components or systents as required by the emergency and/or consequences, and on-site personnel accountability.
- f. Provide management direction to the Control Room (CR) through the Emergency Operations Coordinator.
- g. Provide management direction to the Operational Support Center (OSC) through the Emergency Maintenance Coordinator.
- h. Assign plant staff personnel to positions in the On-site Emergency Organization as appropriate.
*i. Authorize overtime and other expenses associated with maintaining an appropriate On-site Emergency Organization ,
throughout the recovery period. J. Establish and maintain on-site personnel accountability. *
*k. Authorize the evacuation of the plant site and specify the appropriate evacuation route.
*l. Obtain the Recovery Managers approval prior to authorizing any extraordinary emergency measures such as the use of Company emergency personnel exposure limits.
B. Emergency Liaison Coordinator l l This position (both interim and permanent) provides control of y i verbal and written communications to and from the site with the l following duties and responsibilities: l 1. Handle communications to and from the site and between site emergency response groups.
- 2. As directed by the Site Emergency Coordinator, notify plant
! staff and other affected individuals and organizations of the emergency and their assignments. L
- Responsibility that may not be delegated.
DC0075 8VIII
0iAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h0N , DATE 2/26/85 PAGE 9 0F 22 TIT m ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION
- 3. Maintain contact with on-site and off-site emergency support 1 groups, regulatory agencies, and monitoring teams and i transmit instructions and infonnation to and from the Site Emergency Coordinator.
- 4. Maintain records of incoming and outgoing messages. Operate ,
communications equipment and develop message content as required to support the above.
- 5. Provide general assistance to the Site Emergency Coordinator.
C. Liaison Assistant (Interim and permanent) )
- 1. Assist the Emergency Liaison Coordinator in communications and recording messages and carrying out his assigned duties.
D. Emergency Maintenance Coordinator This position provides coordination of maintenance, repair and material deployment in response to the emergency situation with the following duties and responsibilities:
- 1. At the direction of the Site Emergency Coordinator fabricate and set up any special equipment necessary for recovery operations.
- 2. Provide management direction to the Operational Support .
Center Supervisor and maintenance organizations.
- 3. Coordinate the movement and accountability of support personnel brought to the site.
- 4. Provide general advice and assistance in these matters to I the Site Emergency Coordinator and other evaluations personnel.
E. Maintenance Organizations ! Electrical, mechanical and instrument coordinators are assigned to plan and supervise maintenance, repair or installation of special equipment required to respond or recover from the - emergency at the direction of the Emergency Maintenance Coordinator. These coordinators are generally involved with activities at the OSC. DC0075 9VIII
otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON . DATE 2/26/85 PAGE 10 0F 22 TITLE. ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION Advisors are also assigned, when required, to provide technical . advice in their areas of specialty to the evaluation personnel in the TSC. F. Operational Support Center Supervisor This position provides comunication and coordination of emergency response activities in areas of the plant potentially affected by the emergency situation, with the following duties and responsibilities:
- 1. Determine that personnel entering a potentially hazardous plant area are informed of the plant status, potential hazards in the area, safety and radiation protection provisions, and are appropriately equipped and familiar with the requirements for their work.
- 2. Assists the functional coordinators in assignment of -
personnel to tasks designated by the Emergency Maintenance Coordinator.
- 3. Maintains accountability of personnel dispatched from the ,
OSC, and maintains the capability of comunicating with personnel engaged in operations, maintenance or chemistry and radiation protection emergency response activities.
- 4. Briefs response teams on plant status, and changes in emergency classification or plant conditions.
- 5. Assists the Control Room and TSC in comunicating with response personnel.
- 6. Maintains appropriate records of activities at the OSC.
G. Emergency Evaluations and Recovery Coordinator This position provides overall technical coordination of the plant response activities with the following duties and responsibilities:
- 1. Evaluate the safety consequences of the occurrence and ,
advise the Site Emergency Coordinator accordingly of ; appropriate response actions and on-site and off-site 1 recommended protective measures. l DC0075 10VIII
DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON - DATE 2/26/85 PAGE 11 0F 22 TITLE. ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION
- 2. Advise the Site Emergency Coordinator on technical matters relating to nuclear and radiological safety.
- 3. Provide coordination and supervision of all company support teams operating at or in the vicinity of the site.
- 4. Provide coordination and supervision of all company technical support work as part of the overall recovery program developed by the Site Emergency Coordinator and Recovery Manager.
- 5. Advise the Site Emergency Coordinator of actions and findings of company support groups.
- 6. Assist the Site Emergency Coordinator in determining personnel deployment to emergency support assignments.
- 7. Provide operation and control of emergency data transmission systems, and review and evaluate plant data.
( The interim Emergency Evaluation and Recovery Coordinator is c
'. responsible for the above as applicable to the initial emergency response.
H. Emergency Radiolacical Advisor This position provides overall coordination of radiological aspects of the emergency with the following duties and responsibilities:
- 1. Advise the Site Emergency Coordinator and/or Emergency Evaluations and Recovery Coordinator on matters relating to radiological safety.
- 2. Coordinate and supervise radiological surveys and investigations, both in plant and near site. Work with the Radiological Emergency Recovery Manager in making an overall assessment of radiological conditions.
- 3. Coordinate and supervise all on-site radiological surveys and investigations, and manage the on-site radiation protection program.
DC0075 11VIII l l
F"" DIABLO CANYON POWER PUWT UNIT NO(S) 1 AND 2 ON DATE 2/26/85 PAGE 12 0F 22 j Tmm. ESTABLISHMENT OF THE ON-SITE EMERGEv. ORGANIZATION
- 4. Assist the Emergency Evaluation and Recovery Coordinator in operation and control of radiological emergency data transmission systems, review and evaluation of data from these systems, and development of data and status updates for transmission off-site I. Site Chemistry and Radiation protection Coordinator This position assists the Emergency Radiological Advisor in coordinating on-site radiological protection and chemical and radiological surveys and investigations. These duties include the following:
- 1. Personnel exposure monitoring and record keeping.
l
- 2. Radiological and chemical analysis _ of in-plant samples.
- 3. In-plant surveys and establishment of radiation and/or contamination control area boundaries.
- 4. Determine radiation protection access requirements for entry to controlled areas. '
- 5. Maintain proper records and logs.
; 6. Keep the Emergency Radiological Advisor and/or the Emergency Evaluation and Recovery Coordinator informed of actions and
- findings. Coordinate dispatch of personnel into affected plant areas with the OSC Coordinator.
l J. In-plant Chemistry and Radiation protection Technicians l These personnel perform their normal job functions in chemical , sampling and analysis or radiation protection or provide sample data for radiological or chemical assessment. K. Radiological Data processor (TSC) This position assists the Emergency Radiological Advisor in processing and evaluating radiological data, documenting the - results of such evaluations and comunicating approved results to TSC and EOF personnel. l l DC0075 12VIII
DIABLO CANYON POWER PLANT UNIT NO(S) ~ 1 AND 2 RE ON DATE 2/26/85 PAGE 13 0F 22 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION L. EARS Operator - TSC This position assists the Emergency Radiological Advisor in . developing radiological data using computerized models. M. Emergency Radiological Monitoring Teams . Emergency radiological teams will be 2-man teams established for near site and off-site monitoring in the event of a radiological release emergency. They have the following duties and responsibilities: On-Site Team (s):
- 1. Perform radiation surveys in and around the plant site and obtain appropriate samples for analysis.
- 2. Maintain comunications with the Control Room or Technica'l Support Center for reporting monitoring results and maintaining cognizance of the emergency situation.
. 3. Establish controlled access areas to contain or limit the spread of radioactive contamination, as appropriate.
- 4. Issue personnel protective equipment and clothing. -
- 5. Establish and post radiation and/or contamination area boundaries.
- 6. Monitor personnel and evaluate their exposure, if required.
- 7. Maintain proper records and logs.
- 8. Keep the Emergency Radiological Advisor and/or the Emergency Evaluation and Recovery Coordinator infomed of their actions and findings.
Off-Site Team (s):
- 1. Perform radiation surveys at off-site locations as designated by the Radiological Emergency Recovery Manager and obtain appropriate samples for analysis.
DC0075 13VIII
- O OLA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h0N DATE 2/26/85 PAGE 14 0F. 22 ints. ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION
- 2. Maintain communications with the Emergency Operations Facility and Mobile Environmental Monitoring Laboratory for reporting results and maintaining cognizance of the emergency situation.
- 3. Coordinate monitoring activities and reporting of results with the county personnel assigned to the monitoring team.
- 4. Provide recommendations regarding establishing controlled access areas and determining the boundaries of such areas in cooperation with county personnel assigned to the monitoring team.
- 5. Assist in monitoring personnel and evaluating.their exposure as required. -
- 6. Maintain proper logs and records.
- 7. Keep the Radiological Emergency Recovery Manager informed of their actions and findings.
I N. Emergency Operations Coordinator This position provides senior plant management representation in' the control room.
- 1. Manage Operational Activities.
- 2. Supervise the Shift Foreman in the operational control of the plant.
- 3. Advise the Site Emergency Coordinator on operational matters.
The interim Emergency Operations Coordinator is responsible for item 1 above. O. Emergency Operations Advisor This is a position filled by an individual knowledgeable in operational matters to provide general operational advice and assistance to the Site Emergency Coordinator and other evaluations personnel in the TSC. This position may be assigned other operational duties such as radwaste management as required by the situation. DC0075 14VIII
DiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 - ON DATE 2/26/85 PAGE 15 0F 22 TITLE. ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION P. Shift Foreman This is a position in the nomal operating organization which i fills the emergency position of interim Site Emergency . Coordinator and which reverts back to normal job duties under the ! direction of the Emergency Operations Coordinator when relieved i by the long term Site Emergency Coordinator. ' Q. Operators These are positions in the normal plant organization which . continues to perform plant operational manipulations in the emergency organization when not otherwise assigned. R. Shift Technical Advisor This is a position in the normal operatthg organization which-remains filled throughout the emergency recovery period. The initial function of this individual is to assume the position of . interim Emergency Evaluation and Recovery Coordinator and assist the Shift Foreman in the evaluation of the occurrence, possible consequences, and possible courses of action. In the long term, this position may assist in the Control Room or TSC on plant evaluation or radiological evaluation, as required by the occurrence. S. Fire Brigades These teams are responsible for on-site fire suppression activities. T. Security Liaison This is a position in the TSC, or Control Room, to coordinate security activities in support of the emergency response and to < advise the Site Emergency Coordinator on security matters. U. Evacuation Coordinator This is a temporary position to coordinate evacuation of non-essential personnel from the site if warranted by the situation. It would nomally be assigned to a member of the ' security staff, such as the Security Liaison, but may be assigned to a member of the emergency planning staff. DC0075 15VIII
OLASLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 h ON DATE 2/26/85 PAGE 16 0F 22 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION V. Evacuation Team These are temporary positions consisting of a group leader (the senior person at an assembly area) and an out-of-plant monitoring technician who will accompany the evacuees in the event a site evacuation is necessary. The basic functions of this team are to:
- 1. Assure that the evacuees stay together and take the correct route.
- 2. Assist in personnel accountability at the evacuation off-site assembly area.
- 3. Secure radiation survey equipment and survey personnel and vehicles at the collection area and "arrange for decontamination as required.
W. First-Aid and Medical i The importance of providing prompt first-aid is well recognized. , l First aid training is provided for plant staff personnel and I includes certification for Cardio-pulmonary resuscitation. An onsite medical facility is available during normal working hours to provide basic life support capabilities as well as routine , medical examinations. Emergency safety personnel are E.M.T. certified. Personnel in the immediate area of the injured personnel, or as dispatched by the Site Emergency Coordinator, will provide care until off-site assistance arrives. X. Evaluation Data Processors These positions provide engineering assistance to the Emergency Evaluation and Recovery Coordinator in performing those duties relating to evaluation of plant core /thennal hydraulics, electrical and mechanical data, coordination of technical support work, operation of computer systems and other on-site emergency response activities. I DC0075 16VIII
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DiAsto CANYON POWEQ PLANT UNIT NOCS) 1 AND 2 ON . DATE 2/26/85 PAGE 17 0F 22 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION Y. Advisor to the County Emergency Organization The function of this position is to activate and provide interim management of the Emergency Operations Facility (EOF) and be available to advise the County Emergency Organization on the meaning and significance of information being transmitted from the site. Basic duties and responsibilities include:
- 1. Prior to the arrival of the Recovery Manager and until relieved, act as the EOF Director to activate the utility portion of the Emergency Operation Facility / Emergency '
Operations Center. In this capacity, specific functions include: a) Direct the activation of the utility portion of the . building by appropriately establishing comunications. b) Provide administrative and management direction of the EOF interim staff in carrying out the duties of the Radiological Emergency Recovery Manager, the Public Information Recovery Manager and the Operations and
. Analytical Recovery Manager.
c) Keep the Site Emergency Coordinator informed and serve as his contact at the EOF.
- 2. Keep the senior county response staff members advised of plant conditions and recomended protective actions.
- 3. Coordinate security of the EOF and UDAC portion of the ,
building with the Sheriff's Watch Comander. Z. Interim Radiological Emergency Recovery Manager This position assists the Advisor to the County Emergency Organization in coordination and direction of off-site i radiological assessment activities and development of radiological status information, until relieved by the corporate i Radiological Emergency Recovery Manager. Basic duties and i responsibilities include:
- 1. Develop radiological data and status information for '
evaluation by UDAC personnel and distribution to EOF and EOC j personnel. DC0075 17VIII l i I
0iAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/26/85 PAGE 18 0F .22 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION
- 2. Direct the activities of off-site monitoring teams and the mobile environmental monitoring laboratory in coordination o with the UDAC Director, maintain records, and provide findings in status reports.
- 3. Perform dose projections and provide radiological assessment infonnation for the determination of protective action recomendations.
AA. Interim EARS Operator--EOF This position assists the Radiological Emergency Recovery Manager in the perfonnance of his duties, including activation and operation of the EARS computer system, activation and operation of the health physics radio system and comunication with off-site monitoring teams, maintenance df logs and records and preparation of status reports as directed, until relieved by the corporate EOF EARS operator. BB. Interim Operations and Analytical Recovery Manager This position assists the Advisor to the County Emergency Organization in providing plant status information and coordination of local off-site emergency response activities, as directed, until relieved by the Corporate Operations and Analytical Recovery Manager. Basic duties and responsibilities include:
- 1. Act'.vation and operation of plant data computer systems for obtaining plant data.
- 2. Preparation of plant status updates for approval and I distribution to EOF, UDAC and EOC personnel.
I 3. Coordination and direction of off-site response activities involving local support, including activation and operation of radio and telephone systems and maintaining proper records of communications. CC. Interim Public Information Recovery Manager This position assists the Advisor to the County Emergency ( Organization in formulating news releases concerning the I emergency condition, obtaining approval of the release, and coordinating the news release with county and corporate public OC0075 18VIII
DIABLO CANYON POWEQ PLANT UNIT NO(S) - 1 AND 2 ON ' DATE 2/26/85 PAGE 19 0F 22 m Ls. ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION information personnel. It is staffed by a local public information representative until relieved by the Corporate Public Information Recovery Manager.
- 00. Technical Advisor to the Public Infomation Recovery Manager i
This position assists the Public Infomation Recovery Manager by providing technical assistance in the preparation of news releases and participation in news media briefings. EE. Radiological Data Processor (EOF) This interim position assists the Interim Radiological Emergency Recovery Manager in developing and evaluating radiological data. This may include serving as Monitoring Team Liaison Coordinator when offsite monitoring is required.
~
FF. Monitoring Team Liaison Coordinator This optional, interim position assists the Radiological Emergency Recovery Manager in commurications with monitoring , teams, the mobile van, and other emergency response locations when offsite monitoring activities are required. The position is relieved by the Radiological Monitoring Director. - GG. County Liaison This optional, interim position assists the Advisor to the County ' Emergency Organization by facilitating the flow of information between the E0F and EOC portions of the E0F/EOC buildire. HH. Mobile Environmental Monitoring Laboratory Operator This position supports the offsite radiological monitoring progran by providing isotopic analysis of samples obta'med by monitoring teams using the mobile van or other laboratt+y facilities. The results of analysis are communicated t) the EOF and appropriate records are kept. DC0075 19VIII
^
DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 2/26/85 PAGE 20 0F 22 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION l l FIGURE 1 i TYPIC AL ON-SHIFT EMERGENCY ORGANIZATION AND ASSIGNMENTS
$1TE EMERGENCY COORDINATOR
- I I I EMERGENCY EMERGENCY EMERGENCY EVALUATIONS LIAISON OPERATIONS AND RECOVERY COORDINATOR
- C00R0!NATOR* COORDINATOR I
l I I I EMERGENCY FIRST A10 LIAISON FIRE OPERATORS RADIOLOGICAL AND ME0lCAL AS$1STANT BRIGADE TEAM PERSONNEL PostTION TYPICAL ASSIGNMENT
- Interim Site Eme gency Coordinator
- Shift Foreman (Shift Technical Advisor if See Taa4e 1 for responsibilities) not available) interim Emergency Liaison Coordinator
- Auxiliary Operator or Shift Control (develops notification messages and Technician performs off-site notifications)
Interim Emergency Operations Sr. Control Operator or Control Operator Coordinator * (Provides operational control of the plant) Intenm Emergency Evaluations and Shift Technical Advisor (STA) ( Assisted by Shift Recovery Coordinator Ca.mP Technician and/or Control Operators (Plant and Radiological Assessment) if necessary) Liaison Assistants S5ift Clerk, Auxiliary Operator or : (Notifies plant staff, coordinates Shift Control Technician message dissemination among liaison personnel) Operators Assignments per the intenm Site Emergency Coordinator Fire 8ngede See Emergency Procedure M4 or R4 Emergency Radiological Team Shift C&RP Technician and Auxiliary Operator (if required) First Aid and Medical Employees at the scene
' Required Assignments DC0075 20VIII
NUMBER EP G-2 OiAsLO CANYON POWEA PLANT UNIT NO(S)' 1 AND 2 REVIS!ON 7
- DATE 2/26/85 PAGE 21 0F 22 1 TITLE ESTABLISHMENT OF THE ON-SITE EMERGENCY ORGANIZATION l l
FIGURE 2 ; LONG-TERM EMERGENCY ORG ANIZATION j I slTE l EMERGENCY l' COORDINATOR (T3C)
; ; g- - - - , i EMERGENCY EWERGENCY EMERGENCY EMERGENCY !
LIAISON MAINTENANCE OPERATION $ EVALUATIONS & l C0ORDINATOR C00R0lNATOR COORDIN ATO R COORDINATOR l (TSCI 105C) (C R) (Tsc) l s i UAl$0N MECHANICAL g EMERGENCY ! ADVISO R TO WAINTENANCE OPERATIONS ! COUNTY Assistants - FOREWAN iT3CJ ORGANIZATION (CR) ADVtsor a EutRGENCY (OSCI (TSC3 j ORGANIZATION I-SEE FIGURE 3 IEEU u,A;$oN MAINTENANCE ORGA izA1,0N TEC NICAL A0vis0R
----------' EOF OaGANizATim c
(OSC) (CR or 75C) INSTRUMENT MAINTENANCE _ OPERATOR $ ORGANIZATION (CRI (OSC) OPE R ATION AL SUPPO AT F1RE
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BRIGADES suNUv$s*0R tosci I l l EV A LU ATION EWERGENCY FIR $7 AID DATA EVACUATION RADIOLOGICAL ) A40mE0tCAL PROCESSOR $ COORDINATOR ADVISOR PERSONNE L (TSC) (TSCI I I I I l LEGEND:
- LINE AUTHORITY EVACUATION MO I ORING AN RAD 0 TA
#" PROTECTION
====LINE AUTHORITY UNTIL TEAus PROCESSORS C00RolNATOR RECOVERY MANAGE R ASSUMES EOF MANAGEMENT l ,
EOF EMERGENCY OPERATIONS FACILITY 8 TSC -TECHNICAL SUPPORT CENTER IN-PLANT C&RP TECMs MR OR-OSC-OPE R ATION AL SUPPORT CENTE R CR -CONTROL ROOM DC0075 21VIII
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NUMBER EP G-2 oiAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 7
~~
's OATE 2/26/85 PAGE 22 0F 22 TITLE. ESTABLISHMENT 0F THE ON-SITE EMERGDCY ORGANIZATION,_
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THE PUB LIC INFORMATION COUNTY MOBILE MANAGER LIAISON VAN
- --- Indicates Communication Channel A
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NUMBER EP G-2S1 . 7 G v4 3 Pacific Gas and Electric Company REVISION 2 pun DATE 5/15/85 DEPARTMENT OF NUCLEAR PLANT OPERATONS 1 AND 2 PAGE 1 0F 2 DIABLO CANYON POWER PLANT UNIT NO(S) EMERGENCY PROCEDURE TnLE NOTIFICATION OF THE ON-SITE EMERGENCY ORGANIZATION APPROVED
- M I'D -15 FLANI MANAGER s,
j .DATE SAFETY 1 SCOPE This procedure supplement provides the call sequence for the notification of the on-site emergency organization, and indicates the preferred candidates to fill each position as required by Administrative Procedure NPAP A-5. This procedure and changes thereto require PSRC review. PROCEDURE Notification of required personnel in an emergency is made using the Rapid Alert hotification System (RANS) or call sequence of this supplement, Form 69-10297, " Emergency Organzation Call List." RANS is not intended for Unusual Event notification. When using Form 69-10297, the preferred position holders should be contacted when possibk. An "On-Call" rotation for essential positions in the emergency organization is maintained in accordance with NPAP A-3, Supplement 1. The on-call person may be called if the preferred position holder is not imediately available or whenever judged necessary by the Shift Foreman. The primary means of notification during "off hours" or. when the site emergency signal is ut scuded trir.; r. mal wcrking h:urs is the tele;Mont. A backup , means of notification is the pager for those individuals designated "0N CALL". Key plant managers have UHF radio equipped cars which can be used for initial contact and two way comuncations while enroute to the plant. Because these persons are essentially on-call at all times, use of these vehicles is warranted in off hours to ensure rapid comunication and response. DC0234 IVII
1 AND 2 NUMBER EP G-251 . DIASLO CANYON POWER PLANT UNIT NO(S) REVISION 2 DATE 5/15/85 PAGE 2 0F 2 7gtg EMERGENCY ORGANIZATION CALL LIST FORM 69-10297 SUPPORTING PROCEDURES NPAP A-5, " Organizational Control Of Emergencies" NPAP A-3, Supplement 1, "On Call System & Personnel Availability" ATTACHMENTS
- 1. Description and Activation of the Rapid Alert Notification System.
- 2. Form 69-10297, " Emergency Organization Call List" e
9 DC0234 2VII
5/85 PACIFfC GAS AND ELECTRIC COMPANY Page 1 of 4 DEPARTMENT OF NUCLEAR PLANT OPERATZONS : DfABLO CANYON POWER PLANT UNfT NOS.1 AND 2 . j ATTACHMENT 1 TITLE: DESCRIPTION AND ACTIVATION OF THE RAPID ALERT NOTIFICATION SYSTEM (RANS)' j The RANS will begin the onsite emergency organization call-out when activated and deliver a pre-selected message. The person called should respond with an acknowledgement code. The RANS has the capacity to contact up to 512 individual people. There are eight lists and up to 64 groups in each list. The RANS dials numbers sequentially by list and within each list, sequentially by group. When a call is made, it is either logged acknowledged or not acknowledged. If the ' call is logged not acknowledged, RANS will continue to call the remaining numbers in that group until an acknowledgement or the programed number of notification attempts is reached. Once a call is acknowledged, the system will no longer attempt to call anyone else in that group. The system can deliver up to eight different messages. For Diablo Canyon these messages are: 1.
- 2. Alert -
Diablo Canyon has declared an Alert. Dial acknowledgement code. -
- 3. Site Area - Diablo Canyon has declared a Site Area Emergency Emergency. Dial acknowledgement code.
4 General - Diablo Canyon has declared a General Emergency. Emergency Dial acknowledgement code.
- 5. Test -
This is the Diablo Canyon call-out system test. Dial acknowledgement code. No response is required.
- 6. This is -
Alert - Diablo Canyon is simulating an Alert. Dial a Drill acknowledgement code.
- 7. This is - Site Area Emergency - Diablo Canyon is simulating a Site a Drill Area Emergency. Dial acknowledgement ode.
- 8. This is -
General Emergency - Diablo Canyon is simulating a a Drill General Emergency. Dial acknowledgement code. DC0234 35VI
5/85 3 age 2 of 4 TITLE: DESCRIPTION AND ACTIVATION OF THE RAPID ALERT NOTIFICATION SYSTEM (RANS) ACTIVATION OF THE RANS SYSTEM: There are two parts to the RANS, the data terminal and the front panel. The system is located in the Control Room Shift Foreman's Office. There are two ways that the RANS system can be activated:
- 1. Through the Data Terminal
- 2. Through the Front Panel Keyboard Before the system is activated, the user should know the access code, which lists to be called, and what message is to be delivered. The access code can be obtained by contacting the Shift Foreman. The message to be delivered is determined by the emergency classification.
EMERGENCY CLASSIFICATION LISTS TO BE MESSAGE TO BE SELECTED DELIVERED, ALERT 1, 2, 3 2 SITE AREA EMERGENCY 1,2,3 3
~
GENERAL EMERGENCY 1,2,3 4 NOTE: THE RANS IS NOT INTENDED FOR UNUSUAL EVENT NOTIFICATIONS. DC0234 36VI
l
. . 5/85 Page 3 of 4 TITLE: DESCRIPTION AND ACTIVATION OF THE RAPID ALERT NOTIFICATION SYSTEM (RANS) -
To Activate From The Data Terminal:
- 1. Verify that power is available to the printer. l l
The green light at the bottom right corner should be on. If this i light is not on;
- a. Check to make sure printer is on. The switch on the top of the printer should be in the on position. You should see a red dot.
- b. Check to make sure the printer is on-line. The switch next to '
the green light is the on-line switch. It should be pushed down on the side that has the red dot.
- 2. Enter the Access Code and press the " return" key.
- 3. The system will proceed through a "self-test." It will print the number of operative phone lines and the time.
- 4. To start the notification process, type "S."
- 5. The terminal will then request which lists are to be called. Enter the correct lists, separated by commas, and press the " return" key.
- 6. The terminal will request which message is to be delivered. Enter the appropriate message number and press the " return" key.
The system is activated and will begin the call-out sequence. _. g: If, during the activation, you need help, type " shift ?" and the syst'em will respond with more information. To STOP the system at any time, press the BREAK key. The RANS will automatically reset. The user must again enter the access code to activate the system. DC0234 37VI
5/85 Page 4 of 4 , TITLE: DESCRIPTION AND ACTIVATION OF THE RAPID ALERT NOPIFICATION SYSTEM (RANS) To Activate From the Panel Keyboard: The Automatic Notification Mode can be activated by entering the access code into the front panel keyboard. Be sure to use slow, deliberate strokes. If the access code was accepted, the " Wait" Ifght should start blinking. If this light is not on, depress the BREAK key on the Data Terminal and try entering the access code again.
- 1. When the " Ready" light appears, the system is ready to accept com nds.
- 2. To select the p' hone lists to be called, type the
- and then the appropriate list.
- 3. Repeat this for each list to be called.
l i 4 To select the message to be delivered, type the number key "#" and then the message number.
- 5. The phone lists and the message number shoul.d light up on the front panel.
If they are not correct, type the "##" key twice and reenter the ' phone lists and message. l 6. If the lights are correct, type the ** key twice to start the call-out process. g: To STOP the system at any time, press the BREAK key. The RANS will automatically reset. The user must again enter the access code to activate the system. l l t DC0234 38VI l l __
69-10297 5/85 (100)
~
EMERGENCY ORGANIZATION CALL llST DATE: TIME EVENT CLASSIFIED: EVENT CLASSIFICATION: ! EVENT DESCRIPTION: CALL OlIT INSTRUCTIONS
- 1. Contact one person for each position.
- 2. First name on list is preferred position holder; if unavailable contact next available person.
- 3. Persons with a
- are designated for "on-call" rotation. '
- 4. Give emergency classification and describe event if requested.
NDTE: Personnel to report to assigned location for Alert classification or higher; optional for Unusual Event. i DC0234 Page 1 of 32 3VII
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/N0fiyEMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Site Emergency *l. R.C. Thornberry Coordinator Plant Manager Assigned - TSC
*2. J. M. Giscion Tech Services Mgr
*3. W. B. McLane Materials & Project Coordination Manager
*4. J. A. Sexton Operations Manager s
1 DC0234 CONTROL ROOM ASSISTANT: 4VII 1. Insert date person is not available. Page 2 0F 32
- 2. Insert date person a< es "on-call" responsibility.
(Person on call will . .sess the pager for this . position) ,
.m .
69-10297 a/85 (100) . EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE ., EMERGENCY ~ HP FREQ. i ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL f CONTACTED YES NO Emergency *l. R. Patterson Operations Plant Superintendent Coordinator 3 Assigned - *2. S. R. Fridley Control Room Gen Operating Foreman
*3. J. R. Tinlin Sr Trng Instructor
*4. R. L. Fisher Sr Power Prod Eng (Operations) 1 4
j .. 1 i l DC0234 CONTROL ROOM ASSISTANT: i SVII 1. Insert date person is not available. Page 3 0F 32 '
- 2. Insert date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position)
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO AVAILABLE_ Emergency 1. J. M. Gisclon Evaluation Tech Services Manager
& Recovery Coordinator
*2. L. F. Womack Engineering Manager
*3. V. R. Foster Sr Power Prod Eng Assigned - TSC
*4. M. J. Angus Power Prod Eng l
l l l DC0234 CONTROL ROOM ASSISTANT: 6Vil 1. Insert date person is not available. Page 4 0F 32 '
- 2. Insert date persor sumes "on-call" responsibility.
l (Person on call w .. possess the pager for this position) - l l
o 69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE' EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL f TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Emergency *1. J. V. Boots ! Radiological Chem & Rad Prot Mgr . Advisor I Assigned - TSC *2. R. P. Powers Sr Chem & Rad Prot Engr ,
*3. H. W. C. Fong Chem & Rad Prot Eng 1
i l 1 i l DC0234 CONTROL ROOM ASSISTANT: .
! 7VII 1. Insert date person is not avaliable. Page 5 0F 32
- 2. Insert date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position)
E 69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO , Emergency *l. T. J. Martin Liaison Training Manager Coordinator
*2. J. E. Molden Assigned - TSC Ops Trng Supervisor i *3. W. F. Steinke
- Sr Trng Instructor i
~
DC0234 CONTROL ROOM ASSISTANT: 8VII 1. Insert date person is not available. Page 6 0F 32
- 2. Insert date person ;umes "on-call" responsibility.
(Person on call wi .--possess the pager for this position) ,
~
69-10297 5/85 (100) l EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE-EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL f C0HTACTED YES NO Advisor to the *l. W. B. Kaefer County Emerg. Support Services Ngr Organization Assigned - EOF *2. W. J. Keyworth Sr Power Prod Engr (Emergency Planning)
*3. W. S. Joiner Coordinator j (Emergency Planning) i I
l i i DC0234 CONTROL ROOM ASSISTANT: ! 9VII 1. Insert date person is not available. Page 7 0F 32 l 2. Insert date person assures "on-call" responsibility. l (Person on call will pnssess the pager for this position)
l. 69-10297 S/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURi HP FREQ. EMERGENCY TIME WILL BE IN DATE NOT DATE HOME PHONE / PAGER CALL # ORGANIZATION NO ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES POSITION AVAILABLE l Emergency None 1. J. A. Sexton Operations Operations Manager Advisor Assigned - TSC 2. S. R. Fridley Gen Operating Foreman
- 3. J. R. Tinlin Sr Trng Instructor i 4. R. L. Fisher Sr Power Prod Eng (Operations)
I - DC0234 CONTROL ROOM ASSISTANT: 10VII 1. Insert date person is not available. Page 8 0F 32
- 2. Insert date person sumes "on-call" responsibility.
(Person on call wi ,_ possess the pager for this position) ,
~ .
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Emergency Main- *l. D. B. Miklush tenance Coor- Maintenance Manager dinator Assigned - OSC *2. W. G. Crockett I&C Maintenance Mgr
*3. R. Nanninga Sr Pow Prod Eng (Maint)
*4. D. L. Bauer Sr Power Prod Eng (Maint) 1 i
e I i l DC0234 CONTROL ROOM ASSISTANT: IIVII 1. Insert date person is not available. Page 9 0F 32
- 2. Insert date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position)
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO l Media Information Specialist None 1. Ron Weinberg News Services i Diablo Canyon
- 2. David Monfried News Services Manager San Francisco, G.0.
- 3. Don Hanes
' News Services Director San Francisco, G.O.
- 4. Jim Kilpatrick News Services Director San Francisco, G.O.
1 I l .1 i l i 1 i - DC0234 CONTROL ROOM ASSISTANT:
; 12VII 1. Insert date person is not available. Page 10 0F 32 l 2. Insert date person mnes "on-call" responsibility. ; (Person on call wi. , ossess the pager for this position) ,
STOP CALL-OlIT AT Tills POINI FOR TE LMUSUAL EVENT CLASSIFICATION - CONTIRE FOR HIGER CLASSIFICATION, DETEIMIE IF TE SITE EERGENCY C00I0lNATOR EQJIES ADDITIONAL PERS0PfEL, .l l l i j -, i l 1 l DC0234 Page 11 0F 32 13VII l .
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT OATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Opera tional Mone 1. S. J. Foat Support Center Electrical Engineer Supervisor
- 2. R. B. Willis
- Assigned - OSC Mechanical Engineer
- 3. R. T. Hanson Electrical Engineer
- 4. D. R. Stupi Welding Engineer
- 5. R. P. Warren
- Maintenance Engineer 4 ,
e 1 I DC0234 CONTROL ROOM ASSISTANT: 14VII 1. Insert date person is not available. Page 12 0F 32
- 2. Insert Date person uses "on-call" responsibility. ,
(Person on call wi. --possess the pager for this position) .
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL f CONTACTED YES NO Site Chemistry *l. H. A. Ferguson & Radiation Chem & Rad Prot Foreman Protection Coordinator *2. L. T. Moretti Chem & Rad Prot Foreman Assigned - Access Control *3. R. L. Johnson Chem & Rad Prot Foreman
*4. F. A. Guerra Chem & Rad Prot Foreman
*5. J. A. Robbins Chem & Rad Prot Foreman
*6. L. Vulchev Chem & Rad Prot Foreman i
+
10TE: The person assigned this position also assures that adequate Chemistry and Radiation Protection Technicians are available. As a minimum this includes: Six CSRP technicians for on-and-off site monitoring teams. Six CARP technicians for in-plant monitoring and chemistry. DC0234 CONTROL ROOM ASSISTANT: ISVII 1. Insert date person is not available. Page 13 0F 32
- 2. Insert Date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position) m *u
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO TSC/ EOF None 1. C. D. Lampert Clerical Of fice Supervisor Assistance
- 2. E. G. St. John Asst Office Supervisor
- 3. D. W. Swearingen Asst Office Supervisor NOTE: Request supervisor to dispatch three (3) clerks to the TSC and two (2) clerks to the E0F, DC0234 CONTROL ROOM ASSISTANT:
16VII 1. Insert date person is not available. Page 14 0F 32
- 2. Insert Date person - uses "on-call" responsibility.
(Person on call wi -possess the pager for this position) .
69-1029i 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Interim None 1. W. A. O'Hara Radiological Sr Chem & Rad Prot Eng Emergency Recovery Manager 2. S. J. Fahey-Benson Chem & Rad Prot Eng Assigned - EOF 9 DC0234 CONTROL ROOM ASSISTANT: 17VII 1. Insert date person is not available. Page 15 0F 32
- 2. Insert Date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position)
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT OATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO i::terim None 1. M. W. Mak EOF-EARS Computer Specialist Operator
- 2. D. R. Clifton Assigned - EOF Maint Trng Supervisor 1
DC0234 CONTROL ROOM ASSISTANT: 18VII 1. Insert date person is not available. Page 16 0F 32
- 2. Insert Date person sumes "on-call" responsibility.
(Person on call wi. , possess the pager for this position) ,
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69-10 97 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE HP FREQ. EMLRGENCY TIME WILL BE IN HOME PHONE / PAGER CALL # OR.WIIZATION DATE NOT DATE CONTACTED YES N0 ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # PCSITION AVAILABLE i I:sterim None 1. Ron Weinberg Ptblic Public Information 1:: formation R:covery 2. Missie P. Hobsom Manager Public Information Assigned - EOF 3. Pam Zweifel Manager, Information Center l . l DC0234 CONTROL ROOM ASSISTANT: 20VII 1. Insert date person is not available. Page 18' 0F 32
- 2. Insert Date person unes "on-call" responsibility. -
(Person on call wi. .jossess the pager for this position) ,
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE' EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT Pil0NE GROUP CALL # CONTACTED YES NO Technical None 1. W. J. Keyworth Advisor Sr Power Prod Engr to the Public (Emergency Planning) Infonnation Recovery Manager 2. W. J. Kelly Power Prod Eng Assigned - EOF (Reg Compliance)
- 3. B. A. Loconte Nuclear Gen Engr I
4 l l DC0234 CONTROL ROOM ASSISTANT: 21VII 1. Insert date person is not available. Page 19 0F 32
- 2. Insert Date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position)
69-10297 5/85 (100) EMERGEN,CY OR6ANIZATION CALL LIST -- _, NOT FOR PUBLIC DISCLOSURE EMERGENCY + , HP FREQ. ORGANIZATION DATE NOT DATE : -ll0ME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL [ CONTACTED YES NO Mobil (Personnel 1. Roland Richardsor. # E vironmental / r'ota te y , Dept of Engr Research y Monitoring pager ' ' ; Lcboratory as p-Operator required) 2. Mike Kunde ,-
- Dept of Engr Research ,
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T l I i i I DC0234 CONTROL ROOM ASSISTANT:
- 22VII 1. Insert date person is not available. Page 20 0F 32
- 2. Insert Date persor sumes "on-call" responsibility.
(Person on call wi , possess the pager for this position) ,
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE ' EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL _ NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL f CONTACTED YES NO EARS Operator *l . R. H. Garacci TSC Sr C&RP Analyst Assigned - TSC
*2. J. N. Johnson C&RP Analyst
*3. E. R. Psoter
- C&RP Analyst DC0234 CONTROL ROOM ASSISTANT: 23VII 1. Insert date person is not available. Page 21 0F 32
- 2. Insert Date person assimes "on-call" responsibility.
(Person on call will possess the pager for this position)
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN ORGANIZATION ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO POSITION AVAILABLE Emergency 1. J. E. Holden Liaison Training Supervisor Assistant #1
*2. R. F. Sargent Assigned - TSC Sr Training Instructor
*3. J. P. Northness Training Instructor
*4. B. E. Terrell Training Instructor
*5. W. E. Weems Training Instructor
*6. G. W. Hamann Training Instructor .
*7. J. M. Welsch Training Instructor .,
10TE: Contact Two people from this list. I Only one "on-call" person for this position. l DC0234 CONTROL ROOM ASSISTANT: . 24VII 1. Insert date person is not available. Page 22 0F 32 '
- 2. Insert Date person r ames "on-call" responsibility.
(Person on call wi , ssess the pager for this position)
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE - EMERGENCY HP FREQ. DRGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL f TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT Pil0NE GROUP CALL ! CONTACTED YES NO Emergency *l. R. L. Graham Liaison Sr Trng Instructor Assistant #2
*2. D. A. Lewis Assigned - TSC Asst Trng Coordinator
*3. L. R. Sawyer Asst Trng Coordinator
*4. J. M. Becerra Training Instructor
*S. G. E. Somers Training Instructor
*6. C. J. Leach Training Instructor
*7. N. M. Bennett Training Instructor NOTE: Contact THREE people from this list.
Only one "on-call" person for this position. DC0234 CONTROL ROOM ASSISTANT: 25VII 1. Insert date person is not available. Page 23 0F 32
- 2. Insert Date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position)
t 69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Data Processor *l. T. Black No. 1 Power Prod Engr (Computer) Assigned - TSC
*2. G. V. Johnson Power Prod Engr (Computer)
*3. J. K. Bigelow -
i Power Prod Engr (Computer)
. i
*4. J. D. Lodge Power Prod Engr (Computer)
*5. D. A. Remington Power Prod Engr (Computer) .,
*6. G. R. Wescom Applications Analyst i
DC0234' CONTROL ROOM ASSISTANT: 26VII 1. Insert date person is not available. Page 24 0F 32
- 2. Insert Date person a- es "on-call" responsibility.
(Person on call wil., _,sess the pager for this position) ,
D 69-10297 o/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE - EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Data Processor *l. P. W. Baum No. 2 & No. 3
*2. W. A. Ginter Assigned - TSC
*3. P. E. Rigney
*4. R. D. Thurston
*S. K. Wallace
*6. W. H. Yip ,
*7. C. Pendleton
*8. J. Hjalmarson
*9. P. Sarafian
*10. D. Efron
*11. C. Beall 4
*12. J. Nolan M)TE: Contact TWO people from this list.
Only one "on-call" person for this position. DC0234 CONTROL ROOM ASSISTANT:- 27VII 1. Insert date person is not available. Page 25 0F 32
- 2. Insert Date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position)
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST _NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Instrument *l. M. Hanrahan Maintenance Sr IAC Supervisor Coordinator
*2 D. D. Malone Assigned - OSC Sr.18C Supervisor
*3. N. A. Rego11 IAC Supervisor DC0234 CONTROL ROOM ASSISTANT:
28Vil 1. Insert date person is not available. Page 26 0F 32
- 2. Insert Date person unes "on-call" responsibility.
(Person on call wi . p ssess the pager for this position) ,
69-10297 S/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE -
- EMERGENCY HP FREQ.
ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL f TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Electrical *l. G. M. Zocher Maintenance Gen Elec Foreman Coordinator
*2. J. M. Rappa Assigned - OSC Elec Foreman
*3. Clay Beck Electrical Foreman
'l l
i DC0234 CONTROL ROOM ASSISTANT: 29VII 1. Insert date person is not available. Page 27 0F 32
- 2. Insert Date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position)
69-10297 5/85 (100) . EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL f TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Mechanical *l. W. R. Ryan Maintenance Gen Maint Foreman Coordinator
*2. J. D. Albers Assigned - OSC Mech Foreman
*3. J. E. Strahl Mech Foreman
*4. G. H. Brodnick Mech Foreman
*S. J. O. Askins Hech Foreman DC0234 CONTROL ROOM ASSISTANT:
30VII 1. Insert date person is not available. Page 28 0F 32
- 2. Insert Date person a mes "on-call" responsibility.
(Person on call will -ssess the pager for this position) ,
e 69-10297~ 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE' EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL f TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL f CONTACTED YES NO Radiological None 1. A. O. Taylor Data C&RP Engineer Processor
- 2. R. S. Snyder Assigned - TSC CARP Foreman
- 3. D. R. Unger C&RP Engineer l t DC0234 CONTROL ROOM ASSISTANT:
31VII 1. Insert date person is not available. Page 29 0F 32
- 2. Insert Date person assumes "on-call" responsibility.
(Person on call will possess the pager for this position)-
- . m
69-10297 5/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL f CONTACTED YES NO l Radiological None 1. K. R. Bieze Data Sr Trng Instructor Processor l- 2. G. P. Monk Assigned - EOF Trng Instructor f0TE: Contact TWO people from this list. l DC0234 CONTROL ROOM ASSISTANT: 32VII 1. Insert date person is not available. Page 30 0F 32
- 2. Insert Date person sumes "on-call" responsibility. *
(Person on call wi_ , possess the pager for this position) ,
69-10297 a/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE - EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME WILL BE IN POSITION AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Records None 1. C. Leon Meyers Management Records Analyst Assigned - TSC 2. L. Yamaguchi Records Analyst
- 3. J. M. Neill Document Control Supv DC0234 CONTROL ROOM ASSISTANT:
33VII 1. Insert date person is not available. Page 31 0F 32
- 2. Insert Date person assumes "on-call" responsibility. '
(Person on call will possess the pager for this position)
~
69-10297 S/85 (100) EMERGENCY ORGANIZATION CALL LIST NOT FOR PUBLIC DISCLOSURE EMERGENCY HP FREQ. ORGANIZATION DATE NOT DATE HOME PHONE / PAGER CALL # TIME POSITION WILL BE IN AVAILABLE ON-CALL NAME/NON-EMERGENCY TITLE PLANT PHONE GROUP CALL # CONTACTED YES NO Security None 1. R. G. Todaro Liaison Security Supervisor Assigned - TSC 2. J. P. Hubble Sr Security Shift Supvr
- 3. L. C. Fisher Sr Security Shift Supvr
- 4. D. R. Dysert '
Security Shift Supvr NOTE: CALL SEClRITY SHIFT SlFERVISOR (EXT. 3330) AND PROVIDE A LIST OF PERS0KL C(NING ONSITE WEN CALLOUT IS CCM'LETE, i DC0234 CONTROL ROOM ASSISTANT: 34Vil 1. Insert date person is not available. Page 32 0F 3?
- 2. fr.ert Date persen mes "on-call" responsibility.
(Person on call wil rossess the pager for this position) - .
PGandE Letter No.: DCL-85-222 CURRENT , EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Yolume 3B TITLE REV OR-1 Offsite Support & Assistance 4 OR-2 Release of Information to the Public 3 EF-1 Activation and Operation of the Technical Support Center 5 EF-2 Activation and Operation of the Operational Support Center 5 EF-3 Activation and Operation of the Emergency Operations Facility 5 EF-4 Activation of the Mobile Environmental Monitoring Laboratory 6 EF-5 Emergency Equipment, Instruments & Supplies 6 EF-6 Operating Procedures For EARS 9845C Controlling Stations 4 EF-6S1 Transfer of EARAUT Control 1 EF-8 EARS Operating Procedures for TSC-CC HP-1000 Station 0 RB-1 Personnel Dosimetry _ 1 RB-2 Emergency Exposure Guides 1 RB-3 Stable Iodine Thyroid Blocking 1 RB-4 Access to & Establishment of Controlled Areas Under Emergency Conditions 2 RB-5 Personnel Decontamination 2 RB-6 Area & Equipment Decontamination 2 RB-7 Emergency On-Site Radiological Environmental Monitoring 4 RB-8 Emergency Off-Site Radiological Environmental Monitoring 4' RB-9 Calculation of Release Rate & Integrated Release 3 RB-10 Protective Action Guidelines 1 RB-11 Emergency Off-Site Dose Calculations 4 RB-12 Mid and High Range Plant Vent Radiation Monitors 1 RB-13 Improved In-Plant Air Sampling for Radiciodines 1 RB-14 Core Damage Assessment Procedure 2 RB-15 Sentry Post Accident Sampiing System (SPASS) Initial Sampling Exercise After An Accident 1 RE- MA SPASS Inf tial Actions During An Emergency 3 RB-;6J SPASS Reactor Coolant Sampling (Stripped-Gas and Diluted RCS) 2 OS02d/0005K 06/21/85 l l
TITLE REV RB-15C SPASS Containment Air Sampling 2 RB-15D SPASS Gas Chromatographic Hydrogen Analysis 2 RB-15E SPASS RCS Liquid and Gas Sample Handling 2 RB-ISF SPASS Data Analysis 1 RB-15G SPASS ION Chromatographic Chloride analysis 1 RB-15H SPASS pH/ Conductivity / Dissolved Oxygen 1 RB-15I SPASS Sample Storage and Disposal 0 RB-16 SPASS Subsequent Sampiing 0 RB-16A SPASS Initial Actions During An Emergency (Not Intended to Meet The 3-Hour Time Limit) 2 RB-16B1 SMS Diluted Liquid Sampling From Reactor Coolant (Not Intended to Meet The 3-Hour Time Limit) 1 RB-1682 SMS Undiluted Liquid Sampling From Reactor Coolant (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16B3 SMS Reactor Coolant Stripped Gas Sampiing (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16B4 SMS Diluted Liquid Sampling From Radwaste (Not Intended to Meet The 3-Hour Time Limit) 2 RB-1685 SMS Undiluted Liquid Sampling From Radwaste (Not Intended to Meet The 3-Hour Time Limit) 2 RB-16C SMS Containment Air Sampiing _ (Not Intended to Meet the 3-Hour Time Limit) 1 RB-16D SMS Gas Chromatographic Kydrogen Analysis (Not Intended to Meet the 3-Hour Time Limit) 1 RB-16E SMS Liquid and Gas Sample Handling (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16F SMS Data Analysis (Not Intended to Meet The 3-Hour Time Limit) 0 RB-16G SMS Ion Chromatographic Chloride Analysis (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16H SMS Ph/Caductivity Dissolved Oxygen (Not Intended to Meet The 3-Hour Time Limit) 1 RB-16I SMS Undiluted Containment Air Sampling (Not Intended to Meet The 3-Hour Time Limit) 0 RB-16J SMS Sample Storage and Disposal (Not Intended to Meet The 3-Hour Time Limit) 0 0502d/0005K C6/21/85
m NWBER EP RB-14 F(B*#E Pacific Gas and Electric Company REVISION 2 DEPARTMENT OF NUCWAR PLANT OPERATIONS DATE 1/18/85 PAGE 1 OF 13-DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 IMPORTANT EMERGENCY PROCEDURE 73T 2 CORE DAMAGE ASSESSMENT PROCEDURE TO g
. SAFETY APPROVED: W* $~ ,Fy PLANT MANAGER M DATE SCOPE This procedure describes the evaluation of the extent of core damage following an accident that can lead to inadequate core cooling.
This procedure and revision thereto requires PSRC review. DISCUSSION Fuel damage resulting in the release of radioactive material can occur following a loss of coolant accident (LOCA) or following the loss of available heat sinks. These events, if uncorrected, can lead to localized or widespread overheating of reactor fuel and eventually to fuel rod cladding failure, and/or fuel melt. The description of plant parameters indicative of ( conditions that can lead to fuel failure or melt are provided in the Emergency Equipment Operation Pmcedures (OP Series). This procedare supplements other emergency procedures by providing a methodology to detennine the extent of core damage that may have resulted from an accident. This procedure does not replace procedures that are used to provide instructions regarding accident identification and/or mitigation or dose assessment although similar data and assessment is utilized in this procedure to dete.rmine the type and extent of fuel damage. . The objective of this procedure is the classification of fuel damage into one of four broad categories: (1) no fuel damage, (2) fuel cladding damage. (3) fuel overheat, and (4) fuel melt. Within the latter three categories, the procedure permits a rough estimate of damage as a proportion of core radionuclide inventories that have been released to the reactor coolant and/or containment atmosphere. It prov..es a preliminary and a long tenn methodology for assessing core damage. The preliminary assessment utilizes rough evaluations of plant parameters such as reactor vessel level and reactor coolant temperatures to confirm that conditions exist which can lead to core damage, and quantifies the damage through the use of containment hydrogen levels and containment radiation levels. The long-tenn methodology requires that reactor coolant and containment air samples be obtained and analyzed for radiochemical and chemical parameters. These results are then used, along with other plant parameters, to determine the extent of core damage. The preliminary assessment can yield quick initial results (within approximately 10 minutes). DC0279 11V
=
otAsLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER EP RB-14 REVISION 2 DATE 1/18/85 - PAGE 2 OF 13 TiTLECORE DAMAGE ASSESSMENT PROCEDURE The long-term assessment could require up to three (3) hours to obtain sample arialyses and further time for computation and evaluation of the results, but yields additional inforination necessary to distinguish between cladding failures, fuel overheat, and fuel melt. PROCEDURE
- 1. Pmliminary Assessment It should be noted that the results obtained in step b and c of this section are indicators of the various categories of fuel damage.
Therefore, when completing the long term assessment for core damage I (Section 2), these results should be used as confimation. j
- a. If personnel in the TSC have indicated that conditions exist that could lead to inadequate core cooling, or ineffective ESF functioning under LOCA conditions (perr EP OP-1 Appendix H), skip this section and proceed to Step lb. Otherwise, detemine the potential for fuel damage by completing Attachment 1.
- b. Complete Attachment 2. " Containment Radiation Monitors".
- c. Camplete Attachment 3 " Containment Hydrogen Levels". )
- 2. Long-Term Assessment l
- a. Request Sample Collection Request that the Emergency Radiological Advisor (ERA) assign a sampling team to collect samples from the Post Accident Sampling System (PASS). Recomended sampling locations are shown in Table 1.
- b. Request Isotopic Analysis on:
(1) Liquid sample from the Liquid Sampling Panel (LSP). (2) Containment air sample from the Containment Air Sampling Panel (CASP).
- c. Request Chemical Analysis for:
(1) Hydrogen concentration on stripped gas from the liquid sample from the LSP. (2) Hydrogen concentration on containment air sample from the CASP.
- d. Request that the sample analysis be decay corrected back to the time of sampling.
l ) L _ DC0279 21V
- _ y
OtA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NLVBER EP RB-14 REVISION 2 4 DATE 1/18/85 PAGE 3 OF 13 TRLE; CORE DAMAGE ASSESSMENT PROCEDURE
. e. Await sample analyses. This may take up to 3 hours. In the interim, continue to assess core damage via the techniques provided 1 in Section 1 of this procedure. When sample analyses are available.
l proceed to Step 2.f. I
- f. Analysis of Sample Results
- 1) Canplete Attachment 4 " Water Inventory Worksheet."
- 2) Complete Attachment 5, " Airborne Inventory Worksheet."
- 3) If reactor power for the 30 days prior to shutdown remained relatively constant (within the range of e10 percent) proceed to Attachment 6 and determihe the power corrected source inventories. Otherwise, complete Attachment 7 to correct source inventories for a variable power history.
- 4) CompleteAttachment8todetermihepercentageoffuel'orGAP activity released.
- 5) Refer to Attachment 9 to determine what type of failure (no damage, clad, overheat, melt) is occurring (if any).
- 6) Report results determined by this procedure to the individual I making the request for a core damage assessment.
- 7) Continue to monitor the situation by utilizing this procedure as necessary.
1 DC0279 31V
l NUMBER EP RB-14 , DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 2 DATE 1/18/85 PAGE 4 OF 13 mLE. CORE DAMAGE ASSESSMENT PROCEDURE
- Table 1 ,
Reconnended Sample Locations Plant Parameters Sanpling Location
- Small break LOCA Reactor Power > 1% RC Hot Leg 1 or 4 (LSP)
Containment air (CASP) Reactor Power < 1% RC Hot Leg 1 or 4 (LSP)
- Large break LOCA Reactor Power > 1% Reactor Cavity Sump (LSP)
' Containment air (CASP)
E HM Lg l or 4 . Reactor Power < 1% Reactor Cavity Sump (LSP) Containmentair(CASP)
- Steam Line break RC Hot Leg 1 or 4 (LSP)
Containment air (CASP) .
- - Steam Generator tube rupture RC Hot Leg 1 or 4 (LSP)
Containment air (CASP)
- Indication of significant Reactor Cavity Sump (LSP)
Containment Sump Inventory Coitainment air (CASP)
- Containment building Reactor Cavity Sump (LSP)
Radiation Monitor Alarm Cantainment air (CASP) I
- Safety injection actuated RC Hot Leg 1 or 4 (LSP)
)
- Indication of High Radiation RC Hot leg 1 or 4 (LSP)
Level in RCS
)
DC0279 41V
1' NUMBER EP RB-14 OLABLO CANYON POWER PLANT UNIT NO('S) 1 AND 2 REVISION 2 DATE 1/18/85 PAGE 5 OF 13 7TLE. CORE DAMAGE ASSESSMENT PROCEDURE FIGURE 1 Saturation Curve 1600 i 2400 2200 1 _ 1800 *
\
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I I NUMBER EP RB-14 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 * ' REvlSION 2 DATE 1/18/85 PAGE 6 OF 13 . Tine CORE DAMAGE ASSESSMENT PROCEDURE I l FIGURE 2
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i
' NUMBER EP RB-14 OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 2 -
e DATE 1/18/85 PAGE 11 OF 13 t TITLE: CORE DAMAGE ASSESSMENT PROCEDURE FIGURE 7 Density Correction Factor 1.0 _ y _ x- = - = _ - . ..= _ .. __ _-_mg=s __. _ _ _ - . _ _ _ _ =
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I o 100 200 300 400 500 TWFEMTWE (8F) 4 l DC0279 111V i
1 AND 2 NUMBER EP RB-14 DIA8LO CANYON POWER PLANT UNIT NO(S) ' REVISION 2 DATE 1/18/85 PAGE 12 OF 13 TITLE: CORE DAMAGE ASSESSMENT PROCEDURE
- FIGURE 8 Power Correction Factor for Cs-134 1.00
-901 POWER
.80 -
- 755 PWER 5
lE as * .40
.a - - , . .
.20
^
0.0 0.0 100 200 300 400 500 600 700 800 900 OPEMTim (OAYS) DC0279 12IV
"""F" "- - - ' ' -
- DIABLO CANYON POWER PLANT UNIT Nd(S) 1 AND 2 NUMBER EP RB-14 i REVISION 2 .
DATE 1/18/85 TITLE: CORE DAMAGE ASSESSMENT PROCEDURE l ATTACHMENTS
- 1. Corroborating Evidence of Core Damage
- 2. Containment Radiation Monitors
- 3. Containment Hydrogen Levels
- 4. Water Inventory Worksheet
- 5. Airborne Inventory Worksheet
- 6. Calculation of Power-Corrected Source Inventories for Constant Power Levels ,
- 7. Source Inventory Power Correction for Variable Power History
- 8. Comparison of Expected and Actual Source Inventories
- 9. Qualitative Assessment o
3 OCO279 131V
l PACIFIC GAS -AND ELECTRIC COMPANY Page 1 of 1 l DEPARTMENT OF NUCLEAR PLANT OPERATIONS ; DI ABLO CANYON POWER PLANT UNIT NOS.1 AND 2 l TITLE: CORROBORATING EVIDENCE FOR CORE DAMAGE ! 1 ATTACHMENT 1 Check the Appropriate Answer YES NO
- 1) Are five or more core exit thermocouples temperatures greater than 1,200*F? []
- 2) Can SI and/or charging flow to the RCS be verified? []
- 3) Can AFW flow to the steam generators and CCW and ASW flow be verified? []
- 4) Am RCS pressure and core exit T/C temperature !
(T hottest) within the " Acceptable Area" of subcooling as detemined using Figure 17 []
- 5) Are containment rad. monitors (RE-30 -and 31) .
reading greater than IR/hr.? []
- 6) Is containment pressure greater than 1.3 psig? []
'- 7) Is containment temperature greater than 120*F? []
- 8) Is containment hydrogen level as indicated by monitors CEL-82 and CEL-83 up scale? []
- 9) If any of the boxes (as opposed to line spaces) for the previous questions were checked then those conditions are potentially indicative of inadequate core cooling or a LOCA* therefore, proceed to step 1.b.
10 ) If none of the boxes were checked, continue monitoring the situation in accordance with applicable procedures. i
- NOTE: In general, the more boxes that are checked, the greater the potential for inadequate core cooling. However, evaluation is necessary to detemine the significance of this information. For conservatism, continue with this procedure if a full evaluation cannot be performed.
DC0279 141V
PACIFIC GAS. AND ELECTRIC COMPANY Page 1 of 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DI ABLO CANYON POWER PLANT UNIT NOS.1 AND 2 TITLE: CONTAINMENT RADIATION MONITORS ATTACHMENT 2 If loss of reactor coolant to the containment is not occurring, skip this section and proceed to Section 2.
*1) Record time since reactor trip (hrs). hrs @
- 2) Record reading of containment area monitor (RE-30) (R/hr). R/hr@
- 3) Record reading of containment area monitor (PE-31)(R/hr). R/hr h
- 4) If both monitors are operable determine average area monitor reading as follows:
[(@+h)/2](R/hr). R/hr @ Otherwise use the operable monitor for Item h.
- 5) Clad failure or fuel melt is indicated if the value of ItemOD 's greater than 1R/hr. To estimate the level of either damage romplete steps 6 through 8.
- 6) Compare Item @ determined in step 4 with the average response curves found in figures 2 and 3. Determine the type and degree of core
( damage by using the following interpolation technique: (hx100)/[100% exposure rate in figure 2 or 3'at time @].
- 7) ** Check the applicable type of damage: ,
No Damage Clad Failure , Percent Failure % Fuel Melt , Percent Damage %
- 8) Proceed to section 2 of this procedure if fuel melt is indicated, otherwise proceed to step 1.c.
- NOTE: In case of RE30 and RE31 monitor failure, have chemical and radiation protection personnel take exposure rate readings at the equipment hatch shield and/or personnel hatch steel door with an ionization chamber and use figures 4 and 5 for this step of the procedure. The interpolation technique in step 6 can be used in this case.
**In general, values below the 100% gap release curve (figure 2) are indicative of clad failure, while values below the 100% fuel release curve (figure 3) are indicative of fuel damage.
DC0279 151V
. t i
PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 1 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DI ABLO CANYON POWER PLANT UNIT NOS 1 AND 2 - TITLE: CONTAINMENT HYDROGEN LEVEL i ATTACM ENT 3 To provide a quantitative verification of the degree of clad damage complete steps I through 6.
- 1) Record reading of containment hydrogen monitor CEL-82(%). @
- 2) Record reading of containment hydrogen monitor CEL-83(%).
- 3) Deterinine average hydrogen i monitor reading as follows.
[( % )/2)(%). %@
- 4) Compare itehetermined in step 4 with the curve of " Expected H2 concentration versus percent clad failure" found as figure 6.
- 5)
- Estimate and record the percent clad failure.
No clad failure Clad failure , %
- 6) Proceed to Section 2. .
- NOTE: Hydrogen levels in containment are a valid indicator of damage only within the first 24 hours of the accident, assuming that the hydrogen recombiners are not operating. Since complex mechanisms dictate the amount of Hp and radioactive materials released to containment it is not passible to predict which assessment of clad damage is more accurate. If results of damage assessment using the rad monitors and the H, monitors differ, try to utilize corroborating data from'RVLIS, etc., to select the most representative assessment of damage. If resolution cannot be obtained, use the highest estimated level of clad failure.
DC0279 161V
o . PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 TITLE: WATER INVENTORY WORKSHEET ATTACHMENT 4
- 1. Check the appropriate sample type:
Hot Leg I Hot Leg 4 h Reactor Cavity Sump
- 2. Convert the elapsed time from the reactor trip and the sample collection to '
hours: hr @
- 3. If the sample is a Hot Leg sample, record the following information:
Temperature (Tave) *F Pressure psia Density Correction Factor (Figure 7)
- 4. Last RWST volume prior to accident gal h
- 5. Current RWST volume gal @
- 6. Volume of RWST injected ( @-@) = gal @
- 7. Detemine which ECCS volumes have been released into the RCS cr containment, and detemine the total volume in the Containment Sump:
Total Volume Ac'ual Used in RCS (1) RWST Volume r H x3,785h= cc@ 7 (2) Each Accumulator = 4.28 X 10 cc (there are four accumulators) cc@ 8 8 (3) RCS = 3.56 X 10 cc 3.56 x 10 cc@ (4) Total Volume (@ + h + h) cc @
- 8. Enter the values of @ and L on the next page and calculate.the total water inventory as ind cated.
DC0279 171V
Page 2 of 2 TITLE: WATER INVENTORY WORKSHEET ATTACHMENT 4(Continued) C lD3 laj A B Measured Liquidi Activity at Total Sample Activity RCS Conditions Water Entrained Isotope (uC1/cc) (uCi/cc) Inventory (Ci) Kr-87 Xe-13 I-13 1 1-133 Te-132 Cs-134 . Ba-140 La 140
)
[a] Column B = Column A x @ D- [b] Colu.mn C = Column B x @ x 1 x 10~0
- 9. Proceed to step 2.f.2 of this procedure.
t Liquid is defined as the total activity from the Liquid sample, including any off gases. DC0279 1BIV
PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATION DIABLO CANYON POWER PLANT UNIT N05.1 AND 2 TITLE: AIRBORNE INVENTORY WO9KSHEET ATTACMENT 5
- 1. Record the elapsed decay time since reactor trip and the collections of the containment air sample in hours:
hrh
- 2. Record the following information:
Containment Atmosphere Temperature 'F Containment Atmosphere Pressure psia Sample Temperature 'F Sample Pressure psia
- 3. Calculate the Containment atmosphere Pressure and Temperature (P-T) correction factor using the following formula:
+ 460 P-T Correction Factor = *
, 46 )
P-T Correction Fictor -
- 4. Record the containment airborne sample activities in Column A on page 2 of this attachment. (NOTE: The containment activities reported by the sampling teams are at room temperature and pressure).
- 5. Adjust the reported activities to the conditions of temperature and pressure found.in the contain by multiplying the values in Column. A by the P-T correction factor, and recording the result in Column B.
- 6. Calculate the total airborne inventory of the nuclides of interest by multiplying all the values in Column B by 7.36E+04. (This is the Containment volume of 7.36E+10cc and the conversion factor of 10 -6 Ci/uC1.) The results should be recorded in Column C.
l l DC0279 191V
O n. Page 2 of i
~
TITLE: AIRBORNE INVENTORY 'JORKSHEET ATTACHMENT 5(Continued) A B laj C lD3 Measured Sanple Activity at Activity Containment Conditions Total Airborne Nuclide (uCi/cc) (vC1/cc) Inventory (C1) Kr-87 Xe-13 I-13 1 1-13 3 = 0 , . [a] Column B = Column A x h [b] Column C = column B x 7.36E+04
- 7. Proceed to Step 2.f.3. ,
DC0279 20IV
. D PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DI ABLO CANYON POWER PLANT UNIT NOS.1 AND 2 -
^ TITLE: CALCULATION OF POWER-CORRECTED SOURCE INVENTORIES FOR CONSTANT POWER LEVELS ATTACHMENT 6 This, form is only to be used when the power level has remained relatively constant within the range of 210 percent, in the last 30 days. If the power ] level has not been relatively constant, use Attachment 7.
- 1. Estimate and record the steady state power percentage for prior 30 days. %@
- 2. Estimate and record the steady state power percentage for prior 4 days. %@'
! 3. Calculate the Power Correction Factors as follows:
- 1) For Isotopes with Half-life > 1 day Power Correction Factor =
, 2) For Isotopes with Half-life < 1 day P:wer Correction Factor p ,
- 4) Calculate Corrected Source Inventory, Column 2, as follows:
Corrected Source Inventory = Column 1 x Corresponding Power Correction Factor
- 5) Enter corrected values in Column 2.
I d DC0279 211V Y " ' - ' - ---.,e- - - , -- ., -- , . . , , . .
E7 . Page 2 of 2 i TITLE: CALCULATION OF POWER-CORRECTED SOURCE INVENTORIES FOR CONSTANT POWER LEVELS ATTACHMENT 6 (Continued)
- 1 2 EQUILIBRIUP. CORRECTED SOURCE SOURCE HALF LIFE INVENTORY INVENTORY NUCLIOE (DAYS) (Ci) (Ci) l GAP INVENTORY Kr-87 5.28E-2 3.9E+4 Xe-133 5.4E0 1.3E+6 I-131 8.0E0 8.0E+5 I-133 8.75E-1 _5.1E+5 FUEL PELLET INVENTORY Kr-87 5.28 E-2 5.9E+7 !)
Xe-133 5.4E0 1.9E+8 Te-132 3.24E0 1.4E+8 Cs-134 7.3E2 3.1E46 Ba-140 1.28E1 1.8E+8 La-140 1.66E0 1.8E+8 1-131 8.0E0 9.7E+7 i 1-133 8.75E-1 1.88E+8
- 4. Proceed to step 2.f.4.
OCO279 221V v --
PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 4 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT NOS.1 AND 2 . TITLE: SOURCE INVENTORY POWER CORRECTION FOR VARIABLE POWER HISTORY ATTACHMENT 7 I When the power level has not been relatively constant for the last 30 days, nuclides of interest have not had enough time to build up to equilibrium levels. Due to the production characteristics of Cs-134, a special consideration is used to determine its Power Correction Factor.
- 1) The effects of each significant power change must be taken into account for .
each isotope, except for Cs-134, by using Equation I. t t PF4=IP3 3 (1-e i 33),-14 2j Eq. I HP Where: PF4 = 30-day power correction factor for Nuclide i P) = average power level (Mwt) for time Period J RP = Rated Pcwer level of core (Mwt) RP = 3338 Mwt Unit 1 RP = 3411 Mwt Unit 2 A i = nuclear decay constant for Nuclide i
*1j = length of time Period j t
2j = time from end of time Period j to end of 30-day period.
- 2) For Cs-134 Figure 8 is used to determine the Power Correction Factor. io use Figure 8, the average power during the entire operating period is required.
- 3) To determine Corrected Source Inventory the following steps should be completed:
a) For Cs-134
- 1. Determine average power during the entire operating period.
- 2. Detemine operation time in days.
- 3. Use Figure 8 to determine Power Correction Factor.
- 4. Record the results in Column B of this form, b) For the remaining isotopes
- 1. Detemine power correction factor for each nuclide using Eq. I.
See the sample provided.
- 2. Record the result for each nuclide in column B of this form.
DC0279 231V
l l r . Page 2 of 4 i TITLE: SOURCE INVENTORY POWER CORRECTION FOR VARIABLE POWER HISTORY ATTACHMENT 7 (Continued) c) Corrected Source Inventory for each nuclide in column D can be determined as follows: Corrected Source Inventory = Column B x Column C.
- 1. Record the results for each nuclide in column D.
d) Proceed to step 2.f.4. Sample power correction factor calculation: The Plant has operated for the 30 days prior to the accident with the ' following power history: 100 Mwt for 10 days 70 ht for 5 days 0 Nt for 7 days 70 N t for 8 days . 100 70 30 Day Power History' Prior to Accident 0 0 10 15 22 30 . For time Period 1, P = 100, t = 10 days, t21 = 20 days 1 il For time Period 2, P2 = 70, t12 = 5 days, t22 = 15 days For time Period 3, P3 = 0.0, t13 = 7 days, t23 = 8 days For time Period 4, P = 70, t g4 = 8 days, t = 0 days 4 24 DC0279 24IV
Page 3 of 4 TITLE: SOURCE INVENTORY POWER CORRECTION FOR VARIABLE POWER HISTORY _ ATTACHMENT 7 (Continued) The equation for Nuclide i would be: PF = ([100 (1-e At (10 days)),-Ag(20 days)) 4
+ [ 70 (1-e-Ai (5 days)),-Ag (15 days))
+ [0.0 (1-e-Ai (7 days)),-Ag (8 days))
+[70 (1-e-Ai (8 days)),-19 (0 days)]) /RP % t)
DC0279 25IV
Page 4 of 4 TITLE: SOURCE INVENTORY POWER CORRECTION FOR VARIABLE POWER HISTORY ATTACHMENT 7 (Continued) CORRECTION FOR VARIABLE POWER LEVEL A B C D Power Equilibrium Corrected Decay Correction Source Source Constant Factor Inventory Inventory NUCLIDE (day-1) (PF4 ) (Ci) (C1) Gap Inventory . Kr-87 13.10 3.9E+4 Xe-133 0.13 1.3E+6 I-131 8.62X10~A 8.0E+5 ) 1-133 7.92x10~ 5.1E+5 Fuel Pellet Inventory Kr-87 13.10 5.9E+7 Xe-133 0.13 1.9E+8 Te-132 2.13X10"A 1.4E+8 Cs-134 9.21X10~4 3.1E+6 Ba-140 5.42X10-2 1.6E+8 La-140 4.15X10~1 1.8E+8 1-131 8.62X10~ 9.7E+7 1-133 7.92x10-2 1.88E+8 DC0279 261V
, 0; PACIFIC GAS AND ELECTRIC COMPANY Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DIABLO CANYON POWER PLANT UNIT N05.1 AND 2 TITLE: COMPARISON OF EXPECTED AND ACTUAL SOURCE INVENTORIES ATTACHMENT 8
- 1. Copy both the total water and airborne inventories into Columns 1 and 2 of the attached Form.
- 2. Total Release Inventory for each nuclide, Column 3, can be determined as follows:
Total Release Inventory = Column 1 + Column 2.
- 3. Record the results of step 2 in Colurn 3.
- 4. Copy the expected source inventory into Column 4 from Attachment 6 or 7.
- 5. The percen: of each nuclide released, Column 5, can be determined as follows: ,
Percent Released = Column 3 Column 4
- 6. Record the results of step 5 in Column 5.
- 7. Determine and record iodine and noble gas ratios by using the respective g
totals in Columm 3. Iodine Ratio = h Noble Gas Ratio = Xe[{ (B)
- 8. Proceed to step 2.f.5.
DC0279 261V
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Page 2 of 2 TITLE: COMPARISON OF EXPECTED AND ACTUAL SOURCE INVENTORIES ATTACHMENT 8 3 4 5 1 2 Expected Total Total Total Source Water Airborne Released Inventory (C1) Inventory Inventory Inventory (Attachment 3 Percent (C1) or 4) Released Isotope (Attachment 1) (Attachment 2) Gas Gap Inventory Kr-87 Xe-133 1-13 1 I-13 3 Average % Fuel Pellet Inventory
)
Kr-87 Xe-133 I -13 1 1-133 Cs-134 Te-132 Ba-140 La-140 Average %
*Do not use for calculating " average Check One:
No damage percent". Use only for qualitative GAP release assessment on Attachment 6. Fuel melt l DC0279 281V
f o 4 RAC2FIC GAS AND ELECTRIC COMPANY Page 1 of 2 DEPARTMENT OF NUCLEAR PLANT OPERATIONS DI ABLO CANYON POWER PLANT UNIT NOS.1 AND 2 TITLE: QUALITATIVE ASSESSMENT ATTACHMENT 9
- 1. For each nuclide listed on the attached worksheet, check the box which corresponds to the inventory percentage found on attachment 8. Circle the applicable iodine and noble gas ratio determined in Attachment 8, step 7.
- 2. To best determine the category of damage, concentrate on the presence or absence of key nuclides (e.g. , Te, Cs, Ba, La).
- 3. The general location of the marks should give an indication of the type of core damage.
! 4. Enter the type of damage that has been determined on Attachment 8, and proceed to step 2.f.6. NOTE: If Ag-110m was found in any of the samples, it is a good i ndicator of fuel melt (Ag is from the control rods). f DC0279 291V
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